ML20093M737

Rev 5 to Calibr Rept for Model RD-52 Offline Beta Detector

ML20093M737
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	10/31/1984
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20093M728	List: ML20093M727 ML20093M735 ML20093M737
References
E-115-647, E-115-647-R05, E-115-647-R5, NUDOCS 8410230211
Download: ML20093M737 (33)

Text

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i t-t i- * - E-115-647 (Rev. 5) i i

e i 9 l s CALIBRATION REPORT I FOR MODEL RD-52 0FFLINE BETA DETECTOR j

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@ Copyright GA Technologies Inc.1984 i

All Rights Reserved

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i October 1964 ,

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E-115-647 CHANGE RECORD

, . Issue Date Pages Affected ,

Original April 1977 All Rev. 1 May 1979 Cover, change record, 4 Rev. 2 March 1980 Cover,_ change record, 6, 7, 8, 9 Rev. 3 May 1980 Cover, change record, 1,3,7,9 Rev. 4 January 1983 All Rev. 5- October 1984 Cover, change record, 9

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Wherever reference is made in this document to General Atomic Company or one of its divisions, it l

'shall be understood to mean GA Technologies Inc.

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CONTENTS

1. INTRODUCTION . . . . . . . . . . . ............... . 1

.. 2. DETECTOR DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . ' . 2 3 SETUP AND PROCEDURE ....................... 3

4. ENERGY RESPONSE CURVE ...................... 8

5. CORRECTION FOR SAMPLE CHAMBER PRESSURE . . . . . . . . . . . . . . 10

6. DESENSITIZED DETECTORS . . . . . . . . . . . . . . . . . . . . . . 14

7. BACKGROUND . . .......................... 19

8. LINEARITY TEST . . . . . . . . . . . . . . . . . . . . . . . . . . 20 8.1. Objective ......................... 20 8.2. Method . .......................... 20 8.3 Results ........-......-............

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'8.4 Conclusions ........................ 23 APPENDIX . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-i FIGURES

1. RD-52 sensitivity test setup . . . . . ............. . 4

2. y Energy response curve for RD-52 offline beta detector

' operating at 760 mm Hg abs and 25 C . . . . . . . . . . . . . . . . 9

, 3 RD-52 response versus chamber pressure .............. 12

. 4. Setup for RD-52 linearity test .................. 21 TABLES

1. Detector alignment . ....................... 5

2. Detector alignments using Cl-36 source serial no. CL36-113 . . . . 6 3 Kr-85 and Xe-133 calibrations .................. 7 4 Correction for sample chamber pressure . . . . . . . . . . . . . . 11

5. Nominal and effective phosphor sizes and ratios ......... 15

6. Test results for desensitized detectors ............. 16 i

7. Solid source response ...................... 17

, 8 .~ Calculated solid source response for round phosphors . . . . . . . 18

9. Backgrouhd data ......................... 19

- 10. RD-52 Linearity test data .................... 22 S

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1. -INTRODUCTION

-Since 1977, a series.of calibration tests has been performed on the

'RD-52 offline gas detector. Response to menon 133 gas has been corrected.

Response to krypton 85 gas was confirmed. The effects of sample chamber

. pressures for menon 133 and krypton 85 responses were obtained. The res-ponses of detectors with various sizes of scintillators were obtained.

Linearity tests to show the response of countrate versus activity strength were performed.

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2. DETECTOR DESCRIPTION

- The Rb52 is an ortline beta detector assembly designed for detecting the radioactivity in a continuous gas sample.

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3 SETUP AND PROCEDURE l

The. detector, a 0.1 to 20 mm Hg pressure gage, a 0 to 800 mm Hg pres-sure gage, a vacuum pump, and, alternatively, cylinders of Xe-133 and Kr-85 gases were connected to a manifold (see Fig. 1). Prior to injecting any

• - radioactive material into the system, the detector was aligned using cali-brated solid sources positioned in front of the light-tight window on the scintillator. The high voltage and discriminator voltage levels cere set to obtain a good counting efficiency for the C-14 source. Background counts and counting efficiencies for C-14, Tc-99, Cl-36, and Sr-90 were recorded (see Tables 1 and 2). The system was then evacuated to less than 0.1 mm Hg abs and. backfilled with the gas mixture to 755 mm Hg abs. Counting effi-ciencies obtained are shown in Table 3 All of the count rates were ob-tained on a scaler / timer.

