U. S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150·0027 EXPIRES: (11/3 /2015)Estimated burden per response to complywilh this mandatorycolleotion request: 2.4 hou . Thissubmittal is reviewed to ensure that ilie applicable statutory, regulatory, an policyccnsideraUons are satisfied. Send comments regarding buIden estimate to ilie Infqnnauon

APPLICATION FOR NRC EXPORT OR IMPORT Services Branch [T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 205 5-0001,or by internet e-mail to Infocclleots.Resounoe@mc.gov,and to ihe Desk Officer, Ice of

LICENSE, AMENDMENT, RENEWAL, Infonnation and Regulatory Affairs, NEOB-10202, (3150-0027), Office of Managem nt andOR CONSENT REQUEST(S) Budget, Washington, DC 20503. If a means used to impose an infonnation collection oes not

display a currently valid OMB control number, fhe NRC may not conduct or sponso , and a(See Instructions on Pages 4 and 5) person is not requiredto respond to, the infonnation collection.~~~~~~~~~~~~~~~~--~~=~~~~~~~~

.PART B. TO BE COMPLETED FOR ALL LICENSES, AMENDMENTS, RENEWALS, OR CONSENT REQUES S(If more space is needed to complete any of the items, use Pages 3-4 first, and then attach additional sheets, if necessary.)

Mirion Technologies (IST) Corporation300 1ST Center315 Daniel Zenker DriveHorseheads, NY 14845

lc. PHONE NUMBER

(607) 301-4160

1. NAME AND ADDRESS OF APPLICANT/LICENSEE la. NAME OF APPLICANT'S CONTACT lb. APPLICANT'S REFERENCE NUMBE

. Eric P. Brand EPBOOOI

ld. FAX NUMBER

(607) 562-4482

te, E-MAIL ADDRESS

ebrand@mirion-ssd.com

2. TYPE OF ACTION REQUESTED (Check One)

[l] EXPORT D IMPORT(Parts B, C, E) (Parts B, D, E) D AMENDMENT/RENEWAL

Current License Number: DCONSENT REQUEST

(Parts B, C)Current License Number:

3. CONTRACT NUMBER{S)

C83-QH36D062334. FIRST SHIPMENT DATE

11/09/20155. LAST SHIPMENT DATE

01/31/2016

10. DESCRIPTION OF RADIOACTIVE MATERIALS, SEALED SOURCES,NUCLEAR FACILITIES, EQUIPMENT, OR COMPONENTS; FORNUCLEAR EQUIPMENT INCLUDE TOTAL DOLLAR VALUE OFEQUIPMENT FOR EXPORT

Quantity 1 each, Radiation Detectors for measurement ofthermal radiation over multiple decades as follows:1.) Dual Range Fission Chamber from 1.4 to 1.4xlOe5 nv Dual Range Fission. I 2.) Uncompensated Ionization Chamber Chamber Only.from 2.5xlOe2 to 5.0xlOe10 nv . I . ,,-3.) Compensated Ionization Chamber measures up to5x10el1 nv .

lOa. MAX TOTAL VOLUME /ELEMENT WGT (KG), ORTOTAL ACTIVITY (TBq)

IEA-R1 Research Reactor

PART C. TO BE COMPLETED FOR EXPORT LICENSES, AMENDMENTS, OR RENEWALS(If more space is needed to complete any of the items, use Pages 3-4 first, and then attach additional sheets, if necessary.)

7. NAME{S) / ADDRESS{ES) OF SUPPLIERS 8. NAME(S) / ADDRESS{ES) OF INTERMEDIATE 9. NAME(S) / ADDRESS(ES) OF ULTIMATEAND/OR OTHER PARTIES TO THE EXPORT FOREIGN CONSIGNEE{S) FOREIGN CONSIGNEE{S)

Comissao Nacional De Energia Nuc1eCNENTravessa R, N 400 Ciade UniversitySao Paulo05508-170 Brazil

7a. FUNCT/ON(S) PERFORMED/SERVICE(S) PROVIDED 8a. INTERMEDIATE USE(S) 9a. ULT/MATE END USE(S) IFlux Monitor, IEA-R1 Research Reactpr

lOb. MAX ENRICHMENT 10c. MAX ISOTOPEOR WGT % WGT (KG)

Dual Range Fis ioriChamber Only.

