ATOMIC ENERGY &S& L ENERGIE ATOMIQUE OF … · OF Am21*1 FROM KILOGRAM AMOUNTS OF PLUTONIUM (Report CRC-661) . Atomic Energy of Car«ida Limited Report, AECL-353 (1956). 16. W.M

AECL-6425 Rev. 1

ATOMIC ENERGY & S & L ENERGIE ATOMIQUEOF CANADA LIMITED V A j r DU CANADA, LIMITEE

FUEL CYCLES: A BIBLIOGRAPHY OF AECL PUBLICATIONS

CYCLES DES COMBUSTIBLES: BIBLIOGRAPHIE DE L'EACL

Compiled by/Compilee par

N. J. Hawley

Whiteshell Nuclear Research Etablissement de recherchesEstablishment nucleaires de Whiteshel!

Pinawa, Manitoba ROE 1LOMay 1983 mai

Copyright © Atomic Energy of Canada Limited, 1983

ATOMIC ENERGY OF CANADA LIMITED


Compiled by

N.J. Hawley

Whiteshell Nuclear Research EstablishmentPinawa, Manitoba ROE 1LO

1983 MayAECL-6425 Rev. 1

(•

CYCLES DES COMBUSTIBLES: BIBLIOGRAPHIE DE L'EACL

Compilée par

N.J. Hawley

RESUME

Les publications de l'EA X qui proviennent de la littérature

accessible au public et tratient des combustibles et cycles des combus-

tibles sont énumérees dans cette bibliographie. L'index qui l'accompagne

est par sujet. La bibliographie sera mise à jour périodiquiment.

L'Energie Atomique du Canada LimitéeEtablissement de Recherches Nucléaires de Whiteshell

Pinawa, Manitoba ROE 1L01983 mai

AECL-6425 Rev. 1


Compiled by

N.J. Hawley

ABSTRACT

AECL publications, from the open literature, on fuels and fuel

cycles used in CANDU reactors are listed in this bibliography. The

accompanying index is by subject. The bibliography will be brought up

to date periodically.

Atomic Energy of Canada LimitedWhiteshell Nuclear Research Establishment

Pinawa, Manitoba ROE 1L01983 rnai

AECL-6425 Rev. 1

CONTENTS

Page

1. INTRODUCTION

2. AECL REPORTS AND REPRINTS

3. MISCELLANEOUS PUBLICATIONS 26

SUBJECT INDEX 30

1. INTRODUCTION

Since the beginning of AECL, one of the major R & D programs has

been the development of fuels and fuel cycles. This program has been sub-

divided so that many different aspects of this broad subject have been

represented In the research and development activities. Among these aspects

are fuel fabrication, Irradiation and post-irradiation analysis. Although

principal emphasis has been on natural uranium In a once-through cycle,

development work has also been done on thorium and enriched fuel cycles.

Fuel recycle, through the reprocessing and refabrlcatlon of fuel, has also

been evaluated for Improved conservation of uranium.

Through ths years, requests have been received for publications

on many of these aspects within the general field. It was therefore felt

that a comprehensive listing should be compiled covering all segments of our

research and development in this area.

This bibliography covers AECL publications that have emerged

from the various fuel and fuel cycle research and development programs. It

includes reports, conference papers and journal articles most of which have

been assigned numbers in the AECL series. Storage and disposal aspects of

the CANDU fuel cycle are documented in a similar report, "Radioactive Haste

Management In Canada: A Bibliography of Published Literature", Atomic

Energy of Canada Limited Report, AECL-6186-Rev.3 (1983).

It is Intended that the listing will be brought up to date

periodically. Suggestions for additions or deletions, if necesssary, will

be welcomed.

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2. AECL REPORTS AND REPRINTS

1. G.C. Laurence, ATOMIC POWER REACTORS AND THEIR FUELS.Chemistry in Canada, 7_, 32 (1955).Also AECL-175.

2. W.B. Lewis, POSSIBILITIES OF GENERATING ATOMIC ELECTRIC POWERAT COMPETITIVE RATES (Report DL-17).Atomic Energy of Canada Limited Report, AECL-178 (1955).

3. J.C. Horsman, ATOMIC POWER REACTORS AND THEIR FUELS.Chemistry in Canada, 7_, 48 (1955).Also AECL-179.

4. W.B. Lewis, REACTIVITY CHANGES EXPECTED AND OBSERVED IN LONGIRRADIATION OF NATURAL URANIUM IN THE NRX REACTOR (ReportDR-21, 1952 declassified 1955).Also AECL-187.

5. W.B. Lewis, CALCULATED REACTIVITY CHANGES IN THE LONG IRRADIA-TION OF NATURAL URANIUM (Report DR-28, 1953 declassified1955).Also AECL-188.

6. W.B. Lewis, NOTE ON THE POSSIBILITIES OF URANIUM-PLUTONIUMREGENERATIVE THERMAL NEUTRON REACTORS.Atomic Energy of Canada Limited Report, AECL-189 (1955).

7. A.M. Aikin, BASIC PROBLEMS IN THE PROCESSING OF NUCLEAR FUELS.Chemistry in Canada, 1_, 44 (1955).Also AECL-192.

8. W.B. Lewis, SOME ECONOMIC ASPECTS OF NUCLEAR FUEL CYCLE.Proceedings of the First International Conference on thePeaceful Uses of Atomic Energy, 3_, 3 (1956).Also AECL-203.

9. D.G. Hurst, EXPERIMENTS ON SOME CHARACTERISTICS OF THE NRXREACTOR - PART I: METHODS AND PROLONGED FUEL IRRADIATION.Proceedings of the First U.N. International Conference on thePeaceful Uses of Atomic Energy, 1956.Also AECL-204.

10. G.W. Hatfield, REPROCESSING OF NUCLEAR. FUELS.Atomic Energy of Canada Limited Report, AECL-259 (1955).

11. W.B. Lewis, ECONOMIC POWER FUELLING WITHOUT U-235 ENRICHMENT.Atomic Energy of Canada Limited Report, AECL-265 (1955).

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12. W.B. Lewis, ATTAINABLE BURN-UP OF URANIUM WITH PLUTONIUM RE-CYCLING.Atomic Energy of Canada Limited Report, AECL-285 (1956).

13. W.B. Lewis, THE HEAVY WATER REACTOR FOR POWER (Report DL-25).Atomic Energy of Canada Limited Report, AECL-319 (1956).

14. P.D. Goulden, B.W. Durham and V. Corriveau, TRIBUTYL PHOSPHATEPROCESSING OF Pu-Al ALLOY FUELS, PRELIMINARY INVESTIGATION.Atomic Energy of Canada Limited Report, AECL-348 (1955).

15. J.P. Butler and J.S. Merritt, A BATCH PROCESS FOR THE RECOVERYOF Am21*1 FROM KILOGRAM AMOUNTS OF PLUTONIUM (Report CRC-661) .Atomic Energy of Car«ida Limited Report, AECL-353 (1956).

16. W.M. Campbell, CANADIAN FUEL REPROCESSING.Nucleonics, .14(9), 92 (1956).Also AECL-357.

17. W.B. Lewis, LOW COST FUELLING WITHOUT RECYCLING.Atomic Energy of Canada Limited Report, AECL-382 (1956).

18. W.B. Lewis, CHALK RIVER PROSPECTS FOR ATOMIC POWER. (ReportDR-22 Rev. 2).Atomic Energy of Canada Limited Report, AECL-395 (1957).

19. A.M. Aikiu, ION EXCHANGE RECOVERS PLUTONIUM FROM IRRADIATEDFUELS.Chemical Engineering Progress, 53, 82F (1957).Also AECL-406.

20. A.J. Mooradian, CANADA'S APPROACH TO THE ECONOMIC FUELLING OFNUCLEAR POWER REACTORS.Engineering Journal, 4_0, 121 (1957).Also AECL-416.

21. W.B. Lewis, NATURAL URANIUM - HEAVY WATER REACTORS FOR LOWCOST POWER.Atomic Energy of Canada Limited Report, AECL-417 (1957).

22. H.K. Rae, D.H. Charlesworth, A.R. Bancroft, F.G. Crouch,G.E. Haddeland, E. Mizzan, A.J. Mooradian and E.E. Winter, APRELIMINARY COST ESTIMATE FOR FUEL RECYCLING.Atomic Energy of Canada Limited Report, AECL-418 (1957).

23. D.H. Charlesworth, A PRELIMINARY DESIGN AND COST ESTIMATE FORA DUAL-PURPOSE PROCESSING PLANT.Atomic Energy of Canada Limited Report, AECL-424 (1956).

24. R.G. Hart, TRIBUTYL PHOSPHATE PROCESSING OF PLUTONIUM-ALUMINUMALLOY FUELS.Atomic Energy of Canada Limited Report, AECL-429 (1957).

25. W.B. Lewis, FUELLING SYSTEM FOR NATURAL URANIUM REACTOR WITHLONG RODS FOR HIGH BURN-UP WITHOUT RECYCLING.Atomic Energy of Canada Limited Report, AECL-436 (1957).

26. W.B. Lewis, NATURAL URANIUM AND ENRICHED URANIUM, TECHNICALAND ECONOMICAL ASPECTS.The Industrial Challenge of Nuclear Energy, Organization forEuropean Economic Co-operation, Paris, 1958, Volume II,109-11, 153-154.Also AECL-466.

27. H.K. Rae, FUEL PROCESSING AND RECYCLING FOR NATURAL URANIUMPOWER REACTORS.American Society of Mechanical Engineers Paper 57-NESC-102, 1957.Also AECL-494.

28. W.W. Morgan, THE PROCESSING OF IRRADIATED THORIUM FUELS USINGTRIBUTYL PHOSPHATE - DECALIN.Atomic Energy of Canada Limited Report, AECL-508 (1958).

29. O.J.C. Runnalls and K.L. Wauchope, THE PREPARATION AND SHEATH-ING OF PLUTONIUM-ALUMINIUM FUEL ALLOYS IN THE NRX REACTOR.Atomic Energy of Canada Limited Report, AECL-514 (1957).

30. L.C. Watson, THE PRODUCTION OF U02 FOR CERAMIC FUELS.Atomic Energy of Canada Limited Report, AECL-515 (1957).

31. G.C. Laurence, THE NRU REACTOR (Report CRL-49).Paper given at the meeting of the American Nuclear Society,New York, Oct. 30, 1957.Atomic Energy of Canada Limited Report, AECL-525 (1957).

32. W.B. Lewis, COMMENT OH AMERICAN STANDARD'S "AN EVALUATION OFHEAVY WATER REACTORS FOR POWER" PROJECT SIZE-UP REPORT ASAE-3,October 1, 1957.Atomic Energy of Canada Limited Report, AECL-527 (1957).