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0.1 TO 20 mm Hg 0 TO 800 mm Hg ABSOLUTE y ABSOLUTE

! PRESSURE GAGE A PRESSURE GAGE PRESSURE GAGE

[ X X X LECTURE 80TTLE

,] K CONTAINING I RA010 ACTIVE l GAS i

I R0-52 SAMPLE CHAM 8ER ANO 1

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l j l VACUUM i PUMP 1

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-- AMMETER

l RP-30 RADIATION i C- ANALYZER --

VOLTMETER

', OR RM-80 PREAMP BOARD i

! SCALER / TIMER EL-2585-1 l

Fig. 1. RD-52 sensitivity test setup l

TABLE 1 DETECTOR ALIGNMENT

. (Detector removed from shield and sources positioned in contact with window)

Activity (ope) GA Source No.

. Background 113 -

C-14 (0.180 pci - 135 eff)I* 2.508 net c-114-101 Tc-99 (0.170 pci - 285 eff) 30,080 net Tc-99-102 ci-36 (0.184 yci - 615 eff) 138,960 net cl-36-113 3r-90 (0.185 vc i - 645 eff) 308.700 net Sr-90-101

(* See Appendix fo.a assay and efficiency certification.

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TABLE 2 DETECTOR ALIGNMENTS USING Cl-36 SOURCE SERIAL NO. CL36-113 Net Countrate CL36-113 Date (ope) 3-23-77 138.960 6-04-80 141.306 6-05-80 141.407 4-08-82 138.592 8-05-82 139.852 i

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TAOLE 3 Er-SS AaB 1*-133 CALIDOATICBS Aettwity .

l Ser. Be. At flee of Bet op Sonettivity Aettvity Date Date Melf Celthrottee for ese 3 3 l

Isotope (wC1/em ) of Aeoey of Calibretten Life (sC1/ee ) RD-52 oc1/em I 2012 1.F.L 1200 ter 8-1-42 1315 hr 8-5-42 8.76 a 10~3 2.57 x 105 2.93 x 107 1.5 a 14 5.254 E0-133 1.F.L. Im W W #*F* 7.71 a 10~3 2.28 x 10 5 2.96 a 107 1300 w 4-8-82

! 1.01 a 10 1.F.L. #20-121 8.43 E 104 7.06 s 107 3-23 77 5.97 x 10 3

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• 3 16 6-5 30 6.45 x 10 4.99 x 10 7.28 x 10 0.157 6 ,,7 Er-85 diluted to 1.79 x 10 7,,, ,

2.49 x 10 GA #106 0.168 5-7-79 6-4-80 0.157 diluted to 1.87 a 10 7.19 s 10 2.60 x 10-3 Average Sensitivities Ie-133 2.94 x 10Ie p (wC1/em3 )~I Er-85 7.19 u 107 e;n (pC1/ m 33-1

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.4. ENERGY RESPONSE CURVE  !

The energy response ourve (see Fig. 2) can be useful when calculating a L counting efficiency for an espected source ters. The source ters of inter-est must contain the following information when calculating an expected detector' response.

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1. Isotopes of interest and their intensities (the sum of the individ- l:

ual intensities is equal to one). [

l 2. Each beta with its energy in MeV and number produccd per disinte- '

gration.

Beta response can now be obtained from the energy response curve. This

! response in opa/(microcuries/onI ) (assuming one beta per disintegration)

! sust be corrected for the intensities of the isotope and the number of betas produced per disintegration. The set of these beta responses is the expect-ed response in ope /(microcuries/em 3 ) for the source term of interest. The I reciprocal of the detector response is the . detector conversion factor

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(mierocurles/os 3)/ cpm.