4.679xlOe-6 TBq 93% U235 applied as 1.8 gramscoating on aninternal sealedelectrode.

Dual Range FissionChamber Only.

11. FOREIGN OBLIGATIONS (BY COUNTRY AND BY PERCENTAGE OF MAX/MUM TOTAL VOLUME)

NRC FORM 7 (11-2012)

Page 2 of

NRCFORM7(11-2012)10 CFR 110

U. S. NUCLEAR REGULATORY COMMIS ION

APPLICATION FOR NRC EXPORT OR IMPORTLICENSE, AMENDMENT, RENEWAL, OR CONSENT REQUEST(S) (Continued)

3

PART D. TO BE COMPLETED FOR IMPORT LICENSES, AMENDMENTS, OR RENEWALS(If more space is needed to complete any of the items, use Pages 3-4 first, and then attach additional sheets, if nscessary.)

12. NAME(S) IADDRESS(ES) OF FOREIGNSUPPLIERS ANDIOR OTHER PARTIESTO IMPORT

13. NAME(S) IADDRESS(ES) OF INTERMEDIATECONSIGNEE(S)

14. NAME(S) I ADDRESS(ES) OF ULTIMATE U. S.CONSIGNEE(S)

12a. NRC EXPORT LICENSE NUMBER(S)(if applicable)

13a. LICENSE NUMBER(S) I EXPIRATION DATE(S) 14a. LICENSE NUMBER(S) I EXPIRATION DATE(S)

13b. INTERMEDIATE US.E(S) 14b. ULTIMATE END USE(S)

15a. MAX TOTAL VOLUME IELEMENT WGT (KG), ORTOTAL ACTIVITY (TBq)

15. DESCRIPTION OF RADIOACTIVE MATERIALS, SEALED SOURCES,NUCLEAR FACILITIES

1Sb. MAX ENRICHMENTORWGT%

150. MAX ISOTOPEWGT(KG)

16. FOREIGN OBLIGATIONS (BY COUNTRY AND BY PERCENTAGE OF MAXIMUM TOTAL VOLUME)

PART E. TO BE COMPLETED FOR ALL LICENSES, AMENDMENTS, RENEWALS OR CONSENT REQUEST(S)17. ADDITIONAL INFORMATION

PROVIDED ON PAGES 3, 4,AND/OR ON SEPARATE SHEETS?

DYES[{]YES 17a. COPIES OF RECIPIENTS'AUTHORIZATIONS PROVIDED?

I, the applicant's authorized official, hereby certify that this application is prepared in conformity18. CERTIFICATION: with Title10, Code of Federal RegUlations, and that all information provided is correct to the best

of my knowledge.18a. PRINT NAME AND TITLE OF AUTHORIZED OFFICIAL i8b. SIGNATURE - AUTHORIZED OFFICIAL 18c. DATE

Eric P. BrandQuality Manager, Export Compliance OfficerMirion Technologies (1ST) Corporation

NRC FORM 7 (11-2012)

Page 3 of 3

NRCFORM7(11-2012)10 CFR 110

U. S. NUCLEAR REGULATORY COMMISS' ON

APPLICATION FOR NRC EXPORT OR IMPORTLICENSE, AMENDMENT, RENEWAL, OR CONSENT REQUEST(S) (Continued)

ADDITIONAL INFORMATION (Reference applicable block numbers from page 1 and/or page 2 for each entry)

Mirion Technologies (rST) Corporation is applying for license to export a quantity of 1 each, Radiation Detectors for measuremen ofthermal radiation over multiple decades. The Radiation Detectors will be exported from Mirion Technologies (IST) Corporationlocated in Horseheads, NY to the CNEN IEA-Rl Research Reactor located in Sao Paulo Brazil.