33. A.J. Mooradian, CANADA'S APPROACH TO THE ECONOMIC FUELLING OFPOWER REACTORS.Atomic Energy of Canada Limited Report, AECL-528 (1957).

34. W.B. Lewis, HIGH BURN-UP FROM FIXED FUEL.Atomic Energy of Canada Limited Report, AECL-531 (1957).

35. O.J.C. Runnalls, URANIUM DIOXIDE - A PROMISING NUCLEAR FUEL(Report CRL-51 Rev.).Metallurgy Seminar Presented at the University of Toronto andat McMaster University, 1958.Also AECL-553 (Rev.).

36. D.T. Nishimura, STUDY OF THE PROCESS VARIABLES IN THE ANIONEXCHANGE PLUTONIUM SEPARATION PROCESS.Atomic Energy of Canada Limited Report, AECL-556 (1957).

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37. THE CANADIAN STUDY FOR A FULL-SCALE NUCLEAR POWER PLANT.Atomic Energy of Canada Limited Report, AECL-557 (1958).

38. W.B. Lewis, URANIUM OXIDE FUEL OF LOW COST. MANAGEMENT ANDATOMIC ENERGY - Proceedings of a Conference, Chicago, 1958,Atomic Industrial Forum and National Industrial ConferenceBoard, New York, 1958.Also AECL-568.

39. A.R. Bancroft and L.C. Watson, PREPARATION OF URANIUM DIOXIDEFOR USE IN CERAMIC FUELS - PART III: AMMONIUM DIURNATE RE-DUCTION STUDIES.Atomic Energy of Canada Limited Report, AECL-586 (1958).

40. G.H. Chalder, N.F.H. Bright, D.L. Paterson and L.C. Watson,THE FABRICATION AND PROPERTIES OF URANIUM DIOXIDE FUEL.Proceedings of the Second U.N. International Conference on thePeaceful Uses of Atomic Energy, j>, 590 (1958) .Also AECL-602.

41. J.A.L. Robertson, A.S. Bain, A.H. Booth, J. Howieoon,R.F.S. Robertson and W.G. Morison, BEHAVIOUR OF URANIUM OXIDEAS A REACTOR FUEL.Proceedings of the Second U.N. International Conference on thePeaceful Uses of Atomic Energy, 1958.Also AECL-603.

42. D.S. Craig, G.C. Hanna, D.G. Hurst, S.A. Kushnerik, W.B. Lewisand A.G. Ward, LONG IRRADIATION OF NATURAL URANIUM.Proceedings of the Second U.N. International Conference on thePeaceful \J~.<*.F, of Atomic Energy, 1958.Also AECL-615.

43. H.A. Smith, W.M. Walker, N.L. Williams and E. Critoph, A STUDYOF A FULL-SCALE URANIUM AND HEAVY WATER NUCLEAR POWER PLANT.Proceedings of the Second U.N. International Conference on thePeaceful Uses of Atomic Energy, 1958.Also AECL-618.

44. W. Boyd and F.W. Gilbert, THE NRU REACTOR.Atomic Energy of Canada Limited Report, AECL-621 (1958).

45. W.B. Lewis, COST COMPARISONS FOR ENRICHED VERSUS NATURALURANIUM FUEL AND FOR ZIRCONIUM VERSUS STAINLESS STEEL FUELSHEATHING IN BI-DIRECTIONAL SLUG FUELLED REACTORS.Atomic Energy of Canada Limited Report, AECL-651 (1958).

45. D.E. McKenzie, W.L. Elsdon and J.W. Fletcher, THE EXTRACTIONOF PLUTONIUM FROM NEUTRON-IRRADIATED URANIUM BY URANIUM TRI-CHLORIDE AND BY MAGNESIUM CHLORIDE.Canadian Journal of '".hsmistry, _3J>, 1233 (1958) .Also AECL-656.

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47. E. Yatabe and L.C. Watson, PREPARATION OF U02 FOR USE IN CE-RAMIC FUELS - PART II: CONTINUOUS PRECIPITATION OF AMMONIUMDIURANATE.Atomic Energy of Canada Limited Report * AECL-662 (1958).

48. W.B. Lewis, INITIAL FUELLING OF POWER REACTORS.Atomic Energy of Canada Limited Report, AECL-696 (1958).

49. W.B. Lewis, ECONOMICS OF URANIUM AND THORIUM IN THE GENERATIONOF ELECTRICITY.Canadian Sectional Meeting of the World Power Conference,Montreal, 1958.Also AECL-704.

50. R.F.S. Robertson, SOME PROCEDURES FOR THE EVALUATION OF REAC-TOR FUELS AND SHEATHING MATERIALS AT CHALK RIVER.Canadian Journal of Chemical Engineering, 3£, 213 (1958).Also AECL-709.

51. W.B. Lewis, URANIUM DIOXIDE,Atomic Energy of Canada Limited Report, AECL-733 (1958).

52. O.J.C. Runnalls, URANIUM DIOXIDE FUEL ELEMENTS.Atomic Energy of Canada Limited Report, AECL-754 (1959).

53. R.G. Hart, J.A. Brothers and I.W. Allam, THE CHEMISTRY OF THEANICN EXCHANGE PROCESS FOR THE RECOVERY OF PLUTONIUM.Atomic Energy of Canada Limited Report, AECL-755 (1958).

54. W.T. Bourns and L.C. Watson, PREPARATION OF URANIUM DIOXIDEFOR USE IN CERAMIC FUELS - PART I: BATCH PRECIPITATION OFAMMONIUM DIURANATE.Atomic Energy of Canada Limited Report, AECL-757 (1958).

55. W.W. Morgan, W.G. Mathers and R.G. Hart, PROCESSING OF IRRA-DIATED REACTOR FUELS - EFFECT OF DIBUTYL PHOSPHATE IN THETRIBUTYL PHOSPHATE PROCESSING SYSTEM.Industrial and Engineering Chemistry, .51, 817 (1959).Also AECL-821.

56. O.J.C. Runnalls, ECONOMIC FUELLING WITH URANIUM DIOXIDE.Atomic Energy of Canada Limited Report, AECL-808 (1959).

57. J.A.L. Robertson, /Kde IN FUEL IRRADIATIONS.Atomic Snergy of Canada Limited Report, AECL-807 (1959).

58. G.H. Chalder, FUEL FABRICATION STUDIES RELATED TO THE NPDREACTOR.Atomic Energy of Canada Limited Report, AECL-836 (1959).

59. D.L. Patterson and G.H. Chalder, THE INTEGRAL FABRICATION OFURANIUM DIOXIDE FUEL ELEMENTS BY ROTARY SWAGING.Atomic Energy of Canada Limited Report, AECL-841 (1959).

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60. C.B. Elgham, G.C. Hanna and P.R. Tunnicliffe, THE DETERMINA-TION OF 23SU BURNUP BY COUNTING METHODS (Report CRR-861).Atomic Energy of Canada Limited Report, AECL-924 (1959).

61. J. Kowieson, ECONOMICS OF THE NATURAL- URANIUM FUEL CYCLE.The Industrial Challenge of Nuclear Energy III - Stress Con-ference, Paris, Organization for European Economic Co-opera-tion, 1960.Also AECL-928.

62. Symposium on Equipment Manufacturing and Development Problemsfor Nuclear Power Systems, Chalk River, 1960. Contains thefollowing papers:C.A. Mawson, MANAGEMENT OF RADIOACTIVE WASTE.A.J. Mooradian, PROBLEMS IN FUEL ELEMENT DESIGN.Also AECL-990.

63. D.R. MacKenzie, DETERMINATION OF 235U BURNUP IN IRRADIATEDNATURAL URANIUM BY CHEMICAL AND COUNTING METHODS.Talanta, j5, 72 (I960).Also AECL-1025.

64. M.F. Duret, REACTIVITY AND FUEL BALANCE IN RECYCLED PLUTONIUMREACTORS.Atomic Energy of Canada Limited Report, AECL-1070 (1955)revised 1960.

65. Nuclear Canada Issue - Nucleonics, 1£_, 1960. This issue con-tains: A.J. Mooradian and J.A.L. Robertson, CANDU FUELLINGCOSTS - BREAKING THE 1-Mill/kwh BARRIER.J.S. Foster, W.rf. Brown and H.E. Tilbe, ON-POWER REFUELLING.W.B. Lewis, COMPETITITVE NUCLEAR POWER FOR CANADA.Also AECL-1080.

66. J.A.L. Robertson, SOME CONSEQUENCES OF EXCESS OXYGEN IN U02.Proceedings of the Symposium on Radiation Effects in Refrac-tory Fuel Compounds - A.S.T.M. Special Technical Publication,306, 3 (1961).Also AECL-1123.

67. G.H. Chalder, PROBLEMS IN THE USE OF THIN ZIRCALOY CLADDINGFOR URANIUM DIOXIDE FUEL.Proceedings of a Symposium on Fuel Element Fabrication,Vienna, 1960, 1., 57 (1961).Also AECL-1145.

68. J.L. Gray, A CANADIAN APPROACH TO NUCLEAR POWER.Symposium on Nuclear Power, Bombay January, 1961.Also AECL-1155.

69. W G. Mathers, E.E. Winter, L.C. Cornett, B.M. Mitchell andR.C. Cairns, A MINIATURE EXTRACTION PLANT FOR FUEL PROCESSING.Atomic Energy of Canada Limited Report, AECL-1169 (1960).

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70. R.G. Hart, M. Lounsbury and CD, McKay, A COMPARISON OF METHODSOF DETERMINING BURN-UP ON URANIUM DIOXIDE FUEL TEST SPECIMENS.Atomic Energy of Canada Limited Report, AECL-117.6 (1961).

71. A.S. Bain, J.A.L. Robertson and A. Ridal, U02 IRRADIATIONS OFSHORT DURATION, PA1T II.Atomic Energy of Canada Limited Report, AECL-1192 (1961).

72. A. Ridal, A.S. Bain and J.A.L. Robertson, IRRADIATION OF NON-STOICHIOMETRIC URANIUM OXIDE IN SHORT DURATIONS.Atomic Energy of Canada Limited Report, AECL-1199 (1961).

73. W.T. Bourns, PREPARATION OF UO2 PELLETS CONTAINING FLUORIDE.Atomic Energy of Canada Limited Report, AECL-1201 (1961).

74. M.J.F. Notley and J.A.L. Robertson, ZIRCALOY-UO2 FAILURES TIEDTO FLUORIDES.Nucleonics, 3J3/3), 77 (1961).Also AECL-1218.