This conversion factor, when footored into the RM-80 data bese, can l 3

provide a storocuries/on equivalent for a known source term. f The shape of the energy response curve was obtained from the solid source data in Table 1. After the shape of the curve was established, the curve was superimposed over the actual responses for Yr-85 and Xe-133 to provide the surve in Fig. 2.  ;

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ISOTOPE AVERAGE ENERGY (MeV) MAXIMUM ENERGY l'isV)

C-14 0.049 0.158 Tc-99 0.086 0.295 C1-36 0.252 0.714

- Sr-90/Y-90 0.200/0.931 0.544/2.245 Xe-133 0.099 0.343 Kr-85 0.249 0.672 100 _. *-

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1 O.1 0.2 0.3 0.4 0.5 0.60.70.80.91 2 3 ENERGY,Smax (MeV) 6 3 NOTE: USE 87 x 10 CPM ( Ci/cm 3-1 FOR ALL DETA ENERGIES ABOVE 2.2 MeV.

THIS WILL PROVIDE A CONSERVATIVE ESTIMATE OF THE EXPECTED RESPONSE.

Fig. 2. Energy response curve for RD-52 offline beta detector operating at 760 mm Hg abs and 25'C 9

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5. CORRECTION FOR SAMPLE CHAMBER PRESSURE Since the response (counts per minute for one microcurie per om ) of ,

noble gases emitting beta radiations for GA's RD-52 gas detector chambers was determined _at-atmospheric pressure (760 mm Hg A), corrections may be required when operating the detector chambers at pressures other than atmospheric. The response to. beta radiations will vary not only for in-creasedoor decreased amounts of microcuries in the chamber due to the pressure changes, but also will vary for differences in self absorption

. caused by density changes of the sampled gas. Tests were run during July and ' August of 1982 to determine these effects for Xe-133 and Kr-85 radio-active gases. Upon red'ucing the test data, empirical . formulas were produced to provide pressure . corrections for specific conditions. (See Table 4 and

Fig. 3.) These test conditions may not' exist at an operating power plant.

Caution must be used when entering correction factors into the RM-80 data

-base so that the actual ~results are not overcorrected, thus causing addi-tional errors.

Listed.below are the correction factors obtained from the tests and the i" specific test condf.tions.

The following expression is use'd for correcting detector response in

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l counts per minute (cpm) at-various pressures to equivalent response in cpm at atmospheric pressure (760 mm Hg A) for Kr-85 and Xe-133 noble gases in a dry N atmosphere.

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e TABLE 4 CORRECTION FOR SAMPLE CHAMBER PRESSURE

• Percent of RD-52 Detector Atmospheric Chamber Response (Sea Level)

Pressure (cpm) Response Xe-133 Kr-85 Xe-133 Kr-85 15 psig 3.69 x 10 5 8.24 x~10 6 143 164

. 12 psig 3.53 x 10 5 7.76 x 10 6 137 155 5 6 9 psig 3 34 x 10 7.15 x 10 130 143 6 psig 3 12 x 10 5 6.50 x 10 6 121 130 6

3 psig 2.88 x 10 5 5.83 x 10 112 116 ATMOS 2.57 x'10 5 5.01 x 10 6 100 100 5 6 5 in. Hg vac L2.26 x 10 4 31 x 10 89 86 6

10 in. Hg vac 1.92 x 10 5 3 59 x 10 75 72 15 in. Hg vac 1,56 x 10 5 2.81 x 10 6 61 56 5 0 20 ins Hg vac 1.12 x 10 1.96 x 10 44 39 11

PSIG 0 2 4 6 8 10 12 14 200

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28 24 20 16 12 8 4 0 CHAMBER PRESSURE (IN. Hg VACUUM)

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POSITIVE PRESSURE CORRECTION 14.7-(Pp + 14.7)(1-P p p A) where P = positive pressure in chamber (psig) -

p

, Ap= 0.021 for Xe-133 in RD-52 Chamber

= 0.009 for Kr-85 in RD-52 Chamber

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The.above correction is accurate to 315 for 0 to 12 psig Xe-133 and 0 to 13

. psig Kr-85.

- NEGATIVE PRESSURE CORRECTION CF = (30-P, + P,An where Pn = negative pressure in chamber (in. Hg vacuum)

An.= 0.013 for Xe-133 in Rd-52 Cnamber

= 0.004 for Kr-85 in RD-52 Chamber The above correction is accurate to +15 for 0 to 15 in. Hg vacuum.