10. Description of Nuclear Equipment.1.) Dual Range Fission Chamber from 1.4 to 1.4xlOe5 nv, Model Number WL-6376A2.) Uncompensated Ionization Chamber from 2.5xl0e2 to 5.0xlOelO nv, Model Number WL-6937 A3.) Compensated Ionization Chamber measures up to 5xl0ell nv, Model Number WL-23084

1O.a MAX Total Activity of equipment in TBq.Dual Range Fission Chamber ONLY, Model Number WL-6376A4.679xlOe-6 TBq

10.b MAX Enrichment by Percent.Dual Range Fission Chamber ONLY, Model Number WL-6376A93% U235 applied as coating on an internal sealed electrode.

10.c MAX Isotope Weight1.8 grams

Attached for your reference:1.) Dual Range Fission Chamber Model Number WL-6376A Product Technical Description, 2 pages2.) Uncompensated Ionization Chamber Model Number WL-6937A Product Technical Description, 2 pages3.) Compensated Ionization Chamber Model Number WL-23084 Product Technical Description, 2 pages4.) Copy of End Use Statement from CNEN

Mirion Technologies (IST) Corporation requests the pricing information be redacted (box 10) if/when the license application ispublished for review.

NRC FORM 7 (11-2012)

MIRIONTECHNOLOGIES

Fission Counter ChamberDual-Range

1.4 to 1.4 x 105 nv Counter Range6 x 105 to 1.4 X 1010 nv Chamber Range300°F (1500C) Operation0.7 cps/nv Counter Sensitivity1.4 x 10-13 Alnv Chamber SensitivityMeets MIL-S-901 & MIL-STD-167 (Typ 1)

Sensing Systems Division

Tube Number: WL-6376A

ApplicationThe WL-6376A fission chamber is designed to detect thermal neutrons in the range of 1.4 to 1.4 x 105 neutrons!cm2!second when operate as acounter and in the range of 6 x 105 to 1.4 X IOlD neutronslcrn2!second when operated as a chamber. The detector is extremely ruggjd inconstruction, meeting MIL-S-901 for shock and MIL-STD-167 (Type I) for vibration, and may be operated in any position at temperatur supto 300°F (l50°C).

The WL-6376A is constructed of aluminum, with high purity alumina ceramic insulators throughout, including those used in the typ~ HNconnector. In typical operation as a fission counter the WL-6376A has a thermal neutron sensitivity of approximately 0.7 counts!neutro /cm2

throughout a wide range of applied voltage. When connected for service as an ionization chamber, the thermal neutron sensitivi isapproximately 1.4 x 10.13 amperes/neutron/cmvsecond with a gamma sensitivity of approximately 4.2 x 10·1lampereslRlhour.

MechanicalDiameter (50.8 mm) 2.00 InchesOverall Length (292 mrn) 11.5 InchesApproximate Sensitive Length (152) 6 InchesNet Weight (794 grams) 1.75 PoundsShipping Weight (5.4 kg) 12 Pounds

MaterialsOuter Case : AluminumElectrodes AluminumInsulation A1203

Sensitive Material:Amount ofU235 in U308 >90 %Thickness ~ 2.0 m'g/crn2Gas Fill Ar-NGas Pressure 76 crn-Hg

Maximum RatingsVoltage between Electrodes 1000 VoltsTemperature (lSO°C) 300 OFExternal Pressure (Note 1) (7.0 kglcm2)100 psigThermal Neutron Flux .3 x 10lDnv

Impedance

Resistance (minimum) (At Max. Temp.) 10.9 OhmsCapacitance 150 pF

Typical Operation as a Connter (at approx. 25°C)Operating Voltage 300 VoltsOperating Voltage Plateau 200-800 VoltsThermal Neutron Flux Range 1.4 to 1.4 x 105 VoltsSensitivity (Note2) 0.7 nvOutput Pulse Characteristics:Amplitude (unloaded) 2 x 10-4VoltsInherent Rise Time (average) 2 x 10.7 Seconds

