ML20093M735

Rev 3 to Calibr Rept RD-72 Wide-Range Gas Monitor High & Mid-Range Detectors

ML20093M735
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	08/31/1984
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20093M728	List: ML20093M727 ML20093M735 ML20093M737
References
E-255-961, E-255-961-R03, E-255-961-R3, NUDOCS 8410230203
Download: ML20093M735 (35)

Text

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., E-255-961 (Rev. 3) a,/

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l CALIBRATION REPORT ,

i RD-72 WIDE-RANGE GAS MONITOR  !

HIGH AND MID-RANGE 4

i DETECTORS  :

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@ Copyright GA Technologies Inc.1984 w All Rights Reserved u

-} August 1984

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. . CHANGE RECORD

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Issue Date Pages Affected

-Original 9/81 All Rev. 1 11/81 Cover, 7 Rev. 2 1/83- All Rev. 3 8/84 Cover, 11, 12, 13, 15

.'Wherever reference is made in thi s document to General Atomic Company or one of its divisions, it shall be understood to mean GA Technologies Inc..

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. CONTENTS

1.- INTRODUCTION . . . . . . . . . . . . . . . .... ........ . 1

2. DETECTOR DESCRIPTION . . . . . .... .... . ..... .... 2 n- 3 SETUP AND PROCEDURE . . . . .. .... .... . .. ..... . 3

4. DETECTOR CORRECTION FACTORS . .................. 7

-os 5.- ENERGY RESPONSE CURVE . . . . ..... .... ......... 10

6. LINEARITY TEST . . . . . . . . . . . . . . . . . . . . . . . . . . 16 6.1. Objective . . . . . . . ................. . 16 6.2. Method . . . . . . . . . ..... ....... .... .. 16 6.3.. Results .. . . . . . . . ... . ... .... . . .... . 16

7. ACCURACY , . . . . . . . . . . ........ .......... 19

8. BACKGROUND . . . . . . . . . .... ..... ........ . 20

. APPENDIX . . . . . . . . . . . . . . . . . . . ... .. ....... A-1 FIGURES

'1. Test setup for calibrating the RD-72 detector . . ........ 4

2. Half life correction . . . . . . . . . . . . . . . . . . . . . . . 9 3 Mid-range detector energy response curve . ... .... ..... 12

4. High-range detector energy response curve ........... . 13

5. Setup for linearity test . . . . . . . -. . . ........... 17 r

TABLES

. .i

-6'

1. Detector response to gaseous and solid test sources .. .. ... 5 2..-So1Ld sources used for energy response curves ........ . . 14 Example for calculating detector response for an 3

expected hypothetical source term for high range detector . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

4. Linearity test data . . . . . . . . . . .. . . . . ... .. . 18 i

1. INTRODUCTION Euring-the period August through November 1982, calibration tests were

,' ' performed on the RD-72 detector.

e Xenon 133 and krypton. 85 radioactive gases were purchased from Isotope

_ Products Laboratories. ' After the prototype detector sample chambers were filled to atmospheric pressure, the Xe-133 lecture bottle was sent to the National Bureau of Standards (NBS) for verification of calibration (see Appendix for certificates of calibration).

A number of solid uncalibrated beta and gamma sources were used to

(

obtain counting efficiencies from individual detectors. A number of detec-tors obtained.from production stock were evaluated using Ba-133 and Cs-137 solid gamma sources, Cl-36 and Kr-85 solid beta sources, and the calibrated Xe-133 and Kr-85 gases.

' Calibrated beta, ceta-gamma, and gamma sources were procured from Isotopes Products Inc. for performing energy-response tests with a number of detectors. (See Appendix for certificates of calibration.) A linearity test' was performed on one detector to show response for the -full 6-decade range of the detector.

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l 2.' DETECTOR DESCRIPTION

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The RD-72 is'a dual-range beta-gamma sensitive gas detector assembly,

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consistin'g of two sample chambers (approxim'ately 0.02 cc and 30 cc active -

volume), coupled directly to solid-state CdT$(C1) detectors. These detec-

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tors are connected-directly to individual charge-sensitive preamplifiers and

' assembled inside a 6-in.-thick lead background shield.

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,3 SETUP AND PROCEDURE

- A number of detectors were obtained for testing from production stock.