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Under some conditions it may not be necessary to correct for self atten-l' untion and A , A can M equal to zero.

n p EXAMPLE:

g If the overall error due to self absorption can be +10% or less A , A n p can equal zero for:

RD-52 w/Xe-133, 5 in. Hg vac to 3 psig RD-52 w/Kr-85. 15 in. Hg vac to 9 psig

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6. DESENSITIZED DETECTORS To meet special requirements, a detector may be desensitized. GA has

.' manufactured detectors with varying sensitivities of approximately 0.1, 0.01 and 0.001 times the standard RD-52 sensitivity. The decreased response is y obtained by. varying the size of the plastic scintillator. The standard plastic scintillator has a nominal 2-in. diameter phosphor. Desensitized

, scintillators have been made with either round or square phosphors. It has

, been found that when producing the plastic phosphors, closer tolerances can be' maintained when cutting a square. The desensitized phosphors are cut to have surface areas of.0.1, 0.01, and 0.001 of the nominal 2 in. diameter phosphor. The sizes used are 0.63 in, diameter, 0.2 in. diameter, and 0.063 in. diameter for the circular scintillators and 0.56 x 0.56 in. , 0.177 x 0.177 in., and 0.056 x 0.056 in. for the square scintillators. The effec-tive area of the standard RD-52 detector is 1-7/8 in. in diameter because of the-sealing ring. It was also observed that the sides of the desensitized phosphors are effective scintillators. All the phosphors are 0.01 in.

i thick.- See Table 5 for actual effective scintillator surfaces areas and ratios of areas.

L 9 Tests were performed with a standard nominal 2 in. diameter 0.56 x 0.56 in., 0.177 x 0.177 in., and a 0.056 x 0.056 phosphor. See Table 6 for test results.

l Tables 7 and 8 show the responses of the various size phosphors to GA

[ standard sources. These counting efficiencies can be used when aligning production detectors to obtain similar counting efficiencies as in the L prototype tests.

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TABLE 5 NOMINAL AND EFFECTIVE PHOSPHOR SIZES AND RATIOS Nominal Effective Nominal Ratic of Ratio of Phosphor Areas to Areas to j Size Std RD-52 Effective Surface Area Std RD-52 2 in, dian std RD-52 1.0 w/4 (1-7/8)2 = 2.76 in.2 1.0 0.63 dies w/4 (0.63)2 + 3(0.63)(0.01) .= 0 332 in.2 0.120 0.1 0.122 i _. 0.56 x 0.56 in. (0.56)2 + (4)(0.56)(0.01) = 0.336 in.2 1

sn 0 2 in. dian w/4 (0.2) + w(0.2)(0.01) = 0.0377 in.2 0.0137 0.01 0.18 x 0.18 in. (0.18) + (4)(0.18)(0.01) = 0.0396 in.2 0.143 0.063 in dian w/4 (0.063)2 + w(0.063)(0.01) = 0.00510 in.2 0.00185 0.001 0.056 x 0.05 in. (0.056)2 + (4)(0.56)(0.01) = 0.00538 in.2 0.00195 i

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1 TABLE 6 TEST RESULTS FOR DESENSITIZED DETECTORS Sensitivity cpe/pci/cm 3 Nominal Effective Net cps

Phospor Ratio of T 1/2 Correction Ratio of Xe-133 Based- Kr-85 Based Size Area to to 1300 Hr ops to on 2.94 x 10 on 7 19 x 10 3

cpa/pci/cm epa /pC1/cm 3 (in.) Std RD-52 4-08-82 Std RD-52 1

7 Std 2.9 diam 1.0 2.28 x 10 1.0 2.94 x 10 7.19 x 10 6 6 0.56 x 0.56 0.122 2.73 x 10" 0.120 3 53 x 10 (a) 8.63 x 10 (a) 6