Tube Number: WL-6376A Page 2

Typical Operation as a Chamber (at approx. 25°C)Operating Voltage (Note 3) , 300-1000 VoltsThermal Neutron Flux Range (Note 4) 6 xlO'5 to 1.4 x 1010NvThermal Neutron Sensitivity 1.4 x 10-13AlnvGamma Sensitivity 4.2 x 10-11AlR/HrAlpha Background Current 1.6 x IO-8A

Notes

1. The pressurizing atmosphere must be dry and non-corrosive.2. The sensitivity given is with the alpha background counting rate of the naturally radioactive uranium adjusted to 5 counts/second. By

varying the pulse height selector on the associated circuitry, or by use of high resolution circuitry, other sensitivities are available.3. The minimum voltage required for saturation is dependent upon the incident neutron flux level.4, The lower limit of operating range is determined by an inherent alpha background current.

Document information is subject to change without notice and contains proprietary information which may not be accurate.

Data Sheets - Marketing\6376A Scanned 07113/09

ITECHNOLOGIES

Uncompensated Ionization Chambers3" Diameter - Guard Ring

MaximumTemp. of

300575300300

SensitivityA/nv

7.6 x 10.14

7.6 X 10-14

7.6 X 10.14

3.3 X 10·]3

TubeType

---.;1>--==-WL-6937 AWL-7606WL-8075WL-23272

Sensing Systems Division

. ApplicationThis group of uncompensated ionization chambers is designed to operate in a thermal neutron to gamma flux ration of 104 IlV to IRzbr or greater, These Chal1E~feature guard-ling construction to minimize the effect of interelectrode leakage currents, They are extremely rugged and may be operated in any position up to eirrated temperature, The materials used in construction of file detector, including those of the type HN connectors, have been selected for low activation prope ies,This reduces the magnitude and duration of act ivation currents and facilitates handling after exposure to high neutron fluxes.

-ItWL-6937A

3.0013.627.02.5

10.0

MechanicalO.D., Nominal .Length, Nominal .Sensitive Length, Nominal .Net Weight .Shipping Weight , .

WL-23273.00

21.5014.03.75

11.5

UnitsInchesInchesInchesPoundsPounds

WL-76063.00

13.627.02.5

10.0

WL-80753.00

13.627.02.5

10.0

MaterialsOuter Case .................................................. .; .................. Aluminum Aluminum Aluminum AluminumElectrodes. ....................................................................... Aluminum Aluminum Aluminum AluminumInsulation ......................................................................... AhO, AhO) AhO) AhO)Neutron Sensitive Material:

Content ....................................................................... Boron (Bill) Boron (B'") Boron (B'o) BIOF)Thickness ................................................................... mg/cm2 0.8 0.8 0.8

Gas Fill ....................................•....................................... Ar-Nz Ar-N2 AI'-N2 81°F3

ImpedanceResistance, Minimum:

Signal Electrode to Case ............................................ Ohms 1011 1011 1011 1011H.V. Electrode to Case .............................................. Ohms 1011 1011 10-" 1011 -1

Capacitance (Notel):,

Signal Electrode to Case ........................................... pF 170 170 170 180H.V. Electrode to Case .............................................. pF 250 250 250 275

Maximum RatingsVoltage Between Electrodes: ......................................... Volts d.c, 1500 1500 1500 2500

Temperature ............................................................... OF 300 575 300 300External Pressure (Note 2) ........................................ PSI 180 180 180 180

Thermal Neutron Flux .................................................... llV 2.5 x 10" 2.5 X ro'' 2.5 X io" 2.5 X 10"Gamma Flux ................................................................... Ribr [07 [07 107 107

Typical OperationOperating Voltage (Note 3) ........................................... Voltsd.c. 200-1000 200·1000 200-1000 200-2000Saturation Characteristics .............................................. See Fig. 6 See Fig. 6 See Fig. 6 See Fig. 5Thermal Neutron Flux:

Lower Limit ................................................................ nv 2.5 x 102 2.5 X 102 2.5 X 102 3.0 X 101

Upper Limit ................................................................. nv 5.0 x 1010 5.0x 10'" 5.0 X 1010 5.0" 109