75. J.A.L. Robertson, UNDERSTANDING UO2 FUEL ELEMENTS.Atorapraxis, h_, 121 (1961).Also AECL-1221.

76. M.F. Duret, THE EFFECT OF BI-DIRECTIONAL FUELLING ON REAC-TIVITY.Atomic Energy of Canada Limited Report, AECL-1235 (1961) .

77. W.W. Morgan, R.G, Hart, R.W. Jones and W.J. Edwards, A PRE-LIMINARY REPORT ON RADIAL DISTRIBUTION OF FISSION-PRODUCTXENON AND CESIUM IN U02 FUEL ELEMENTS.Atomic Energy of Canada Limited Report, AECL-1249 (1961).

78. T.I. Jones, ALUMINIUM-PLUTONIUM FUELS: AN INITIAL ASSESSMENTOF ALUMINIUM-PLUTONIUM ALLOYS FOR WATER-COOLED POWER REACTORS.Plutonium 1960: Proceedings of the Second International Con-ference on the Metallurgy of Plutonium, Grenoble, 1960, 720(1961).Also AECL-1275.

79. M.L. Watson, THE ASSEMBLY AND TESTING OF EXPERIMENTAL FUELELEMENTS FOR IRRADIATION TESTING.Atomic Energy of Canada Limited Report, AECL-1288 (1961).

80. W.B. Lewis, OPTIMIZING ORGANIC-LIQUID-COOLED HEAVY-WATERNATURAL-URAN7TJM REACTOR DESIGN FOR SHUT-DOWN REFUELLING.Atomic Energy of Canada Limited Report, AECL-1291 (1961).

81. W.T. Bourns an.̂ L.C. Watson, PREPARATION OF URANIUM DI0XID5FOR USE IN CERAMIC FUELS - PART IV: STUDIES OF MICRONIZEDUh .ilUM TRIOXIDE.Atomic Energy of Canada Limited Report, AECL-1311 (1961).

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82. W.T, Bourns and L.C. Watson, PREPARATION OF URANIUM DIOXIDEFOR USE IN CERAMIC FUELS - PART V: THE ENRICHED URANIUMDIOXIDE PLANT.Atomic Energy of Canada Limited Report, AECL-1312 (1961).

83. G.H. Chalder, AECL SPECIFICATIONS ON URANIUM DIOXIDE.Atomic Energy of Canada Limited Report, AECL-1327 (1961).

84. W.B. Lewis and O.J.C. Runnalls, AN ASSESSMENT OF PLUTONIUM USE.Presented at the American Nuclear Society Meeting on Plutoniumas a Reactor Fuel, Hanford, 1962.Also AECL-1608.

85. O.J.C. Runnalls, PLUTONIUM FUEL PROGRAM IN CANADA.Presented at the American ITuclear Society Meeting on Plutoniumas a Reactor Fuel, Hanford, 1962.Also AECL-1620.

86. A.J. Mooradian, ECONOMIC FUEL FOR CANDU.Transactions of the Sixth World Power Conference, Melbourne,1962.Also AECL-1647.

87. The Engineering Design and Operation of the NPD Reactor,Papers Given at the Winter Meeting, American Nuclear Society,Washington, 1962:W.M. Brown, THE NPD ON-POWER FUELLING SYSTEM.Transactions of the American Nuclear Society, _5, 447 (1962).J.A. Matthew, FUEL MANUFACTURING DEVELOPMENT IN THE NPD REACTOR.Transactions of the American. Nuclear Society, _5̂ 446 (1962).Also AECL-1682.

88. W.B. Lewis, BREEDERS ARE NOT NECESSARY - A COMPETING OTHER WAYFOR NUCLEAR ELECTRIC POWER.Europa Nucleare, j6(3), 13 (1963).Also AECL-1686.

89. Papers Presented by AECL to the International Conference ofthe Canadian Nuclear Association, Ottawa., 1962:F.S. Hummel, B.C. Stonehill and C.E. Beynon, REFUELLING ANDFUEL HANDLING FOR CANDU REACTOJ.A.L. Robertson, ZIRCALOY-"T TJEL: ITS PRESENT LIMI-TATION AND FUTURE POTENTIAT

Also AECL-1692.

90. S.V.K. Rao, INVESTIGATION Oi ...O2-U02 AS A NUCLEAR FUEL.Atomic Energy of Canada Limited Report, AECL-1785 (1963).

91. A.M. Aikin, M. Moss and T. Bruce, THE EXTRACTION OF PLUTONIUMWITH TRIETHYLENE GLYCOL DICHLORIDE.Atomic Energy of Canada Limited Report, AECL-1786 (1963).

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92. D.R. HacKenzie, EXTRACTION OF PLUTONIUM BY HEXONE FROM AQUEOUSSOLUTIONS CONTAINING NITRIC ACID.Atomic: Energy of Canada Limited Report, AECL-1787 (1963) .

93. R.G. Harf., M. Lounsfaury, R.W. Jones and M.J.F. Notley, A COM-PARISON OF METHODS OF DETERMINING BURNUP ON URANIUri DIOXIDEFUEL TEST SPECIMENS.Nuclear Science and Engineering, 18_, 6 (1964).Also AECL-1876.

94. W.B. Lewis, FUELLING HIGH CONVERSION RATIO REACTORS.Presented at the E.A.E.S. Symposium, Baden-Baden, 1963.Also AECL-1911.

95. W.B. Lewis, HOW MUCH OF THE ROCKS AND THE OCEANS FOR ,'OWER?EXPLOITING THE URANIUM-THORIUM FISSION CYCLE.Atomic Energy of Canada Limited Report, AECL-1916 (1964).

96. G.P.L. Williams, NUCLEAR FUEL IN CANADA.Atomic Energy of Canada Limited Report, AECL-1951 (1964).

97. G.M. James, NRU CONVERTS TO ENRICHED CORE.Canadian Nuclear Technology, 3_(2), 57 (1964).Also AECL-1967.

98. W.B. Lewis and T.G. Church, ELECTRICITY SUPPLY IN CANADA ANDTHE ROLE OF NUCLEAR POWER.Proceedings of the Third U.N. International Conference on thePeaceful Uses of Atomic Energy, Geneva, 1964.Also AECL-2001.

99. G.A. Pon, W.B. Lewis, L.R. Haywood, D.B. Primeau, G.J. Phillipsand E.E. Merlo, PROSPECTIVE D2O-MODERATED POWER REACTORS.Proceedings of the Third U.N. International Conference on thePeaceful Uses of Atomic Energy, Geneva, 1964.Also AECL-2010.

100. R.D. Page, D.G. Hardy, A.J. Mooradian, J. Howieson, G.R. Fan-joy and D.B. Nazzer, ENGINEERING AND PERFORMANCE OF UO2 FUELASSEMBLIES.Proceedings of the Third U.N. International Conference on the:Peaceful Uses of Atomic Energy, Geneva, 1964.Also AECL-2018.

101. D.G. Boxall, W.M. Brown, D.B. Nazzer, J.T. Rogers, R.G. Hartand K.L. Smith, DEVELOPMENT OF FUEL AND COOLANT TUBES FOR AREACTOR COOLED BY ORGANIC LIQUID.Proceedings of the Third U.N. International Conference on thePeaceful Uses of Atomic Energy, Geneva, 1964.Also AECL-2023.

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102. M.F. Duret, R.W. Durham, M. Lounsbury, A. Okazakl, W.H. Walker,A.G. Ward and L. Pease, FUEL BURNUP AND REACTIVITY CHANGES.Proceedings of the Third U.N. International Conference on thePeacelul uses of Atomic Energy, Geneva, 1964.Also AECL-2026.

103. O.J.C. Runnalls, PLUTONIUM FUELS FOR THERMAL REACTORS.Atomic Energy of Canada Limited Report, AECL-2102 (1964).

104. M.F. Duret ?nd M.J. Halsall, A PRELIMINARY ASSESSMENT OFTHORIUM AS A FUEL FOR THERMAL REACTORS.Atomic Energy of Canada Limited Report, AJJCL-2290 (1965).

105. R.F.S. Robertson, FUEL, MATERIALS AND COOLANTS FOR WR-1.Taper 66-CNA-311 Presented at the CNA International Confer-ence, Winnipeg, 1966.Also AECL-2553.

106. J. Howieson, A.M. Aikin and J. Pawliw, EVALUATION OF CANDU-PHWFUELS.Paper 66-CNA-312 presented at CNA International Conference,Winnipeg, 1966.Also AECL-2556.

107. W.B. Lewis, COMPARISION OF 21)0Pu AND 236U IN THERMAL FISSIONREACTORS AND ITS RELATION TO LONG TERM IRRADIATION OF NATURALURANIUM.Atomic Energy of Canada Limited Report, AECL-2590 (1951) re-vised 1960.

108. M.J. Halsall, GRAPHS AHD TABLES OF THE ISOTOPIC COMPOSITION OFPLUTONIUM PRODUCED IN CANADIAN D20 MODERATED REACTORS (ReportCRRP-1245 Rev.).Atomic Energy of Canada Limited Report, AECL-2631 (1966) re-vised 1967.

109. A.T. Jeffs, IRRADIATION BEHAVIOUR OF EXPERIMENTAL FUEL ASSEM-BLIES OF UO2-PuO2 AND ThO2-PuO2.Paper presented to IAEA Symposium on the Use of Plutonium asa Reactor Fuel, Brussels, 1967.Atomic Energy of Canada Limited Report, AECL-2672 (1967).

110. A.T. Jeffs, R.R. Boucher and L.R. Norlock, FABRICATION OFU02-Pu02 AND Th02-Pu02 EXPERIMENTAL FUEL.Paper presented at IAEA Symposium on the Use of Plutonium assels, 1967.Atomic Energy of Canada Limited Report, AECL-2675 (1967).

111. R.W. D'-:ham, BURNUP OF CERAMIC FUEL BY GAMMA-RAY SCANNING.Presented at the Symposium on Nuclear Methods of Chemi;alAnalysis, 153rd National American Chemical Society Mpeting,Miami Beach, 1967.Also AECL-2688.

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112. M.J. Halsall, BOUT: A PROGRAM FOR INTEGRATING THE BURNUPEQUATIONS FOR THORIUM AMD URANIUM FUELS.Atomic Energy of Canada Limited Report, AECL-2693 (1967).

113. J. Griffiths, M. Lounsbury and R.W. Durham, URANIUM AND PLUTO-NIUM ISOTOPES IN NPD FUEL BUNDLE 1016.Atomic Energy of Canada Limited Report, AECL-2695 (1967).