$ 0.63 dian 0.120 - -

3.47 x 10 (b)- 8.49 x 106 (b) l 0.18 x 0.18 0.0143 3 30 x 10 3 0.0145 4.26 x 105(a) ,,gg , 3,6(a) 0.2 dian 0.0137 - - 4.08 x 105 (b) 9.96 x 105(b) 0.056 x 0.056 0.00195 4.48 x 10 2 0.00196 5.76 x 10"I") 1.41 x 105 (a) 0.063 dian 0.00185 - -

5.46 x 10"(D 1.34 x 105 (b)

,

• Calculated: (Ratio of cpm to std) x (std sensitivity)

Calculated: [(Sensitivity sq) x (eff area ratio round )] + eff area ratio sq

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TABLE 7 SOLID SOURCE RESPONSE Phosphor Size Net epm (in.) Source 4-09-82 STD RD-52 cl-36 CL36-113 138.369 0.056-.x 0.056 cs-137 CS81-542 615

- Square Cs-137 cS81-530 4,895 0.18 x 0.18 cs-137 CS81-542 i4,918 Square Cs-137 CS81-530 39,110 0.56 x 0.56 cs-137 CS81-542 43.494 Square cs-137 CS81-530 339.455 The Cs-137 Sources CS81-542 and CS81-530 were positioned with a fixture that insured a repeatable geometry.

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p TABLE 8 CALCULATED SOLID SOURCE RESPONSE FOR ROUND PHOSPHORS a

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Phosphor Size Calculated cpm

-(in.) Source for 4-09-82 2

cs-137 CS81-542 5.83 x 10 0.063 diam-4.64 x 10 3 Cs-137 CS81-530 3

Cs-137 cS81-542 4.71 x 10 0.2 diam CS-137 CS81-530 3.75 x 10 cs-137 CS81-542 4.28 x 10" 0.63 diam Cs-137 CS81-530 3 34 x 10' i

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7. BACKGROUND ~

The RD-52-30 detector was scanned from all directions with a Co-60 point source producing 2 mR/hr and a Cs-137 point source producing 20 mR/hr.

The RD-52-60 detector was scanned with a Co-60 point source producing 5 mR/hr.

Background data are compiled in Table 9 TABLE 9 BACKGROUND DATA Ambient Co-60 Cs-137 Background Inet cpm) Inet epmh q

. Sampler (cpm) ( mR/hr ( mR/hr j RD-52-30 20 43 (max) 6 (cax)

(3 in lead)

RD-52-60 19 No detectable increase

~-

(6 in. lead) above ambient in a 5 mR/hr Co-60 field

RD-52-50(*} 44 .2 (max)

• Tests were conducted on March 21 and March 24, 1980, using a production detector. The detector was scanned with a Co-60 point source producing 5 mR/hr. Data are recorded in General Atomic Lab

-Notebook No. 8185 on pages 88, 89, and 90.

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8. LINEARITY TEST

- 8.1. OBJECTIVE The purpose of the linearity test is to show the response of the detection system for countrate versus activity strength.

8.2. METHOD

.A monoenergetic radioactive nuclide, 10 millicuries of cesium 137, was placed at s ' fixed distance from the detector. Lead attenuators of similar thickness,1/4 'in. (approximately one-half-value layer thickness), were inserted one at a time between the detector and the source. Countrate readings taken before and after adding each attenuator were compared and the percentages of countrate changes were calculated. The tests were repeated to cover .the operating range of the detection system for the decade.above background (102 to 10 3 cpm) to the upper decade or response (10 6 to 107 cpm).- See Fig. 4 for test setup and Table 10 for test data.

83 RESULTS

- The actual change in countrate within the operating range of the 2

• y detector from the decade above background (10 to 103 cpm) through the last decade (10 to 10 Icpe) was found to be between 495 and 535 for one 1/4-in.-

^

thick lead attenuator. The change varied 3,25 from a mean of 515. There-fore, it can be concluded that the detection system is linear within +2% ,

when actual countrate is compared te, activity strength for the operating range of one decade above background to the uppermost decade.

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', , LEAD ATTENUATORS 10-mci Cs-137 j POINT SOURCE j .

