Radioactive waste management. Organizational … Project. Radioactive waste management. Organizational and technical solutions Oxford, UK, 5-7 March 2008 Radioactive waste management

Gremikha Project. Status, problems & proposals

Radioactive waste management. Organizational and technical solutions

B.S. Stepennov, RRC KI

Oxford, UK, 5-7 March 2008

Gremikha Project. Radioactive waste management. Organizational and technical solutions


Gremikha Project participants:Rosatom, RRC «Kurchatov Institute»,

SevRAO,

VNIPIET,

NIKIET,

IPPE,

HYDROPRESS

Additional funding and technical support:CEA (France),

EBRD,

EC (TACIS)



Radioactive waste management objective

— implementation of a system of environmentally safe management of waste

of different activity levels and types accumulated and arising in the course

of remediation activities with the maximum possible limitation of an adverse impact

of ionizing radiation from the radioactive waste on workers, public and environment.



Specific features of the TSF in Gremikha

Remoteness and isolation from large

industrial centres.

Lack of a developed transportation

system.

Lack of a RW management

infrastructure.

Various kinds of RW that differ in

storage locations, radiation parameters,

physicochemical composition, sizes, etc.

High staff turnover (by categories and qualifications).

�.

2.

3.

4.

�.

Arkhangelsk

Murmansk

Arkhangelsk

Murmansk

Gremikha TSFGremikha TSF



Criteria used for selection of organizational and technical solutions on RW management

Technologies and processes to be used shall be simple, proven and efficient and along

with this shall ensure nuclear and radiation safety.

Minimum new construction construction of permanent buildings and structures.

Minimum number of steps in the RW management process along with meeting

acceptance criteria and requirements of transportation to the Regional Centre

in Saida Bay.

Unification and minimization of a range of containers used in transportation and handling

schemes.

�.

2.

3.

4.



Conceptual flow chart of RW management at the TSF in Gremikha

Radioactive waste

LRW

High-level(HLW)

Treated LRW

SRW

ILWLLW

Filtration

Evaporation

Grouting

SRW sorting and fragmentingContainers with SRW

Low- andintermediate-level

(LLW, ILW)

Very low-levelSRW

(VLLW)

Grouting andconditioning

Compactionof soft SRW

Packing incontainers

Preparation of shipping packagesPreparation of shipping packages

High-level processingof SRW and preparationof packages for storage

Disposalin a near-surface

repository

Long-term storage Regional Centrein Saida Bay

Transportat ion



General layout of the TSF

Open Pad

SNF & SRW managementdepartment

LRW managementdepartment



Arrangement of equipment in working areas at the Open Pad.

Stage 2. Removal of SRW

Filtering system

Special solutionspreparation unit

Water-supply system

SRW extraction operator’s module

Scanning unit module

Vehicle washer

Special vehicle (MoAZ-7503)

Special vehicle loading area

Truck-mounted 100-t craneLiebher LTM 1100-4.1

Vent stack (existing)

Air plasma cutting module

Container decontamination module

Container draining module

Personnel contaminationcontrol station (RCP)

Working area for completing SRWand SNF containers

100-t crane working area

10-t crane boom turning radius 22000 mm

20-t crane boom turning radius 13000 mm

Exhaust ventilation module

Containment under the modulefor extraction of SRW from containers



Conceptual flow chart of SRW management at the TSF in Gremikha

Metal SRW(ILW, HLW)

Work clothesand PPE

Filters, CPS

Cemented LRW

Containers with SRW

Very low level waste(rubbish, soil, etc.)

On-site disposalin a near-surface repository

Removal

Empty containers

Drying. Sorting.Fragmentation.Compaction.

Highly penetratingcompound castingof HLW and ILW

Packing.Sealing.