Thermal Neutron Sensitivity:Reactor (Note 4) ......................................................... Alnv 4.4 x 10.14 4.4 X 10.14 4.4 X 10.14

Source Box (Note 5) ................................................... Alnv 7.6 x 10.14 7.6 X 10.14 7.6 X 10"4 3.3 X 1O-t)

Gamma Sensitivity: (Note 6) ....................................... AlR/hr 4.0.x 10.11 4.0x 10.11 4.0 X 10''' 1.3 x ]0.1(1

NotesI.2.3'.4.5.

tCapacitance is measured between an electrode and case with all other electrodes grounded 10 the case.The pressurizing atmosphere mnst be dry and non-corrosive,The saturation voltage varies with CUITent level. See saturation characteristics for proper operating voltage.The reactor sensitivity was determined experimentally. however perturbation effects may alter the effective neutron sensitivity.The Thermal Neutron Sensitivity is determined in a Pu-Be source box. Reactor environments often produce significant flux perturbation which n . yalter the effective neutron sensitivity.The gamma sensitivity is determined in a Co'" flux.6.

Uncompensated Ionization Chambers3" Diameter - Guard RingPage 2

TubeType

~WL-6937AWL-7606WL-8075WL-23272

MaximumTemp. OF

300575300300

WL-6937AWL-8075

FIGURE 1

SensitivityAlnv

7.6 x 10-14

7.6 X 10-14

7.6 X 10-14

3.3 X 10-13

WL-760a

(21 HN ,JocksMole withNIL-UC S9A/Uor~uf'tCltJlt./'

FIGURE 2

WL-23272

(2) HN Jack.Mal ••• 1It1MIL-\IG 59AIUOffllu}volcnl.

/

TYPICAL CONNECTION DIAGRAM

FIGURE 4

FIGURE 3

WL·232721)'P1CAL SATURATION CHARACTERIS11CS

[ 10-3cr~E!l~~ttti~

~ Ir;

WL·6937AWL-7606WL-B075

TYPICAL SATURATION CHARACTERISTICS

10'2 !mffittmtm

I1O-70~~~~~~~~~~~1~~~1~~

Applied Volls de, CC..••.I2..'R A4

FIGURE 6

RANGE CHART

!63A

JO-3A

-=

i"IOIiA

!O-fIAWl:6937 A---'WL-7606

Wl:23272 WI:B075

10'2

FIGURE 7

600 1200 1600 2400 3000

AppJlad VOIiIi d.c..

FIGURE 5

Document information is subject to change without notice and contains proprietary information which may not be accurate

Data Sheets - Marketing\6937A 7606 8075 23272 Scanned 07128/11

WL-23084

MIRIONTECHNOLOGIES

Compensated IonizafonChamber

Sensor and Control Division

APPLICATION

The WL-23084 Compensated Ion Chamber is designed to operate in a thermal neutron to gamma flux rat 0 of500 nv to 1 Rlhr with 95% compensation. This chamber employs guard-ring construction to minimiz theeffect of inter-electrode leakage current, permitting operation from 230 nv to a maximum of 5x1010 nv.1Thechamber materials, including those of the type HN connectors, have been selected for their low activ tionproperties. The use of such materials reduces the magnitude and duration of the activation currents;andfacilitates handling of the chamber after it has been exposed to high neutron fluences. This chamb r isextremely rugged and may be operated in any position up to the rated temperature; however, operation i anend-on flux will shift the chamber's compensation characteristic and may alter its effective neutron sensitivi I •

MECHANICALOutside Diameter (nominal) 3.16 Inches (79.4 mm)Length (nominal) 19.17 Inches (486.9mm)Sensitive Length (nominal) 14.0 Inches (355 em)Net Weight 5.7 Pounds (2.6 kg)Shipping Weight......................................... 19.0Pounds (9.6 kg)

MATERIALSOuter Case ; .Electrodes .• Insulation .Neutron Sensitive Material Content

Thickness (Approx.) .Gas Filling .