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1 j DISTANCE KEPT

< ~ CONSTANT FOR r DETECTOR ASSEMBLY EACH SETUP i

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EL-3512 i

1 Fig. 4. Setup for RD-52 linearity test i

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' ' TABLE 10 RD-52 LINEARITY TEST DATA (,)

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- No. of 1/4 in.

Lead Countrate Attenuators Attenuation Added cpm (5) 0 4.148,259 51 1 2,039,384

, Setup 52 1 2 970,229 "" *""*

53 3 456,534 in countrate = 51%

0 500,260 50 1 248,600 50

, 2 123,504 51 setup 3 60,651 51 2

4 29,816 52-5 14.236 50 6 7,067 0 8,019 49 1 4.065 51 Setup 2 1,983

52

. . 3 3 944 49 4 479 (a)The above data are from General Atomic Lab Notebook 8169, pages 61 and 62.

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8.4. CONCLUSION On the linearity test requirement, consideration has been given to using sources that would provide countrates in the first, third, and sixth decades. Since individual sources are usually assayed to within only +10%,

' this could place an uncertainty of 20% in countrate from one decade to the next and indicate the possibility of nonlinearity when in fact no nonlinear-ity exists. The method of using one source with a series of attenuators of the same thickness is a more positive method of determining linearity, as

, these test results show.

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W ISOTOPE PRODUCTS LABORATORIES 404So LAKE SL,BURbek, Calif.91502 /213-843-7000 GASEOUS STANDARD DATA SHEET AMD CERTIFICATION

,Cuctomer:_b enfre) A b MIC P.O. 4f79959 w.o.6 44'0 Date: /2 /(13" Catalog # SAS-tr5 Container: Lecture Bottle: dot 3 E 1800 S/N hc. / "2 / ( U M /A)

Icotope: MP- If's

'rrier Gas: k$.

, Cantained Activity: 3. I,f />b d #* /E

!- tit._of Gas: /pr. 3 2 o, a g

. 'Cancentration (uci/cc): O . 7/6 2 c.c69 X/0 4

['Calibra'tionDate: /Q[/f[f / Q .' 00 Gauge Reading at Time of Shipment: /37e Ps/ C nn h >> >L M Karl Amlauer, Technical Director 4

4

.:..:;c.vy ;.. ; :... ,. . .m.:c,e3 a N,w.,,y.,

. . - . - . . . . ~ . . - - . . - - _ . - - _ _ - _ - - , . _ . . . _ -

CERTIFICATE OF RADIOACTIVITY CALIBRATION Carbon-14 Reference Source

' NES-9999

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Half-Life: 5730 i 40 years Lot Number:

The activity of Carbon-14 was found to be, 0.184 microcuries in June,1972.

DESCRIP_ TION OF THE _ SOURCE The activity was incorporated into a small amount of epoxy which was unifonnly distributed in an aluminum mount. The mount has an inner diameter of 1.375", an outer diameter of 1.5", and a height of 0.062".

METHODOFCALIBRATIOfl, A stock solution was calibrated by liquid scintillation counting using toluene-C-14 as an internal standard. The toluene-C-14 had been previously calibrated using the National Bureau of Standards benzoic acid standard #4925 as an internal standard.

IMPURITIES Less than 1% according to manufacturer specifications.

ERRORS Random Errors _ (3 times the standard deviation) 2.5%

. Precision of the NEN measurement

"," Systematic Errors Accuracy of the NEN standard 3.0%

a.

Error in preparation method 0.5%

b.

Overa_ll Error

+ 3.0 + 0.5 = 2 6.0%

2.5 The counting rate of the source was found to be 13.03% of the counting rate of an essentially weightless source as determined by 2w internal proportional counting.

h~New England Nuclear 575 Albany Street, Boston. Mass. 02118 CUSTOMER SERVICE: (617) 482-9595

CERTIFICATE OF RADIOACTIVITY CALIBRATION

- Technetium-99 Reference Source NES-9999 Half-Life: 2.1 x 105 years Lot Number:

The activity of Technetium-99 was found to be, 0.172 microcuries in June,1972.

DESCRIPTION OF THE SOURCE

- The activity was incorporated into a small amount of epoxy which was uniformly distributed in an aluminum mount. The mount has an inner diameter of 1.375", an outer diameter of 1.5", and a height of 0.062".