114. R.G. Hart, I.E. Oldaker, H.E. Thexton and J.F. Walker, URANIUMDIOXIDE FUELS IN ORGANIC-COOLED REACTORS.Atomic Energy of Canada Limited Report, AECL-2758 (1968).

115. M.J. Halsall, THE EFFECTIVE SURFACE AREA OF FUEL CLUSTERS FOP.RESONANCE INTEGRAL CALCULATIONS.Atomic Energy of Canada Limited Report, AECL-2775 (1967).

116. P.O. Perron, ON THE CHEMICAL STABILITY OF UO2~ AND PuO2-FUELLED GRAPHITE.Atomic Energy of Canada Limited Report, AECL-2783 (1968) .

117. J.S. Foster, A CANADIAN VIEW OF THE NATURAL URANIUM HEAVYWATER POWER REACTOR TODAY.Presented at the ANS Conference on Reaccor Operating Experi-ence, Atlantic City, 1967.Also AECL-2790.

118. A.M. Aikin, EXPERIENCE WITH CANDU REACTORS AND THEIR POTENTIAL.Presented at the Conference on Prospects and Problems of NuclearPower Applications in Developing Countries, Santiago, Chile.Atomic Energy of Canada Limited Report, AECL-2795 (1967).

119. G.H. Chalder, W.T. Bourns, M.A. Feraday and J. Veeder, U3SiAS A NUCLEAR FUEL.Paper presented at CNA Annual Conference, Montreal, 1967.Atomic Energy of Canada Limited Report, AECL-2874 (1967).

120. R.G. Hart, TECHNOLOGICAL PROGRESS IN CANADIAN NUCLEAR FUELS.Presented at the Nuclear Congress of Rome, 1967.Atomic Energy of Canada Limited Report, AECL-2928 (1967).

121. M.F. Duret, PLUTONIUM PRODUCTION AND RECYCLE IN HEAVY-WATERREACTORS.Paper presented at the IAEA Symposium on Heavy-Water PowerReactors, Vienna, 1967.Atomic Energy of Canada Limited Report, AECL-2944 (1968).

122. M.J.F. Notley and A.D. Lane, FACTORS AFFECTING THE DESIGN OFRODDED U02 FUEL BUNDLES FOR HIGH POWER OUTPUTS.Paper presented at the IAEA Symposium on Heavy-Water PowerReactors, Vienna, 1967.Atomic Energy of Canada Limited Report, AECL-2945 (1968).

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123. L.R. Haywood and A.M. Alkin, COSTS AND ECONOMICS OF HEAVY-WATER MODERATED NUCLEAR PLANTS.Paper presented at the IAEA Symposium on Heavy-Water PowerReactors, Vienna, 1967.Atomic Energy of Canada Limited Report, AECL-2946 (1968).

124. W.E. Lewis, OUTLOOK FOR HEAVY-WATER REACTORS.Paper presented at the IAEA Symposium on Heavy-Water PowerReactors, Vienna, 1967.Atomic Energy of Canada Limited Report, AECL-2947 (1968).

125. R.D. Page, ENGINEERING AND PERFORMANCE OF CANADA'S U02 FUELASSEMBLIES FOR HEAVY-WATER POWER REACTORS.Paper presented at the IAEA Symposium on Heavy-Water PowerReactors, Vienna, 1967.Atomic Energy of Canada Limited Report, AECL-2949 (1968).

126. M.A. Feraday, G.H. Chalder and K.D. Cotnam, IRRADIATION BEHA-VIOR OF CORED U3Si FUEL ELEMENTS.Nuclear Applications, k_, 148 (1968).Also AECL-3006.

127. W.B. Lewis, ECONOMIC RELATIONS BETWEEN FAST AND HEAVY-WATERPOWER REACTORS.Paper presented at the American Nuclear Society Meeting,Detroit, Mich., 1967.Atomic Energy of Canada Limited Report, AECL-3066 (1970).

128. The Twelfth AECL Symposium on Atomic Power, Ottawa, 1968,contains the following:A.J. Mooradian, CANADIAN NUCLEAR FUEL - CHALLENGES MET ANDPENDING.W.B. Lewis, LOOK TO THE FUTURE.Also AECL-3067.

129. R.D. Page and A.D. Lane, THE PERFORhfV-'̂ E OF ZIRCONIUM ALLOYCLAD U02 FUEL FOR CANADIAN PRESSURIZED AND BOILING WATER POWERREACTORS.Presented at the joint ANS/CNA Conference, Toronto, 1968.ANS/CNA Transactions, LI, 1:9 (1968).Also AECL-3068.

130. W.B. Lewis, THE SUPER-CONVERTER OR VALUBREEDER. A NEAR BREEDERURANIUM-THORIUM NUCLEAR FUEL CYCLE.Atomic Energy of Canada Limited Report, AECL-3081 (1968).

131. M.A. Feraday, G.H. Chalder and K.D. Cotnam, IRRADIATION BEHA-VIOR OF SOLID AND HOLLOW UjSi FUEL ELEMENTS: RESULTS TO15 000 MWd/TONNE U.Atomic Energy of Canada Limited Report, AECL-3111 (1969).

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132. O.J.C. Runnalls, URANIUM USE IN CANDU REACTORS - REVIEW ANDPROSPECT.Presented at CIM Annual General Meeting, Montreal, 1969.Atomic Energy of Canada Limited Report, AECL-3114 (1969).

133. D.D. Stewart, THE CANADIAN INCENTIVE FOR FUEL REPROCESSING ANDPLUTONIUM RECYCLE.Presented at the ANS/CNA Joint Annual Meeting - Panel Dis-cussion -- Plutonium, a Nuclear Fuel Resource, Toronto, 1968.Atomic Energy of Canada Limited Report, AECL-3136 (1968).

134. W.B. Lewis, IMMEDIATE RELATION OF ING TO FAST BREEDER REACTORPROGRAMS.Atomic Energy of Canada Limited Report, AECL-3251 (1969).

135. W.B. Lewis and J.S. Foster, CANADIAN OPERATING EXPERIENCE WITHHEAVY-WATER POWER REACTORS.Atomic Energy of Canada Limited Report, AECL-3569 (1970).

136. I.J. Hastings and R.L. Stoute, TEMPERATURE-DEPENDENT SWELLINGIN IRRADIATED U3Si FUEL ELEMENTS.Journal of Nuclear Materials, 3]_, 295 (1970).Also AECL-3713-

137. M.F. Duret, PLUTONIUM RECYCLE IN CANDU-TYPE PHW HEAVY WATERREACTORS.Atomic Energy of Canada Limited Report, AECL-3910 (1971).

138. I.J. Hastings, BURNUP AND TEMPERATURE DEPENDENCE OF SWELLINGIN U3Si.Journal of Nuclear Materials, 4JL, 195 (1971).Also AECL-3949.

139. R.G. Hart, L.R. Haywood and G.A. Pon, CANDU NUCLEAR POWERSYSTEM: COMPETITITVE FOR THE FORESEEABLE FUTURE.Paper presented at the Fourth U.N. International Conference onthe Peaceful Uses of Atomic Energy, Geneva, 1971.Atomic Energy of Canada Limited Report, AECL-3975 (1971).

140. L.R. Haywood, J.A.L. Robertson, J. Pawliw, J. Howieson andL.L. Bodie, FUEL FOR CANADIAN POWER RfciACTORS.Paper presented at the Fourth U.N. International Conference onthe Peaceful Uses of Atomic Energy, Geneva, 1971.Atomic Energy of Canada Limited Report, AECL-3979 (1971).

141. W.B. Lewis, M.F. Duret, D.S. Craig, J.I. Veeder and A.S. Bain,.LARGE-SCALE NUCLEAR ENERGY FROM THE THORIUM CYCLE.Paper presented at the Fourth U.N. International Conference onthe Peaceful Uses of Atomic Energy, Geneva, 1971.Atomic Energy of Canada Limited Report, AECL-3980 (1971).

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142. J.R. MacEwan, A.S. Bain, M.J.F. Notley and R.W. Jones, IRRA-DIATION EXPERIENCE WITH FUEL FOR POWER REACTORS.Presented at the Fourth U.N. International Conference on thePeaceful Uses of Atomic Energy, Geneva, 1971.Atomic Energy of Canada Limited Report, AECL-3981 (1971).

143. M.F. Duret, J. Griffiths, R. Bir, M. Chabrillac and R. Vidal,PLUTONIUM PRODUCTION IN NPD: A COMPARISON BETWEEN EXPERIMENTAND CALCULATION.Atomic Energy of Canada Limited Report, AECL-3995 (1971).

144. I.J. Hastings, J.R. MacEwan and L.R. Bourque, SWELLING INU3S1: THERMAL CONDUCTIVITY AND POST-IRRADIATION DENSIFICATION.Journal of American Ceramic Society, _5_5, 240 (1972).Also AECL-4173.

145. R.W. Dyck and D.G. 3oase, FUEL REPROCESSING WITH TERTIAR"AMINE EXTRACTANTS - PART II: A MANUAL OF ANALYTICAL METHODS.Atomic Energy of Canada Limited Report, AECL-4214 (1973).

146. G.J. Phillips, THE LATREP-PERIGEE SIMULATION OF NPD.Atomic Energy of Canada Limited Report, AECL-4261 (1972) .

147. A.W.L. Segel, ESTIMATING CANDU FUEL COSTS.Presented at the IAEA Study Group Meeting on the Facilitiesand Technology Needed for Nuclear Fuel Manufacture, Grenoble,1972.Atomic Energy of Canada Limited Report, AECL-4273 (1972).

148. A.J. Mooradian, REACTOR DEVELOPMENT (PHW, ABLW, OCR).Proceedings of the 1972 Annual Conference of the CNA, Toronto.Atomic Energy of Canada Limited Report, AECL-4275 (1972).

149. R.W. Durham and V. Corriveau, BURNUP DETERMINATION OF A FUELSTRING BY CHEMICAL AND ISOTOPIC ANALYSES.Atomic Energy of Canada Limited Report, AECL-4313 (1973).

150. L.J. Clegg and J.R. Coady, RADIOACTIVE DECAY PROPERTIES OFCANDU FUEL. VOLUME I: THE NATURAL URANIUM FUEL CYCLE. PART1, STARTING MATERIALS: URANIUM ORE, SEPARATED URANIUM ANDURANIUM MILL TAILINGS AND PART 2, IRRADIATED FUEL.Atomic Energy of Canada Limited Report, AECL-4436/1 (1977).

151. L.J. Clegg and J.R. Coady, RADIOACTIVE DECAY PROPERTIES OFCANDU FUEL. VOLUME I: THE NATURAL URANIUM FUEL CYCLE. PART3, REPROCESSED FUEL: PLUTONIUM PRODUCT AND HIGH LEVEL WASTE.Atomic Knergy of Canada Limited Report, AECL-4436/2 (1977).