4,*- 1Each detector was. evaluated for response to calibrated noble gases Xe-133

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and'Kr-85 and a number of solid beta and gamma sources. Each detector was

-M aligned for gross counting with a 60 kev threshold. A Canberra model 30

. multichannel analyzer was used to obtain the data. (See Fig. 1 for test setup.)

Solid Ba-133 and .Cs-137 gamma sources were used for the detector alignment. The initial alignment was performed using 80 kev gamma and Cs X-ray photopeaks from the Ba-133 source. The alignment was verified by

^

observing the Ba-133 356 kev gamma and the Cs-137 662 kev gamma photopeaks.

' Counting efficiencies for each detector were obtained from the proto-type RD-72 sample chambers. The chambers were evacuated to less than one millimeter of mercury absolute pressure, then backfilled to atmospheric pressure with~a calibrated Xe-133 or Kr-85 gas sample. The chambers and

. detectors were installed in the prototype RD-72 lead shield when obtaining Lthe countrates. A fixture was used for locating the solid sources in a -

repeatable counting geometry.

.The cdTe(Cl) crystals are approximately 2 mm x 2 mm x 5 mm in size.

Because of manufacturing tolerances when cutting the crystals to size and

.when assembling the unit, each detector has a specific counting efficiency for: beta and gamma radiations. 'A relationship was obtained between the gaseous sources and the solid sourcas. A solid Kr-85 source was selected to relate beta response to radioactive gases. A solid Ba-133 source was selected to relate gamma response to radioactive gases. Ba-133 has the same

. .Cs X-rays as Xe-133 and an 80 kev gamma as compared to Xe-133 with an 81 kev

' gamma. The~ ratios of the solid Kr-85 beta source to the gaseous Kr-85 varied

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l by.less than 16% from the mean value for all the detectors tested. We

, ratios of the solid Ba-133 gamma source to the gaseous Xe-133 varied by +12%

from the mean value for all the detectors tested. We test results are i given-in Table 1.

TABLE 1 DETECTOR RESPONSE TO GASEOUS AND SOLID TEST SOURCES Response-to Xe-133 Gas Mid-range chamber 1295 spread from a mean of 1,42 x 10 cpm (microcuries/cm3) -1 High-range chamber 130% spread from a mean of 49.4 cpm (microcuries/cm 3 )-l Ratio of responses, mid versus high chambers 3 85% spread from a mean (,f 294  !

Response to Kr-85 Gas Mid-range chamber.

3 140% spread from a mean .of 1.51 x 10" cpm -(microcuries/cm )-1 High-range chamber 136% spread from a mean of 58.9 cpm (microcuries/cm3 )-1 Ratio of responses, mid versus high chambers

+5.7%

spread from a mean of 252 Responses to Solid Sources a

Kr-85 (source S/N KR85-109) on 9-1-82 141% spread from a mean of 35618 cpm Ba-133 (source S/N BA81-001) on 9-1-82 1265 spread from a mean of 14550 cpm

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TABLE 1 (continued)'

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. Pesponses of Solid Sources Versus Gaseous Sources

'Mid-Range Chamber Xe-133 gas versus Ba-133 solid source (BA81-001) 1 12% spread from the mean

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Kr-85 gas versus Kr-85 solid source (KR85-109) '

12.8% spread from'the mean High Range Chamber Xe-133 gas versus Ba-133 solid source (BA81-001) 112%_ spread from the mean Kr-85 gas versus Kr-85 solid source (KR85-109)

_15 9% spread from the mean

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4. DETECTOR CORRECTION-FACTORS Since there is a definite relationship between the solid Ba-133 source

'. and Xe-133 gas and between the solid Kr-85 source and Kr-85 gas, these solid sources can .be used to obtain correction factors for the individual detec-tors. After 'a-detector is aligned for gross counting with a 60 kev thresh-old, a beta and gamma correction factor can be calculated as follows:

Beta correction factor (Cg) cpm net Kr-85 source C

• Fb mean epm Kr-85 source x C T 1/2 Gamma correction factor (Cp)

C =

m ne a- 33 source Fq mean opm Ba-133 source x C T 1/2 where net opm for the Kr-85 and Ba-133 source response is obtained from the transfer calibration procedure 0360-9010 for each detector.