AluminumMagnesium and AluminumAlumina CeramicB-10 Enriched Boron0.8mgicm2

Nitrogen (with Helium Trace)

L2.0

150.'1

IMPEDANCEResistance, minimum (Note 1)

H.V Electrode to Case..... 1012OhmsSignal Electrode to Case 1013OhmsCompensating Electrode to Case 1012Ohms

SEHSIfI\1iLEI"'GT"

"[3:)5.61AP~RO;l;,

Approximate Capacitance (Note 2) 290 pFSignal to Case H.V. to Case 330 pFCompensating Electrode to Case....... 182pF

MAXIMUM RATINGSVoltage between Electrodes........................ 1500 Volts DCTemperature :............................. 400°F\205°C)Thermal Neutron Flux 5 x 101nvExternal Pressure (Note 3) 180psig (12 kg/ern')

WL-23084 10-31-2007

{::S)HN JA(II;SH..I.T£W1TH

HIL-:)ti59 A/UDR EQuiVAL~IIT,

,@

191 :19(loSe. !;t..8

1712 .•.12[1.50.1 !J.o]

es.re ~ Of){aO . .3!J.5

CompensatedIonization Chamber

WL-23084

Page 2

TYPICAL OPERATIONOperating Voltage .Compensating Voltage .Saturation Characteristics (Note 4) .Thermal Neutron Flux RangeThermal Neutron Sensitivity

Source Box (Note 5) 7.6 x 10"14AlnvReactor (Note 6) 4.4 X 1O~14 Alnv

Gamma Sensitivity (Note 7)Total Compensation 0 AlR/hrUncompensated 2.3 x 10"11 AlRJHr

300 to 1500 Volts DC-10 to -80 Volts DCSee Figure 11.3 x 103 to 5.0 X 1010 nv

NOTES

1. The detector is not designed for immersion in water. High humidityenvironments may degrade performance.

2. Capacitance is measured between an electrode and case with allother electrodes grounded to the case.

3. The pressurizing atmosphere must be dry and non-corrosive.

4. Saturation voltage varies with current level.characteristics for proper operating voltage.

See saturation

I5. Thermal neutron sensitivity is evaluated using an AmBe source.

Reactor environments often produce significant flux perturbationwhich may alter the effective sensitivity.

6. The reactor sensitivity was determined experimentally. However,perturbation effects and reactor spectrum may alter the effectiveneutron sensitivity.

7. The gamma response is determined using a Co60 source.

WL-23084 10-31-2007

cnEnComissao Nadonalole Energia Nuclear

Mirion Technologies

Mr. Tim Pelot

The equipment (chamber) have been used inside of the "Research Nuclear Reactor lEA-Hi". This Reactor waslaunched in 1957 by the program called "Atoms for Peace" established in USA.

The objective of this reactor is the production of radioisotopes for medicine, especially for the research inthe agricultural and other types of industry. The reactor has been used in on site training as well.

Currently the reactor operates 64 hours in total, on rotating shifts, in order to produceradiopharmaceuticals. The current power is 4.5 MW and can reach 5 MW which is the limit of this type ofreactor. The reactor is about 270 cubic meters with light water, graphite and beryllium reflectors asmoderators ..

This reactor consumes U3Si2AI (20% enriched) fuel, MTR type, which is manufactured in IPEN, parallelplate, in a total of 24 elements with four absorber bars composed of Ag Iin / Cd.

The cameras are part of the POWERCHANNELAND BROAD BAND CHANNEL (CHANNELSTARTING LOGIlINEAR).IPEN also has a power channel through the N-16.

In case you need more explanation, please let me know how Ican be of any help.

Sincerely,

WALTER RICCIFILHO

HEAD OF IEA-Rl NUCLEAR RESEARCHREACTOR

COMiSSAO NACIONAl DE ENERGIA NUCLEAR - CNENINSTITUTO DE PIESQUISAS ENIEIRGETICAS E fIIUCLEARES - IPENAv. lineu Prestes, 2242 - Cldade Universiiaria - CEP 05508-000Fone: (05511) 31338820-31338814 Fax (05511) 31338815Sao Paulo - Estado de Sao PauloE-mail: wricci@ipen.hr