152. D. Hamel, REACTIVITY COEFFICIENTS IN A NATURAL URANIUM CARBIDEFUELLED, HEAVY WATER MODERATED, ORGANIC LIQUID COOLED REACTOR.Atomic Energy of Canada Limited Report, AECL-4440 (1973).

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153. R.W. Jones and J.L. Crosthwaite, URANIUM CARBIDE FUEL FORORGANIC COOLED REACTORS.Atomic Energy of Canada Limited Report, AECL-4443 (1973).

154. W.B. Lewis, M.F. Duret, D.S. Craig, J.I. Veeder and A.S. Bain,LARGE-SCALE NUCLEAR ENERGY FROM THE THORIUM CYCLE.Transcript of an oral presentation at the Fourth U.N. Interna-tional Conference on the Peaceful Uses of Atomic Energy,Geneva, 1971, 49/P/A/157.Atomic Energy of Canada Limited Report, AECL-4445 (1973).

155. A.S. Bain, J.C. Wood and C.E. Coleman, FUEL DESIGNS TO ELIMI-NATE DEFECTS ON POWER INCREASES.Proceedings of the International Conference on Nuclear FuelPerformance, London, 1973.Atomic Energy of Canada Limited Report, AECL-4518 (1973).

156. A.M. Aikin, CANADIAN NUCLEAR POWER.Engineering Journal, 56J3) , 13 (1973).Also AECL-4526.

157. R.B. Lyon, TEMPERATURE COEFFICIENTS OF REACTIVITY FOR NATURALURANIUM FUEL AND URANIUM-PLUS-PLUTONIUM FUEL IN ORGANIC COOL-ANT AND HEAVY WATER MODERATOR.Atomic Energy of Canada Limited Report, AECL-4661 (1974).

158. J.L. Gray, WHY CANDU?Atomic Energy of Canada Limited Report, AECL-4709 (1974).

159. A.J. Mooradian, FUTURE VARIANTS. ON THE CANDU THEME.Presented at the 1973 International Conference of the CNA,Toronto.Energia Nucleare, 21̂ , 209 (1974).Also AECL-4775.

160. I.J. Hastings, IRRADIATION OF U3Si-BASED COMPOUNDS IN THE HIGHVOLTAGE ELECTRON MICROSCOPE.Journal of Nuclear Materials, 56, 76 (1975).Also AECL-4836.

161. I.J. Hastings, BUBBLE-PRECIPITATE INTERACTION ON GRAIN BOUND-ARIES IN IRRADIATED U02.Journal of Nuclear Materials, 5k_, 138 (1974).Also AECL-4876.

162. A.J. Mooradian and O.J.C. Runnalls, CANDU: ECONOMIC ALTERNA- .TIVE TO THE FAST BREEDERS.Presented at the 9th World Energy Conference, Detroit, Michi-gan, 1974.Also AECL-4916.

~ 17 -

163. J.L. Gray, THE CANADIAN NUCLEAR POWER PROGRAMME.British Nuclear Energy Society Journal, 13, 227 (1974).Also AECL-4950.

164. Nuclear Engineering International, Survey of Canada i3_, June(1974) contains the following:R.D. Page and H.R. Lee, FUEL FOR CANDU PRESSURIZED HEAVY-WATERREACTORS, p. 496.A.J. Mooradian, NUCLEAR RESEARCH AND DEVELOPMENT IN CANADA,p. 489.Also AEOL-4965.

165. J.A.L. Robertson, PHYSICAL METALLURGY OF CANDU FUEL."Physical Metallurgy of Reactor Fuel Elements", Proceedings ofan International Conference Organized by the CEGB and BerkeleyNuclear Laboratories, 1973,Atomic Energy of Canada Limited Report, AECL-4968 (1974).

166. I.J. Hastings, D.H. Rose and M.H. Schankula, VOLUME CHANGES INIRRADIATED U02 FUEL.Journal of the American Ceramic Society, 58, 74 (1975).Also AECL-4991.

167. S.R. MacEwen and I.J. Hastings, A MODEL FOR IN-REACTOR DENSI-FICATION OF U02.Philisophical Magazine, 31, 135 (1975).Also AECL-4993.

168. J.L. Gray, NUCLEAR POWER: AN ENERGY SOURCE FOR CANADA.Atomic Energy of Canada Limited Report, AECL-5027 (1972).

169. J.L. Gray, FLEXIBILITY IN FUELLING.Nuclear Active, 12, 6 (1975).Also AECL-5030.

170. M.S. Milgram, A GUIDE TO LATREP - 1975.Atomic Energy of Canada Limited Report, AECL-5036 (1975).

171. C.H. Millar, FUEL MANAGEMENT IN CANDU REACTORS."Nuclear Energy Maturity", Proceedings of the European NuclearConference, Paris, 1975.Atomic Energy of Canada Limited Report, AECL-5090 (1976).

172. A.S. Bain, R.D. Page, G.R. Fanjoy, W.R. Tarasuk and J. Howieson,THE PERFORMANCE AND EVOLUTIONARY DEVELOPMENT OF CANDU FUEL."Nuclear Energy Maturity", Proceedings of the European NuclearConference, Paris, 1975.Atomic Energy of Canada Limited Report, AECL-5091 (1976).

173. S. Banerjee, E. Critoph and R.G. Hart, THORIUM AS A NUCLEARFUEL FOR CANDU REACTORS.Canadian Journal of Chemical Engineering, 53, 291 (1975).Also AECL-5147.

V- 18 -

174. M. Milgram, A. MODEL FOR ESTIMATING FLUX DISTRIBUTIONS IN A(THORIUM FUELLED) THERMAL REACTOR.Atomic Energy of Canada Limited Report, AECL-5180 (1976).

175. S.R. Hatcher, FUEL FOR NUCLEAR POWER IN CANADA: OPTIONSBEYOND THE YEAR 2000.The Canadian Business Review, 2_, 4 (It76) .Also AECL-5217.

176. J.S. Foster, THE STATUS OF THE CANAL*: MI NUCLEAR POWER PROGRAMAND POSSIBLE FUTURE STRATEGIES.Annals of Nuclear Energy, ̂ » 689 (1975) .Also AECL-5225.

177. J.D. Chen, D.G. Boase and R.B. Lypka, NON-DESTRUCTIVE DETERMI-NATION OF BURNUP BY GAMMA-SCANNING: AN ASSESSMENT OF mCe/PrAS A FISSION MONITOR IN CANDU FUELS.Atomic Energy of Canada Limited Report, AECL-5236 (1976).

178. P.F. Caillibot and I.J. Hastings, SIMULATION OF IN-REACTORSWELLING IN U-3.5 w « Si-1.5 wt% Al BY ION BOMBARDMENT.Journal of Nuclear Materials, 59_, 257 (1976).Also AECL-5336.

179. I.J. Hastings and D.H. Rose, EXTRACTION OF PRECIPITATES ASSO-CIATED WITH INTERGRANULAR FISSION GAS BUBBLES IN IRRADIATED U02.Journal of American Ceramic Society, _59_, 168 (1976).Also AECL-5373.

180. K.W. Dormuth and R.F. Lidstone, A STUDY OF THE RUNNING-INPERIOD OF A CANDU-PHW THORIUM CONVERTER.Atomic Energy of Canada Limited Report, AECL-5391 (1977).

181. R.B. Lyon, REDUCTION OF LONG-TERM POTENTIAL HAZARD OF SPENTFUEL FROM CANDU REACTORS BY HEAVY ELEMENT RECYCLES.Atomic Energy of Canada Limited Report, AECL-5395 (1976).

182. S.R. Hatcher, S. Banerjee, A.D. Lane, H. Tamm and J.I. Veeder,THORIUM CYCLE IN HEAVY WATER MODERATED PRESSURE TUBE (CANDU)REACTORS.Presented at the session on 233U-Thorium cycle, ANS WinterMeeting, San Francisco, 1975.Atomic Energy of Canada Limited Report, AECL-5398 (1976).

183. M.H. Schankula and I.J. Hastings, PERFORMANCE OF HIGHLY RATEDUO2 FUEL IN THE WR-1 ORGANIC-COOLED REACTOR.Atomic Energy of Canada Limited Report, AECL-5399 (1977).

184. I.J. Hastings and M^H. Schankula, EFFECT OF RESTRAINT ANDBURNUP ON DIAMETRAL INCREASES IN UO2 ELEMENTS IRRADIATED INORGANIC COOLANT.Journal of Nuclear Materials, 61, 229 (1976).Also AECL-5457.

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185. I.J. Hastings, D.H. Rose and J. Baird, IDENTIFICATION OF PRE-CIPITATES ASSOCIATED WITH INTERGRANULAR FISSION GAS BUBBLES INIRRADIATED U02.Journal of Nuclear Materials, 61, 225 (1976).Also AECL-5458.

186. E. (jritoph, S. Banerjee, F.W. Barclay, D. Hamel, M.S. Milgramand J.I. Veeder, PROSPECTS FOR SELF-SUFFICIENT EQUILIBRIUMTHORIUM CYCLES IN CANDU REACTORS.Trans. Am. Nucl. Soc, 2£, 706 (1975).Also AECL-5501.

187. A.J. Mooradian, CANDU FUEL CYCLES - PRESENT AND FUTURE.Presented at the 9th Annual Conference of the Japan AtomicIndustrial Forum (JAIF), Tokyo, 1976.Atomic Energy of Canada Limited Report, AECL-5516 (1976).

188. N.A. Keller, VALIDATION OF THE KENO AND SU-HAMMER CODES FORPLUTONIUM SYSTEMS.Atomic Energy of Canada Limited Report, AECL-5535 (1976).

189. N.A. Keller, CALCULATION OF FOURTEEN Pu-U CRITICAL EXPERIMENTBENCHMARKS USING KENO AND SU-HAMMER.Atomic Energy of Canada Limited Report, AECL-5539 (1976).

190. M. Milgram, THINGS YOU'VE ALWAYS WANTED TO KNOW ABOUT THEPHYSICS OF THORIUM-FUELLED CANDU'S.Atomic Energy of Canada Limited Report, AECL-5558 (1976).

191. M.S. Milgram and W.H. Walker, SOME PHYSICS PROBLEMS IN THEDESIGN OF THORIUM-FUELLED CANDU REACTORS.Atomic Energy of Canada Limited Report, AECL-5561 (1976).

192. J.B. Slater, AN OVERVIEW OF THE POTENTIAL OF THE CANDU REACTORAS A THERMAL BREEDER.Presented to the IAEA Consultants Meeting on the Status andProspects of Thermal Breeders, Vienna, 1976.Atomic Energy of Canada Limited Report, AECL-5679 (1977).