Certification

Building 505Building 504

Building 503

Interimstorage

Area 502

Total accumulated amount 1500 m3

HLW – 7.5 m3

ILW – 195 m3

LLW – 1290 m3



Conceptual layout of SRW management areas

Хранение пустыхконтейнеров

Storageof reagents

Building 9

Cement mixpreparation

Building 505

Completingof containers

Building 10

Interim storageof containers

Area 502Demolition of building 11

SRW sorting

Building 504

HLW ILW LLW

�mptycontainers

Building 503

SRW from the Open Pad

New construction

Exiasting building (refurbishment)

Open area



Layout solutions. Buildings 504 & 505. Structures 501, 502 & 503

Building 11

Building 10Building 9

Bui

ldin

g 50

4 Stru

ctur

e 50

2

Structure 503

Stru

ctur

e 50

1

Bui

ldin

g 50

5



Options of LRW management at the TSF in Gremikha

Accumulated LRW:

• in shore tanks at the LRW site;

• in the pipe lane in building ��;in the pipe lane in building ��;

• in building �;in building �;

• in buried tanks in building ��;in buried tanks in building ��;

• in floating tanks ��;in floating tanks ��;

• in type �� and �� containers with S�� and containersin type �� and �� containers with S�� and containers with SRW at the Open �ad.

Total:

LLW 24� m3

ILW �� m3

HLW �.2 m3



Conceptual flow chart of LRW management for two options

Removalof LRWCement grouting

Salt concentrateRemoval and storage�vaporation

Селективнаяочистка

C o n t r o l

Decantate LLWCementedRW

Sediment

Condensate LLWCondensate

Purified LRW

Dischargeor recycling

Decantate ILW

Removal ofcemented LRW

Interimstorage

Settling and compactionof the sediment

Mixing

LRW (option �)

LRW (option 2)



Layout of buildings and shelters for LRW treatment equipment

1 1

521

522

Building 19

Building 17

Single-beam electricbridge crane Q=5t

506

– V

ehic

leac

cess

yar

d

New annex to building 17Newly constructed shelter



Conceptual flow chart of management of SRW stored in building 19

LLW: packing intocontainers KS-5

ILW: packing intocontainers KSZ-5

Removal

Handling andconditioningin buildings504 & 505

Preparationof shippingpackages

SRW in building 19(except HLW)



Conceptual flow chart of SRW management in open areas

SRW in openareas

Initial sorting Radiation control Removal of LRW

Removal

Preparationof packages

Handlingand conditioning

in buildings504 & 505

Packinginto reusable

containersor applicationof a protectiveaccumulating

coating

Area near building 1 Area betweenthe dry dock and building 1B



Conceptual flow chart of management of SRW from dismantling of floating tanks

LLW: packinginto standard

containers

ILW: packinginto containers

for transportationof drumswith ILW

Handlingand conditioning

in buildings504 & 505

Conditioningin building

505

Removal

Preparationof packages

Floating tanks

Fra

gm

ents



Operations with SRW at the Open Pad

С уз4

Жбе1

Бет8Бет7

С уз1

С уз3

С уз2

БК1

БК2

МК1

МК2

Бет5

Бет2

Бет1

Бет4Жбе2Бет3

Жбе3Бет6

Л30

Л31

53

1 2 3 4

5678

9 10 11 12

13141516

1718 19 20

2122

2324252627

28 29 30

33

34

3536

37

383940

41

4243 44 45 46 47

484950

51

52Бак

Л27

Л23 Л24

Л25

Л26

54

55

56

57

58

59

61

62

64

65

66 68

69

71

7374

75

7677

78

79

8082

83

84

85

88

89

90

91 92

93

94

95

96

98

99

100

101

103 104

105102

106

107

108109

110

111112 113 114

115

116

81

31

32

97

6067 86

70

ОБ

ОБ

ОБ

ОБ

ОБ

ОБ ОБ ОБ

ОБ

ОБ

ОБ

ОБ

О БО Б

ОБ ОБ

К7

К1К2

К3

К1 0

К8

К9

К5

К6

К4

Б5

Б2Б1

Б6

К11 Бет9

К1 6К1 5К1 4

К1 3

С из2

С из1

Б3 Б4

Л29Л28

П1

П2

Ф

Ф

Ф

Х2

Х1

Х5Х4

Х3

Х6

Л19

Л17

Л3

Л20

Л13

Л8

Л14

Л18

Л16

Л2

Л5

72

6387

SE

NW

SWNE

- localization stage 1(2006): containers K10, K15, No.109, 113 & 114 (type 11), SFA fragment between type 6 containers No.2 and No.3;

- localization stage 2 (2007): container K15 (once more), containers No.35 (type 6), No.110, 111, 115 & 116 (type 11), SFA fragment near container Жбе2, traps;

- localization stage 3 (proposals for 2008): container No.113 (once more), SFA fragment near container Жбе2 (once more), containers Бет2, Бет4 & Бет8.