METHOD OF CALIBRATION A stock solution was calibrated by liquid scintillation counting at 100% efficiency by extrapolation of discriminator settings. The conditions for 100% efficiency were determined using standards based on National Bureau of Standards assays and are checked using Chlorobenzene-chlorine-36 as a reference standard. Then an aliquot of the stock solution was ur.iformly distributed throughout a weighed amount of epoxy.

If! PURITIES Less than 1% according to manufacturer specifications.

ERRORS

! Random Errors (3 times the standard deviation) 2.5%

[, Precision of the NEN measurement

1. Systematic Errors Error in efficiency determination 0.5%

! a. 0.5%

Error in preparation method b.

Overall Error

+ 0.5 + 0.5 = 3.5%

2.5 I The counting rate of the source was found to be 27.6% of the countino rate i

of an essentially weightless source as determined by 2r internal proportional l

counting.

h New575 England Nuclear Albany Street, Boston. Mass. 02118 CUSTOMER SERVICE: (617) 482-9595

CERTIFICATE OF RADIOACTIVITY Chlorine-36 Reference Source CAllBRATION NES-0999 Half-Life: 3.0x105 years Lot Number:

The activity of Chlorine 36 was found to be, 0.184 microcuries in June, 1972.

DESCRIPTION OF lilE SOURCE The activity was incorporated into a small amount of cooxy which was uniformly distributed in an alninum mount. The rount has an inner diameter of 1.375", an outer diar.icter of 1.5", and a height of 0.052". "

HETit00 0F CALIBRATION A stoch solution was calibrated by liquid scintillation counting it 100% cfficiency by extrnolation of discriminator settings. The conditions for 103% officie ncy mre dett:rnined usin1 standards bcsed on !!ational Bureau of Shadards assays rnd cre encched using Chlorn-benzene-chlorine-36 as a reforcr.cc standard. Then an aliquut of the stoch solution t.'as unifonaly distributed throughout a weighed amount of epoxy.

IMPURITIES Less than 1% t.f Sulfur-35 according to manufceturcr specifica-I tions.

ERRORS Random Errors (3 timas the standard deviation)

a. Precision of the NEN measurement i 2.5%

. Systematic Errors

~

a. Error in efficiency determination 2 0.5%

- b. Error in preparation method 2 0.5%

,0vcea11 F.rror_

2.5 + 0.5 .+ 0.5 = 2 3.5%

The countinn rate of the source was found to be 60.7% of the countino rate of an essentially weichtless source as determined by 23 in'ternal proportional counting.

@ New England Nuclear 575 Albany Street. Boston. Mass. 02118 CUSTOMER SERVICE: (617) 482-9595

. _ _ . _ _ _ _ _ . - _ _ _ . ~ . -

CERTIFICATE OF

. RADIOACTIVITY CAllBRATION

, Strontium-90 Reference Source NES-9999 4

Half-Life: 28.5 i 0.8 years Lot Number:

The activity of Strontiuia-90 was found to be,

. 0.185 microcuries in June,1972.

DESCRIPTION OF TliE__ SOURCE The activity was incorporated into a small amount of enoxy which was unifornly distributed in an aluminum inount. The mount has an inner diameter of 1.375", an outer diameter of 1.5", and a height of 0.062".

METl!0D OF CALIBRATION A stock solution uas calibrated by liquid scintillation counting at 100% efficiency by extrapolation of discriminator settings. The conditions for 100% efficiency were determined using standards based on National Bureau of Standards assays and are checked using Chloro-benzene-chlorine-36 as a reference standard. Then an aliquot of the stock solution was uniformly distributed throughout a weighed amount of epoxy.

IllPURITI_E_S Less than 15 based on the isotope manufacturer's specifications and tne period of time allotted for the decay of Strontium-89.

_E_R_R_O_R_S_

. Random Errors (3 times the standard deviation)

Precision of the NEN measurement i 2.5%

- Systernatic Error _s_

a. Error in efficiency determination 2 0.5%

b. Error in preparation method 2 0.5%

Overall Error 2.5% + 0.5% + 0.5% = 3.5%

The countino rate of the source was found to be 64.2% of the countina rate of an essentially weightless source as determined by 2x internal proportional counting.