193. E. Critoph, THE THORIUM FUEL CYCLE IN WATER-MODERATED REACTORSYSTEMS.Presented at the IAEA International Conference on NuclearPower and its Fuv.l Cycle, Salzburg, Austria, 1977.Atomic Energy of Canada Limited Report, AECL-5705 (1977).

194. J.S. Foster and S.H. Russell, CANDU - CANADIAN EXPERIENCE ANDEXPECTATIONS WITH THE HEAVY-WATER REACTOR.Presented at the IAEA International Conference on NuclearPower and its Fuel Cycle, Salzburg, Austria, 1977.Atomic Energy of Canada Limited Report, AECL-5707 (1977).

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195. P.E. Hamel and J.H. Jennekens, REGULATORY CONTROL OF RADIO-ACTIVITY AND NUCLEAR FUEL CYCLE IN CANADA.Atomic Energy of Canada Limited Report, AECL-5708 (1977).

196. G.R. Fanjoy and A.S. Bain, CANDU FUEL - FIFTEEN YEARS OF POWERREACTOR EXPERIENCE.Paper IAEA-CN-36/184 presented at the IAEA International Con-ference on Nuclear Power and its Fuel Cycle, Salzburg, Austria,May 1977.Also AECL-5711.

197. J.S. Foster, FUTURE DEVELOPMENTS IN CANDU.Based on a paper presented to the Nuclear Power Seminar,Calgary Power Limited, 1976.Engineering Journal, January/February 1977.Also AECL-5734.

198. J.S. Foster and E. Critoph, ADVANCED FUEL CYCLES IN HEAVY-WATER REACTORS.Transactions of the American Nuclear Society, 2_5, 187 (1977).Also AECL-5735.

199. M.J.F. Notley, F.R. Campbell, I.J. Hastings and H. Sills, FUELMODELLING: GAP CONDUCTIVITY, GAS BUBBLE SWELLING AND FISSIONGAS RELEASE.ANS Topical Meeting "Water-Reactor Fuel Performance", St. Charles,111., 1977 May.Also AECL-5787.

200. M.J.F. Notley and I.J. Hastings, A MICROSTRUCTURE-DEPENDENTMODEL FOR FISSION PRODUCT GAS RELEASE AND SWELLING IN U02.Atomic Energy of Canada Limited Report, AECL-5838 (1979).

201. J.S. Foster, THE FUTURE FOR CANDU.Presented at the Canadian Nuclear Association 17th AnnualInternational Conference, Montreal, 1977.Atomic Energy of Canada Limited Report, AECL-5842 (1977).

202. S. Banerjee, S.R. H.itcher, A.D. Lane, H. Tamm and J.I. Veeder,SOME ASPECTS OF THE THORIUM FUEL CYCLE IN HEAVY-WATER-MODERATEDPRESSURE TUBE REACTORS.Nuclear Technology, 3±, 58 (1977).Also AECL-5873.

203. G. Yan, J.V.R. L'Archeveque and R.N. Paul, INMACS - AN APPROACHTO ON-LINE NUCLEAR MATERIALS ACCOUNTING AND CONTROL IN A FUELFABRICATION ENVIRONMENT.Presented at the CNA 17th Annual International Conference,Montreal, 1977.Atomic Energy of Canada Limited Report, AECL-5902 (1977).

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204. M.S. Milgram and K.N. Sly, TABLES OF THE ISOTOPIC COMPOSITIONOF TRANSURANIUM ELEMENTS PRODUCED IN CANADIAN D20 MODERATEDREACTORS.Atomic Energy of Canada Limited Report, AECL-5904 (1977).

205. N.A. Keller, VALIDATION OF THE KENO AND SU-HAMMER CODES FORCRITICAL SOLUTION SYSTEMS OF U-233 AND U-235.Atomic Energy of Canada Limited Report, AECL-5917 (1978).

206. D.J. Cameron, A REVIEW OF THE POTENTIAL FOR ACTINIDE REDIS-TRIBUTION IN CANDU THORIUM CYCLE FUELS.Atomic Energy of Canada Limited Report, AECL-5962 (1978).

207. T.T. Vandergraaf, L.M. Carefoot and D.G. Boase, BURNUP DETER-MINATION OF NUCLEAR FUELS USING HEODYMIUM-148.Atomic Energy of Canada Limited Report, AECL-5964 (1978) .

208. P.J. Dyne, R.B. Lyon and D.R. McLean, REGIONAL FUEL-CYCLECENTERS: TECHNICAL AND OPERATIONAL CONSIDERATIONS.In "International Arrangements for Nuclear Fuel Reprocessing",Chapter 8, Ballinger Publishing Company, Cambridge, Mass (1976).Also AECL-6063.

209. S.R. Hatcher and W.W. Morgan, TECHNICAL AND ECONOMICAL CONSID-ERATIONS IN FURL REPROCESSING.In "International Arrangements for Nuclear Fuel Reprocessing",Chapter 3, Ballinger Publishing Company, Cambridge, Mass (1976).Also AECL-6064.

210. J.A.L. Robertson, THE CANDU REACTOR SYSTEM: AN APPROPRIATETECHNOLOGY.Science, lj?9, 657 (1978).Also AECL-6067.

211. S. Banerjee and H. Tamm, URANIUM REQUIREMENTS FOR ADVANCEDFUEL CYCLES IN EXPANDING NUCLEAR POWER SYSTEMS.Nuclear Technology, 41, 244 (1978).Also AECL-6158.

212. S.R. Hatcher, NUCLEAR POWER IN CANADA: STATUS AND PROSPECTS.Atomic Energy of Canada Limited Report, AECL-6173 (1978).

213. M.S. Milgram, POTENTIAL OF AXIAL FUEL MANAGEMENT STRATEGIES INTHORIUM-FUELLED CANDU'S.Prepared for the American Nuclear Society Winter Meeting, SanFrancisco, 1977.Atomic Energy of Canada Limited Report, AECL-6182 (1978).

214. J.D. Chen, R.B. Lypka, D.G. Zetaruk and D.G. Boase, NON-DES-TRUCTIVE DETERMINATION OF BURNUP BY GAMMA-SCANNING: AN AS-SESSMENT OF CESIUM-134/CESIUM-137 ACTIVITY RATIO AS A FISSIONMONITOR IN CANDU FUELS.Atomic Energy of Canada Limited Report, AECL-6192 (1978).

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215. M.F. Duret, INTRODUCING ADVANCED NUCLEAR FUEL CYCLES IN CANADA.Atomic Energy of Canada Limited Report, AECL-6202 (1978).

216. A.W.L. Segel, OUTLINE OF THE CANADIAN R AND D PROGRAM ON THEBEHAVIOUR OF CANDU FUEL BUNDLES IN TRANSIENTS.Atomic Energy of Canada Limited Report, AECL-6218 (1978).

217. I.J. Hastings, M.J.F. Notley and D.H. Rose, IRRADIATIOW-INDUCEDVOLUME CHANGES IN COMMERCIAL UO2 FUEL: COMPARISON WITH MODELPREDICTION.Journal of Nuclear Materials, 7±, 301 (1978).Also AECL-6224.

218. J. Veeder, THORIUM FUEL CYCLES IN CANDU.Reprinted from Pacific Basin Conference on Nuclear PowerPlants, Tokyo, Japan, 1978 September, in Transactions AmericanNuclear Society, pp. 267, 1978.Atomic Energy of Canada Limited Report, AECL-6254 (1978).

219. S. Banerjee and F.W. Barclay, CHARACTERISTICS OF PLUTONIUM-TOPPED THORIUM CYCLES IN HEAVY-WATER-MODERATED PRESSURE TUBEREACTORS.Nuclear Technology, 43, 55 (1979).Also AECL-6268.

220. S.R. Hatcher, PROSPECTS FOR FUTURE CANDU FUEL CYCLES.Atomic Energy of Canada Limited Report, AECL-6334 (1979).

221. G.A. Bartholomew, J.S. Fraser and P.M. Garvey, ACCELERATORBREEDER CONCEPT.Atomic Energy of Canada Limited Report, AECL-6363 (1978).

222. A.L. Wight and P. Girouard, OPTIMUM BURNUP DISTRIBUTION IN ACONTINUOUSLY FUELED REACTOR.Nuclear Science and Engineering, &J, 61 (1978).Also AECL-6371.

223. I.J. Hastings, J.A. Scoberg, Kathy KacKenzie and W. Walder,GRAIN GROWTH IN UO2: STUDIES AT CHALK RIVER NUCLEAR LABORATORIES.Atomic Energy of Canada Limited Report, AECL-6411 (1979).

224. M.F. Duret and H. Hatton, SOME THORIUM FUEL CYCLE STRATEGIES.Atomic Energy of Canada Limited Report, AECL-6414 (1979).

225. I.J. Hastings and L.E. Evans, DENSIFICATION ALGORITHM FOR IR-RADIATED UO2 FUEL.Journal of American Ceramic Society, 62/3-4), 217 (1979).Also AECL-6493.

226. A.J. Mooradian, NEW TECHNOLOGY AND FUEL CYCLES.Presented at the Conference on Canadian Nuclear Policy, MontSte. Marie, Quebec, 1978 November 8-10.Also AECL-6535.

- 23 -

227. DATA BASE FOR A CANDU-PHW OPERATING ON A ONCE-THROUGH NATURALURANIUM CYCLE (INFCE/WG 8/CAN/DOC 2).Atomic Energy of Canada Limited Report, AECL-6593 (1979).

228. DATA BASE FOR A CANDU-PHW OPERATING ON A ONCE-THROUGH, SLIGHTLYENRICHED URANIUM CYCLE (INFCE/WG 8/CAN/DOC 3).Atomic Energy of Canda Limited Report, AECL-6594 (1979).

229. DATA BASE FOR A CANDU-PHW OPERATING ON THE THORIUM CYCLE(INFCE/WG 8/CAN/DOC 4).Atomic Energy of Canada Limited Report, AECL-6595 (1979).

230. P.H. Tevari and A.B. Campbell, THE ROLE OF URANIUM (VI) IN THEThO2-UO3 SOL-GEL PROCESS.Journal of Colloid and Interface Science, 2§.» 155 (1980).Also AECL-6597.

231. M.A. Ferady, K.D. Cotnam and F. Preto, ALTERNATIVE METHOD OFMAKING RECYCLE FUEL: IMPREGNATION OF LOW DENSITY PELLETS.American Ceramic Society Bulletin, 58_(12), 1189 (1979).Also AECL-6634.