-Half life correction (C Tg

}

t/T 1/2 C

T

= 0.5 1/2

-where t = time in years since 9-1-82 T1/2.= 10.4 years for Ba-133

= 10.73 years for Kr-85 7

. o, The correction factors are now (cpm KR85-109) c.=

p 4 f r beta counting 3.56 x 10 x 0.5(t/10.7)

(cpm BA81-001)

, Cy -= for gamma counting 4

1.45 x 10 x 0.5(t/10.4)

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Half life corrected values for the Ba and Kr sources can be obtained from

. the graph in Fig. 2.

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5. ENERGY RESPONSE CURVE The energy response curve can be useful when calculating a counting efficiency.for an expected source term. The source term of interest'has to -

contain the. following information when calculating an expected detector response. '

1. Isotopes of interest and their intensities (the sum of the indi-vidual intensities is equal to one) 2.. Each beta and gamma with its energy in MeV and number produced per disintegration.

Beta and- gamma responses can now be obtained- from the Energy Response Curve (see Figs. 3 and 4). This response in opm/(microcuries/cm )3 (assuming one gamma or beta per disintegration) must be corrected for the intensities

' of the isotope and the number. of betas or gammas produced per disintegra-tion. - The sums of all the corrected beta responses and all the corrected

. gamma responses must be multiplied by.the individual detector's beta or gamma correction-factor. These correction factors are obtained from Section 4 of this report.- The sum of the detector's gamma and beta responses is the ,.

-detector's expected response in opm/(microcuries/cm ) for the source term of

,4 inte'est..

r ,

The reciprocal of the detector response is the detector conversion factor.(microcuries/cm 3)/ cpm. This conversion factor, when factored into -

the RM-80 data base, can provide a microcuric/cm 3equivalent for a known source term.

The shape of the energy response curves was obtained from solid beta

-and samma. sources in a ' fixture simulating the actual detector sample chamber 10

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. geometry.- The sources used are listed in Table 2. After the shapes of the curves were established, they were superimposed over the actual responses F

for Kr-85 and Xe-133 to produce the curves shown in Figs. 3 and 4. The beta

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response at 2.25 MeV is recommended as the response for higher beta end

. point energies. This is a conservative recommendation. The gamma response at 1.25?MeV (Co-60) was extrapolated out to 4.0 MeV based on the energy absorption attenuation coefficients for Cd and Te.

Sample. calculations for a source term response are shown in Table 3 n.

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i'ig. 3. Mid-range detector energy response curve 12

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TABLE 2 SOLID SOURCES USED FOR ENERGY RESPONSE CURVES '

Major- Energy Intensities t Isotope Radiations (MeV) (1)

Cd-109 gamma 0.088 5

, . Ce-139 ganna 0.165 80 t cr-51 gamma, 0 320 9 cs-137 gamma 0.662 85 ..

beta 0.514 93 beta 1.176 7 Co-60 ' gamma- 1.173 100 1 332 1.25 av 100 beta -0 314 99+

t Tc-99 beta 0.292 100 Cl-36 beta 0.714 100 Sr-90/Y-90 beta beta 0.546 2.27 100 100

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TABLE 3 EXAMPLE FOR CALCULATING DETECTOR RESPCNSE FOR AN EXPECTED HTPOTHETICAL SOURCE TERM FOR HIGH RANCE DETECTOR HIGH RANGE DETECTOR C (*(DETECTOR CORRECTION FACTORS) a s 1.12 7

. y 0.98 Sourca Term Radiations Produced com cpm

. pC1/cc , pC1/cc Espected Inten- Energy No. per from DE E or Tield i sity HeV 8 or y "is Graph l Actual A1F C p Isotope Activity (C1) lA B l C } D E F

G Ie-133 2.14 x 10 O.39 N/A 49.4 18 9 Actual response obtained from i

{ calibration repcrt Ie-135 ; 2.04 x 10 0 l0.37 0.25 y 0.91 54 49 1 17.8 j 0.61 y 0.03 22 0.7 0.2 l 0.92  ; 8 1.00 103 103 42.7 Kr-88 1.22 x 10 0