575 Albany Street. Boston, Mass. 02118 CUSTOMER SERVICE: (617) 482 9595 l

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ul

s..= ::::=arr ----. .

e :- .x:na. --- :. .scwu vc.xr. v.r. :. =: . , =. ::-- :: - :. -, - .s GENERAL AfoamC CoMPANh P.O. 80x sicos .- - .

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g CERTIFICATION OF RADICACTIVITY STNTDARD -

u -

~Radionuelide Kr-85-106 Nominal Activity 0.2 gCi/cc .

Method of Measurement b) 1. ' Calibration derived frca Sigma 2 Computer Camma Ray Spectrometer calibrated with NBS Standards.

o

[] 2. Calibration derived from Ionization Chamber Calibrated to Sigma 2 Computer Ga=na Ray Spectrometer.

-[ ) 3. Calibration derived from 2n internal gas proportional counter calibrated to Sigma 2 Computer Camma Ray Spectroceter.

Accuracy overall Limit of Error (la + Systematic) tM _

'Kencrks *- - -

This standard is 'a 1PL Kr-85 standard in argon.

a -

y ,We certify that the activity (ics) was(ucre) at fo11cus: -

1. Kr-85-106 681377

.0.168 pCi/cc - at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on,7 May 1979 y -

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Radioca:.viis t .

A:mly{dce.1 C;a::.ist.rv Mar.cger u... , -

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DATA SHEET AND CERTIFICATE OF RADIOACTIVITY CALIBRATION FOR GASEOUS STANDARD Customer: General Mnm e P.O.#acrets 2. W.O.* 9 So6 Date: 29 70c.Y 198L G s.133- X Catalog # c s-gn-2 Container Lecture Bottle: DOT 3E 1800 Isotope: )(e. l33 Half Life: 6.246 clq 5 S/N: 9 2-o11 A.B,C - 9 2.- o12.

12PDT Contained Activity:((92-*lO I I" ' #8

• Calibration Date:Is W 9 1981 C.

92 -on.) 3 2 6 F.

Concentration (uCi/cc):(qg o,,) go,74 PC;/cc ea. STP 9-' 1200 PDT' IAvG 1982.

l.bl ec STP Wt. of Gas:(eacia) 2.7.3 2eg am Carrier Gas: dry O1 (qten ) 75o P5i9 **-

Gauge Rc-ading at Time of Shipment:[q3,,g) 850 p583 (d NBS Traceable (d'mtt/ indirectly) to SRM # 1800 - l

( 92ois ) "T 4%

Total Error at the 99  % confidence level isto2a.27 s.o %

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1800 Nont.k Ktvstost Sineti,Bonbask,Califonsia 91504 213-845-7000

DATA SHEET AND CERTIFICATE OF S' ~

RADIOACTIVITY CALlBRATION FOR GASEOUS STANDARD .

i.

I A4om,c. 7963co

) Customer: Ge u P.O.# W.O.# 95T1 Date: / Aor tsa:t

• Catalog # Cet-I 33- 2. Container Lecture Bottle: DOT 3E 1800 Isotope: Xe-13.3 Half Life: S. 2.~7 I dy s S/N: 8 4-C O 1 Contained Activity: 2.04, I pc ! Calibration Date: 1200 PST 6 Apes 982.

~

._ Concentration (uCi/cc): 1. c f x f o c '/cc 5TP Wt. of Gas:

2.S. 33 ,

Carrier. Gas: 1),,7 A ,

( Gauge Re,ading at Time of Shipment: 8 / o PS ( G-

- (V) NBS Traceable '# ::tt/ indirectly) to SRM # /8co-I

, . . Tbt'it'Eiror~~at the ~99

~

~-- %:cohfidence. level 'is~ 9,6 */o ~

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l- ISOTOPE PRODUCTS 1ABORATORIES 1800 Nonik KEysiONE Sinter Bi.nb4sk,Califonsia 91504 l

213-843-7000

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