Improvement of the radiation situation at the Open Pad

А

B

C

Equivalent dose rate at 3 m above the Open Pad:

А �� before localization of sources,�� before localization of sources, before localization of sources, spring 2��, �� = 3,2� µSv/h

B �� after stage � of localization of sources, autumn 2��, �2 = �,�� µSv/hµSv/h

C �� after stage 2 of localization of sources,�� after stage 2 of localization of sources, after stage 2 of localization of sources, autumn 2��, �2 = �,34 µSv/hµSv/h



Legend:

С уз4

Жбе1

Бет8Бет7

С уз1

С уз3

С уз2

БК1

БК2

МК1

МК2

Бет5

Бет2

Бет1

Бет4Жбе2Бет3

Жбе3Бет6

Л30

Л31

53

1 2 3 4

5678

9 10 12

13141516

1718 19 20

2122

2324252627

28 29 30

33

34

3536

32

383940

41

4243 44 45 46 47

484950

51

52Бак

Л27

Л23 Л24

Л25

Л26

54

55

56

57

58

59

61

62

64

65

66 68

69

71

7374

75

7677

78

79

8082

83

84

85

88

89

90

91 92

93

94

95

96

98

99

100

101

103 104

105102

106

107

108109

110

111112 113 114

115

116

81

31

37

97

6067 86

70

ОБ

ОБ

ОБ

ОБ

ОБ

ОБ ОБ ОБ

ОБ

ОБ

ОБ

ОБ

О БО Б

ОБ ОБ

К7

К1К2

К3

К1 0

К8

К9

К5

К6

К4

Б5

Б2Б1

Б6

К11 Бет9

К1 6К1 5К1 4

К1 3

С из2

С из1

Б3 Б4

Л29Л28

П1

П2

Ф

Ф

Ф

Х2

Х1

Х5Х4

Х3

Х6

Л19

Л17

Л3

Л20

Л13

Л8

Л14

Л18

Л16

Л2

Л5 TK-6, contain only intact SFA (42);

TK-6, contain only intact SFA, contain water (34);

TK-6, contain intact and damaged SFA (22);

TK-6, contain SFA without a basket, contain water (2);

TK-6, contain intact and damaged SFA, contain water (5);

TK-6 without SFA – empty or containing other components (2);

TK-11 (9).

72

6387

11

Examination of SFA in TK-6 containers



Information on SFA in type 6 TK containers at the Open Pad

Distribution of the number of TK-6 containers by water radioactivity level

Examination of SFA in TK-6 containers

98 ТК

39 – 610 115725 84% 16%

686SFA

Co

mp

lete

se

t o

f S

FA

6 ТК

Sh

ort

age

of

SF

A

3 ТК

TK

wit

ho

ut

SF

A

74 ТК

com

ple

te s

et

of

inta

ct S

FA

on

ly

30 ТК

TK

co

nta

in in

tact

an

d d

amag

ed

SF

A

2007

2

103 104 105 106 107 108 109

Num

ber

of c

onta

iner

s

Water activityin the TK, Bq/l

Sr-90Cs-137

16

4

12

15

6

12

3 3

2007



Removal of intact SFA according to a regular procedure

Ramp(concrete)

Concretewall

Open Pad area Area nearthe Open Pad

Caskof type ��

Rock

Vehicle MAZ ��3�

Road to SD��

Rock

Station for preparation of a type �� cask for transportation

Road movementarea

Area of SFA loadingon the ship

SFAreloading area

Reloading container

Building 1

Basket 22M

Maintenance shipspent fuel storage

Cask of type ��

Cask dryingsection

�ointingdevice



Summary1. The works on RW management are performed with financial and

technical support from donor countries, first of all C�A (��rance), �BRD, �C (TACIS) and Rosatom.

2. The issue of the day is selection of an optimum SRW and LRW management option in view of effective technologies using unified container types, process equipment and means of delivery.

3. A key aspect of RW management is coordination of works between facilities under remediation and the Saida Centre to ensure that criteria of waste acceptance for processing and storage are met.

4. Solution of the RW management problem may be expedited if experience available in western companies is used.

Documents

Radioactive waste management. Organizational … Project. Radioactive waste management. Organizational and technical solutions Oxford, UK, 5-7 March 2008 Radioactive waste management