! 0.22 0.166 fy 0.07 110 7.7 1.9

l

• 0.191 ; y 0.35 90 31.5 7.8 l' 'O.36 {' y 0.05 29 1.5 0.4 O.35 y 0.23 18.5 4.2 1.0 C 1.55 2.19  :

y y

0.14 0.18 17.5 15.5 4.3 2.5 1.0 0.7 2.4 y 0.35 15 5.2 13 0.54 s 0.67 40 26.8 6.6 0.70 s 0.09 6 65 5.9 1.5 1.19 8 0.02 n72 34 0.8 1.88 8 0.02 375 7.5

• 1.8

' 0.17 440 74.8 18.4 2.90 s 6

Ze-133M 5.2 x 10 ,j,

,<0.01 Less than 15 of iource Term Total Expected Tield for Source Term cpm (uct/cc)"' 109 c

Notes

, C F

Obtained frcs transfer calibration procedure (OA document 0366-9310). used typical values or 1.12 for beta and 0.98 for s gamma.

A Calculated from source ters B,C and D Obtained from table of isotopes E Obtained from gripa in Fig. 4 of hD-72 Calibration Repeat F D times E or from Table 1 of RD-72 Calibration Report G A times F times C 7

(m 15

6. LINEARITY TEST  !

.6.1. OBJECTIVE The objective is to show response of the detection system for count rate versus activity strength.

I i

6.2. METHOD A monoenergetic radioactive nuclide, 10 mci cesium 137, was placed at a

-fixed distance from the detector. Lead attenuators of eimilar 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 ' r.e percentages of ' -

countrate changes were calculated. The tests were repeated to cover the operating range of the detection system for the decade above background (10 0

to1103 cpa) through the last decade of response (10 to 10Icpm). See Fig.

5 for test setup and Table 4 for test data.

6.3 .RESULTS -

The actual change in countrate within the operating range of the 3

Q -- ' detector from the decade above background (10 to 10 cpm) through the last ,

0 I decade (10 to 10 cpm) was found to be between 485 and 54% for one 1/4-in. ,

thick lead attenuator. The change varied 2,31 from a mean of 511. There- .

g fore, it can be concluded that the detection system is linear within 3.3% -

'when actual countrate is compared with activity strength for the operating ,

range of one decade above background to the uppermost decade.

16

LEAD ATTENUATORS CdTe (Cl) DETECTOR ASSEMBLY , - -

10 mci Cs 137 POINT SOURCE a- f -

%N DISTANCE KEPT CONSTANT FOR =

EACH SETUP EL 3739 Fig. 5. Setup for linearity test t

9 17

'd : -

TABLE 4 LINEARITY. TEST DATA ("} ,

No . o f Countrate .

atten- attenuation uators opm (%)

, Setup 1 1512613 52 1 2 784432 1 560576 --

51 4 Setup 2 285194

2~ 50

'3 143968 50 4 '71354 Mean atten-uation 1 326948 in 49 countrate 2 -159146 = (.

Setup. 3 79874 50 51% (

3- 49 4 38824 50 5 19501

- 50 6 9843 L 1 6645-50 '

2 3337

52 3 1750 .

48- '

Setup .4 844-

. 4 54 5 458 .

l 49 6 223 (a)The above data are from General Atomic Laboratory Notebook 7416, pp. 81 and 82.

18

t

.+ -

C.

7. ACCURACY 3

.'A. . ' Radioactive: Gases

.~

Xe-133 +1.9.5' _

Kr-85'220%

'[(1.9)2 + (20%)23 1/2 = 20.1%

- B. Solid Sources for Energy Response Curves = +7.3%

- C.

' Counting Error (All counts were >3000)

... V3000 3000 r100 = 2 18%-

lD. Spread, Solid Sources to Gaseous Sources Beta <5.9%

Gamma'125

[(5.9)2 + (12)231/2 = 13 4%

?

.g Overall' Accuracy 2 2 2 2 n A + . B + C. +'D =

225.3%

.c .q p

d n

'19 y + , - r--. ,,.g = -

--w.m -- ~ - - me,--n..-,.-.,n, -

- - * - we+ -*w**we*-r~-- w -w "er w w w w-~~-w-w s* V v 9 W"='--r-*~w-~-

. \ct

8. BACKGROUND The RD-72 detector assembly was scanned with a 5 mci co-60 point source producing a gamma . flux of approximately 29 mR/hr. This gamma flux produced .

approximately one count-per-minute increase over the ambient background.