232. I.J. Hastings, J.A. Scoberg and Kathy MacKenzie, GRAIN GROWTHIN UO2: IN-REACTOR AND LABORATORY TESTING.Journal of Nuclear Materials, 82_, 435 (1979).Also AECL-6642.

233. R.B. Matthews and M.L. Swanson, FABRICATION OF LARGE (Th,U)O2MICROSPHERES.American Ceramic Society Bulletin, 53(2), 223 (1979).Also AECL-6646.

234. I.J. Hastings and M.J.F. Notley, PREDICTION OF FISSION GAS RE-LEASE FROM HIGH BURNUP OXIDE FUEL.Paper Cl/3 Transactions of the Fifth International Conferenceon Structural Mechanics in Reactor Technology, Berlin,W. Germany, 1979 August 13-17.Also AECL-6682.

235. A.S. Bain, D.G. Hardy, W.R. Tarasuk and K.T. Bates, CANDUFUEL: THE INFLUENCE OF DESIGN ON FUEL PERFORMANCE.Proceedings of an International Symposium on Water ReactorFuel Element Fabrication with Special Emphasis on the Effectof Fabrication Technology on Fuel Performance sponsored by theIAEA, 1978 November 6 to 10. Paper IAEA-SM-233/31.Also AECL-6697.

236. J.J.M. Too and H. Tamm, FAXMOD AND ITS APPLICATION ON THE PRE-DICTION OF HIGH TEMPERATURE CREEP AND SHEATH BALLOONING BEHAVIOUR.Nuclear Engineering and Design, 5_6, 211 (1980).Also AECL-6722.

- 24 -

237. J.B. Slater, EXPLOITING THORIUM IN CANDH REACTORS.Nuclear Engineering International, 24(292), 45 (1979).Also AECL-6728.

238. A.W.L. Segel, CANDO DESIGN FEATURES THAT INFLUENCE FUEL MODELLINGFOR TRANSIENTS.Nuclear Engineering and Design, _56_, 189 (1980).Also AECL-6729.

239. I.J. Hastings and M.J.F. Notley, FISSION GAS RELEASE FROM THORIA-BASED FUELS: COMPARISONS WITH MODEL PREDICTIONS.Presented at the Canadian Nuclear Society Conference, Montreal,Quebec, 1980 June 18.Also AECL-6983.

240. M.A. Feraday, REMOTE FABRICATION OF (Th, 233U)02 PELLET-TYPEFUELS FOR CANDU REACTORS.Nuclear Technology, J3_, 176 (1981).Also AECL-7117.

241. S. Sunder, D.W. Shoesmith, M.G. Bailey, F.W. Stanchell andN.S. Mclntyre, ANODIC OXIDATION OF U02 PART I. ELECTROCHEMICALAND X-RAY PHOTOELECTRON SPECTROSCOPIC STUDIES IN NEUTRALSOLUTIONS.Journal of Electroanalytical Chemistry, 130, 163(1981).Also AECL-7139.

242. J.S. Geiger and G.A. Bartholomew, Editors, A REVIEW OF THEPROSPECTS FOR FUSION BREEDING OF FISSILE MATERIAL.Atomic Energy of Canada Limited Report, AECL-7259 (1981).

243. J.S. Fraser, C.R. Hoffmann, t.0. Schriber, P.M. Garvey andB.M. Townes, A REVIEW OF PROSPECTS FOR AN ACCELERATOR BREEDER.Atomic Energy of Canada Limited Report, AECL-7260 (1981).

244. P.J. Fehrenbach, P.A. Morel and R.D. Sage, IN-REACTOR MEASUREMENTOF CLADDING STRAIN: FUEL DENSITY AND RELOCATION EFFECTS.Nuclear Technology, 56_, 112 (1982).Also AECL-7341.

245. J.B. Slater, POTENTIAL OF ADVANCED FUEL CYCLES IN CANDU REACTORS.Nuclear Energy, _2£ (5), 421 (1981).Also AECL-7379.

246. S.A. Kushneriuk and P.Y. Wong, FISSILE FUEL BREEDING IN DT FUSIONREACTOR BL«K.KTS.Atomic Energy of Canada Limited Report, AECL-7424 (1981).

247. D.R. McLean and S. Vijayan, KINETICS OF RESOURCE UTILIZATION INLARGE ENERGY SUPPLY SYSTEMS: URANIUM RESOURCES AND FUEL CYCLES.Proceedings of the 2nd Annual Conference of the Canadian NuclearSociety, Ottawa, Ontario, 1981 June 10, p. 113.Also AECL-7455.

- 25 -

248. M.S. Milgram, ONCE-THROUGH THORIUM CYCLES IN CANDU REACTORS.Atomic Energy of Canada Limited, AECL-7516 (1982).

249. 0. HSusser, H. Graf, L. Grodzine, E. Jaeschke, V. Metag, D. Habs,D. Felte, H. Enllng, E. Grosse, R. Kulessa, D. Schwalm,R.S. Simon and J. Kelnonen, g FACTORS OF HIGH-SPIN YRAST STATESIN z32Th and 238U.Physical Review Letters, 48(6), 383 (1982).Also AECL-7619.

250. L.W. Green, C.H. Knight, T.H. Longhurst, I.H. Crocker, MASSSPECTROMETRIC DETERMINATION OF THE ISOTOPIC COMPOSITION OFURANIUM IN URANIUM FUELS USED IN THE CHALK RIVER RESEARCHREACTORS AND CANDU POWER REACTORS.Atomic Energy of Canada Limited Report, AECL-7686 (1982).

251. I.J. Hastings, A. Celli, M. Onofrei and M.L. Swanson, IRRADIATIONPERFORMANCE OF (Th, U)02 FUEL DESIGNED FOR ADVANCED CYCLEAPPLICATIONS.Presented at the Third Annual Conference of the Canadian NuclearSociety, Toronto, Ontario, 1982 June 8-9.Atomic Energy of Canada Limited Report, AECL-7697 (1982).

252. J.J. Llpsett, I.J. Hastings and C.E.L. Hunt, BEHAVIOUR OF SHORT-LIVED IODINES IN OPERATING TO>2 FUEL ELEMENTS.Presented at the Canadian Nuclear Association 22nd AnnualInternational Conference, 1982 June 6-9.Also AECL-7721.

253. J.C. Wood, M.T. Foo and L.C. Berthiaume, REDUCED ENRICHMENTFUELS FOR CANADIAN RESEARCH REACTORS.Presented at the Third Annual Conference of the Canadian NuclearSociety, Toronto, 1982 June.Also AECL-7722.

254. J.B. Slater, ECONOMIC POTENTIAL OF ADVANCED FUEL CYCLES INCANDU.Atottic Energy of Canada Limited, AECL-7753 (1982).

255. J. Donnelly, THE INTEGRATED CANDU SYSTEM-AN INTERNATIONALPERSPECTIVE.Presented at the IAEA Conference on Nuclear Power Experience,Vienna, 1982 September 13-17.Also AECL-7761.

256. N. Aspin, R.M. Williams and R.G. Dakers, CANADA'S URANIUM FUTURE,BASED ON FORTY YEARS OF DEVELOPMENT.Presented at the IAEA Conference on Nuclear Power Experience,Vienna, 1982 September 13-17.Also AECL-7765.

257. J.R. MacEwan, M.J.F. Notley, J.C. Wood and M. Gacesa, CANDU FUEL:PAST, PRESENT AND FUTURE.Presented at the IAEA Conference on Nuclear Power Experience,

- 26 -

Vienna, 1982 September 13-17.Also AECL-7766.

258. E. Critoph, ALTERNATIVE BREEDER AMD NEAR-BREEDER SYSTEMS.Presented at the IAEA Conference on Nuclear Power Experience,Vienna, 1982 September 13-17.Also AECL-7770.

259. P.J. Fehrenbach, I.J. Hastings, P.A. Morel, R.D. Sage andA.D. Smith, DIMENSIONAL RESPONSE OF CANDH FUEL TO POWER CHANGES.Atomic Energy of Canada Limited Report, AECL-7837 (1982).

3. MISCELLANEOUS PUBLICATIONS(Includes Journal Articles, Conference Papers, etc.)

260. G.C. Laurence, MATERIAL BALANCE IN REACTORS WITH RECYCLED FUEL.Paper prepared for the Reactor Core Conference, Chalk River,Ontario, 1956.CRRP-624, 1956.

261. W.B. Lewis, ENRICHED OR NATURAL URANIUM.Nuclear Power, 2, 340 (1957).

262. J.R. Menke, W.B. Lewis, J.A. Lane, C. Starr and W.E. Shoupp,ENRICHED VS NATURAL U.

Nucleonics, _15_. 6 S < 1 9 5 7 ) '

263. W.B. Lewis, IS FUEL REPROCESSING NECESSARY? FOR CANADA THEANSWER SEEMS TO BE "NO".Nuclear Power, 2> 69 (1958).

264. O.J.C. Runnalls, CURRENT TRENDS IN REACTOR FUELS: UO2-FABRI-CATION AND PROPERTIES.Nucleonics, _17_, 104 (1959).

265. G.T. Leaist, PROSPECTS FOR UR/NIUM CONSUMPTION IN THE CANADIANPOWER REACTOR PROGRAM.CRR-907, 1960.

266. J.H. Krenz, ECONOMICAL NUCLEAR POWER: A CANADIAN POINT OF VIEW.Energia Nucleaire, J£, 435 (1963).

267. W.B. Lewis, THE PROGRAM FOR BREEDERS, BREEDERS WHEN OR NEVER.Nuclear News, ]_, 107 (1964).

268. W.B. Lewis, PROSPECTIVE FUELLING SYSTEMS FOR THE HEAVY WATERREACTOR.Canadian Nuclear Technology, _4, 46 (1965).

269. J.L. Gray, W.B. Lewis and L.R. Haywood, CANDU REACTORS TO 1980AND IN THE LONG TERM.

- 27 -

Proceedings of the World Power Conference, Tokyo, Japan, 1966,III, p. 1487.

270. J.L. Gray, USE OF PLUTONIUM IN THE CANADIAN REACTOR PROGRAM.Presented at the Commercial Plutonium Fuels Conference,Washington, D.C., 1966.

271. W.B. Lewis, CANADA'S PLANNED ADVANCED REACTOR CONCEPTS.Proceedings of the American Power Conference, 29th, 1967, 29, 57(1967).

272. W.B. Lewis, ECONOMICS OF NUCLEAR FUEL CYCLES.Forum on Uranium and Nuclear Power at the 1967 Fall Conference ofthe Financial Analysts Federation, Toronto.DL-81, 1967.

273. W.B. Lewis, ECONOMIC HEAVY WATER POWER REACTORS.Steam Generating and Other Heavy Water Reactors, London, BritishNuclear Energy Society, 175 (1968).DL-85, 1968.

274. T.G. Church, ROLE OF THORIUM IN CANDU TYPE REACTORS.Presented at the Thorium Information Meeting, Salmon, Idaho,1968.CONF-680989, p. 52.

275. L.R. Haywood, STATUS OF HEAVY WATER MODERATED REACTOR.Proceedings of the Seminar on Nuclear Power, Bombay, Departmentof Atomic Energy, 1970.

276. W.B. Lewis, WHY MAXIMUM CANDU POTENTIAL LIES WITH ORGANIC COOLANTAND A THORIUM FUEL CYCLE.DM-138, 1973.

277. J.J.M. Too, T.R. Hsu and A.W.M. Bertels, FULMOD: AN INELASTICANALYSIS PROGRAM TO PREDICT THE OPERATING BEHAVIOUR OF CANDU FUELELEMENTS.Fuel Element Analysis, A.S.M.E., p. 23 (1975).CONF-750617-17.

278. J.R. MacEwan, A.T. Jeffs, DEVELOPMENT PROGRAM FOR A PLUTONIUMFUELLED CANDU REACTOR.Plutonium Utilization in Thermal Power Reactors, InternationalAtomic Energy Agency, Vienna, 1975, p. 175.IAEA-PL-632/21

279. J.B. Slater, A CANDU-BLW REACTOR DESIGNED FOR PLUTONIUM RECYCLE.Plutonium Utilization in Thermal Power Reactors, InternationalAtomic Energy Agency, Vienna, 1975, p. 211.IAEA-PL-632/22.

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280. A.M. Alkin, CANADA'S NUCLEAR POWER EXPERIENCE.Annual Conference of the Japan Atomic Industrial Forum, Tokyo,1975.

281. G.T. Leaist, DEVELOPMENT OF THE CANADIAN NUCLEAR POWER PROGRAM.Nuclear Power Development and the Fuel Cycle, American NuclearSociety, 1976.CONF-761014.

282. M.F. Duret, USE OF PLUTONIUM IN CANDU REACTORS.Transactions American Nuclear Society, _23_, 238 (1976).

283. A.S. Bain, D.G. Hardy and J.R. MacEwan, ADVANCES IN CANDU FUEL -PAST AND FUTURE.Proceedings of the Canadian Nuclear Association 17th AnnualInternational Conference, Toronto, 1977, Volume 6, p. 121.77-CNA-6OO.

284. R.W. Jones, H.R. Lee, H. Hann, J.F. Walker and A. Celll, THORIAFUEL TECHNOLOGY IN CANDU-PHW REACTORS.Transactions American Nuclear Society, 2T_, 303 (1977).

285. A.D. Lane, R.W. Jones and D. Hamel, FUEL TECHNOLOGY FOR DENATUREDTHORIUM CYCLES IN CANDU REACTORS.Transactions American Nuclear Society, 27̂ , 304 (1977).

286. J.J.M. Too, G.L. Rigby and H. Tamm, REPEATABLE BOUNDARY CONDI-TIONS AND THEIR APPLICATION IN THE ANALYSIS OF A COMPLETE CANDUFUEL PIN.Transactions of the 4th International Conference on StructuralMechanics in Reactor Technology, San Francisco, 1977, D, Dl/8, 1(1977).

287. M.G. Hare and P.A. Ross-Ross, CONSERVATION WITH CANDU.Engineering Journal, j60, 9 (1977).

288. G.A. Pon and M.G. Hare, CANADIAN NUCLEAR POWER PROGRAM.Transactions American Nuclear Society, 2S_, 6 (1978).

289. J.R. MacEwan, M.J.F. Notley and H. Tamm, MODELLING OF FUELELEMENT BEHAVIOUR.Proceedings of the Canadian Nuclear Association 17th AnnualInternational Conference, Toronto, 1977, Volume 6, p. 124.

290. J.A.L. Robertson, ZIRCONIUM - AN INTERNATIONAL NUCLEAR MATERIAL.Journal of Nuclear Materials, W0_ (1-3), 108 (1981).

291. A.D. Lane and A.T. Jeffs, ADVANCED FUEL CYCLES FOR CANDU:AECL's FUEL DEVELOPMENT PROGRAM.Proceedings of the 2nd Annual Conference of the Canadian NuclearSociety, Ottawa, Ontario, 1981 June 10, p. 126.

- 29 -

292. D. Jenkins, J. Preelsy and M. Augustine, BURHUP IMPROVEMENTTHROUGH RESHUFFLING OF FUEL BUNDLES OF THE FIRST FUEL CHANGE INCANDU-6OO.Proceedings of the 2nd Annual Conference of the Canadian NuclearSociety, Ottawa, Ontario, 1981 June 10, p. 133.

293. R.J. Leraire and C.P. Brown, COMPONENT ACTIVITIES IN THE SYSTEMTHORIUM NITRATE - NITRIC ACID - WATER AT 25°C.Journal of Solution Chemistry, 21 (3). 203(1982).

- 30 -

SUBJECT INDEX

SUBJECT DOCUMENT NUMBERS

BURMUP MEASUREMENTS

ECONOMICS

- General

- Cost of Power

- Fuel Cycles

- Fuel Coats

FUEL CYCLES

- General

- Breeder Concepts

- Enriched Uranium

- Natural Uranium

12, 25, 34, 37, 49, 60, 63, 65, 68, 70, 102,109, 112, 121, 125, 126, 130, 137, 138, 142,143, 146, 149, 155, 163, 170, 177, 207, 213,214, 215, 216, 217, 222, 244, 259, 263, 275,287, 292.

10, 26, 37, 89, 90, 94, 95, 96, 106, 117, 121,175, 187, 194, 209, 262, 273, 281.

2, 11, 13, 18, 21, 22, 32, 33, 49, 65, 119,265, 266, 267.

8, 11, 13, 16, 18, 22, 23, 34, 37, 49, 61, 98,99, 107, 122, 124, 128, 130, 132, 137, 139,141, 148, 154, 158, 162, 163, 173, 176, 185,192, 193, 202, 208, 210, 212, 213, 218, 254,262, 267, 270, 272, 275, 282, 283, 288.

2, 17, 18, 20, 25, 32, 33, 34, 35, 38, 45, 49,56, 65, 84, 86, 100, 103, 104, 117, 118, 120,121, 123, 127, 132, 135, 137, 139, 147, 156,164, 165, 173, 193, 196, 197, 208, 210, 218,242, 266, 268, 270, 272, 273, 276, 281.

1, 2, 3, 8, 9, 31, 34, 48, 51, 57, 75, 78, 83,85, 96, 118, 121, 124, 127, 128, 132, 136, 139,142, 144, 148, 160, 164, 168, 169, 171, 176,178, 195, 196, 197, 198, 211, 220, 226, 268,273, 283.

88, 134, 141, 162, 192, 221, 242, 243, 246,258, 267, 268, 269.

12, 26, 45, 68, 84, 97, 99, 103, 163, 169, 209,218, 228, 250, 253, 255, 257, 261, 262.

4, 5, 11, 12, 13, 17, 18, 21, 25, 26, 27, 33,37, 42, 43, 44, 45, 49, 56, 60, 61, 64, 68, 80,84, 97, 99, 103, 104, 107, 108, 117, 127, 130,132, 139, 146, 150, 151, 152, 156, 157, 158,159, 161, 163, 164, 165, 167, 172, 173, 176,

- 31 -

- Plutonium

- Thorium Cycle

FUEL FABRICATION

- Evaluation

- Design

- Materials

- Preparation

- Plant (remotelyoperated)

FUEL IRRADIATION

- Iodines

FUEL MODELLING

179, 182, 184, 185, 187, 193, 196, 199, 200,202, 205, 208, 209, 210, 212, 213, 215, 217,223, 225, 227, 232, 234, 247, 249, 256, 257,261, 262, 263, 267, 268, 269, 270, 272, 27':,281.

6, 11, 12, 64, 84, 85, 103, 109, 132, 139, 157,159, 162, 176, 189, 196, 215, 219, 247, 260,268, 269, 270, 271, 279, 282, 288.

13, 49, 90, 95, 99, 104, 130, 132, 139, 141,154, 159, 162, 173, 174, 176, 180, 182, 185,187, 190, 191, 192, 193, 194, 196, 197, 198,201, 202, 205, 206, 208, 210, 212, 213, 215,218, 219, 221, 224, 229, 237, 239, 242, 243,245, 246, 247, 248, 249, 251, 254, 255, 257,268, 271, 274, 276, 284, 285, 287, 288, 291,293.

78, 84, 90, 104, 105, 106, 165, 173, 182, 197,251.

31, 37, 62, 83, 89, 97, 100, 101, 114, 120,122, 125, 128, 129, 141, 148, 155, 164, 165,191, 196, 235, 240, 277, 284, 285.

30, 31, 35, 37, 38, 40, 47, 52, 54, 73, 78, 85,90, 105, 110, 114, 141, 150, 195, 230, 231,233, 253, 264, 268, 285, 286, 290.

29, 30, 31, 35, 39, 40, 47, 54, 58, 59, 67, 73,78, 79, 81, 87, 100, 110, 128, 196, 230, 233,264, 279, 284, 285.

240.

4, 5, 9, 19, 28, 31, 42, 46, 55, 57, 60, 63,71, 72, 79, 103, 107, 108, 109, 113, 126, 129,131, 136, 142, 143, 144, K 6 , 151, 152, 160,161, 166, 167, 178, 179, 184, 185, 204, 217,223, 225, 232, 234, 244, 251, 259, 274.

252

112, 113, 115, 146, 167, 170, 174, 180, 184,188, 189, 199, 200, 204, 205, 211, 216, 217,

REPROCESSING

- 32 -

223, 225, 232, 234, 236, 238, 239, 278, 286,289.

- General 151, 173, 182, 190, 193, 194, 197, 202, 218,

224, 260, 263, 269, 275, 276, 282.

- Amines 145.

- Dissolving 22, 241.

- Extraction 14, 22, 24, 28, 46, 69, 91, 92, 145, 197, 207,

218.

- Ion Exchange 15, 16, 19, 36, 53, 207.

- Precipitation 15.

- Recovery 15, 19, 53, 145, 209.

- Recycling 11, 12, 22, 27, 64, 103, 121, 123, 132, 133,137, 139, 162, 176, 181, 193, 208, 211, 218,231, 245, 247, 263, 268, 279, 282.

- Reduction 22.

- Separation 10, 23, 28, 64, 207, 209, 268.

- Tributyl Phosphate 14, 24, 28, 55.

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