- The ambient background was 3 counts in a 10-min counting period.

r.

=The above data is recorded in General Atomic notebook No. 8185 on pages

- 130. 131, and 135.

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O an APPENDI%

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. f CERTIFICATE OF

. RADIOACTIVITY CALIBRATION Isotope: 62 139 Half-Life: /37.u.,r0.0.? c/

Source No.: /A;6+ 2 Was assayed as containing: 9. o 37 G As of: # f - l 1'2.-

. METHOD OF CAllBRATION:

( /) The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a

, single-channel analyzer, using the o.<69 MeV peak (a value of c."1999 gamma rays per decay was used in the calculations), against e standard No. , in the same geometrical arrangement. +cryr41./.Nc.ny cum"

( ) The source was assayed in a windowless internal proportional counter against standard No.

( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No. in the same geome:rical arrangement.

.( )' The source was prepared from a weighed aliquot of a solution whose activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systemauc errors (SE) b) Randon errors (RE) 1.' Accuracy of the standard: 3. 0 *h 1. Precision of source count, e,-

2. 2. Precision of standard count, ej

3. Error due to background, e 3:

c) Total Error TE=SE + RE = 4 3'/- RE= + e ' + e ', + e '3 = t /. 3*/.

r.

IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the bhnci assay (and later NBS certification) of Standard Reference Matenals.

NOTES

(/) The error given is calculated at the M % confidence level.

( ) This calibration is directly/ indirectly based on NBS Standard Reference Material No.

s x -

l EU0 p .s \, gariosA.senxei

,(.

x c,

(;k,::g-

, Quality Assurance l I ISOTOPE PRODUCTS LABORATORIES l, isoo tao Keystone st cureans. cai.tcenia 9tiu4 j

L I i

i . .

CERTIFICATE OF (.- -

RADIOACTIVITY CAllBRATION .

Isotope: CtI-'M Half-Life: V/cN t I c/

Source No.: /co6+ /

Was assayed as containing: /#6 d As of: ll-'- O METHOD OF CAllBRATION: ,

( /) The source was assayed on a 3" x 3" Nat (TI) crystal in conjunction with a single-channel analyzer, using the 0.cn MeV peak (a value of v,o hJ gamma rays per decay was used in the calculations),against 8 standard No..pra , in the same geometrical arrangement.

( ) The source was assayed in a windowless internal proportional counter against standard No.

( ) . The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No. in the same geometrical arrangement.

The source was prepared from a weighed aliquot of a sclution;whuse

( )

activity in uCi/gm was determined by the method indicated above. (-

ERROR CALACULATION:

a) Systematic errors (SE) b) Randon errors (RE)

1. Accuracy of the standard: i II.S*/. 1. Precision of source count, e,:

2. 2. Precision of standard count, e,:

3. Error due to background, e 3:

c) Total Error TE=SE + RE = f 74 RE= + e I + e * + e '3 = 1 I.2. 4 IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials. .

NOTES i

!i (/) The error given is calculated at the 99 % confidence level.

(- / ) This calibration is tW/ indirectly

• based on NBS Standard Reference Material No. It00-1 N #

' I I r l t j ",)% ls 1 (4& LJ I/. W/

\. [arlos A. Henkel

., Quality Assurance a 1-l lSOTOPE PRODUCTS LADORATORIES l 1800 No Keyston<= St . Duroank. Cabforma 91504 l

9

m

• t CERT!F!CATE OF

(- RADIOACTIVITY CALIBRATION Isotope: CT S I Half-Life: 2.7.7041 ac04 cl Source No.: I0064- 3 Was assayed as containing: /2s C As of: / l :f 2 , @ Av./

METHOD OF CAllBRATION:

(/) The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the 0.b MeV peak (a value of o. cx;s 3 gamma rays per decay was used in the calculations), against ? Standard No. , in the same geometrical arrangement. - Euyy/e/sciemy cur.s

( ) The source was assayed in a windowless internal proportional counter against standard No.

( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No. in the same geometrical arrangement.

( ) The source was prepared from a weigiied aliquot of a solution wnose C activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systematic errors psE) b) Randon errors (RE)

1. Accuracy of the standard: 3. 0 Y. 1. Precision of source count e..

2. 2. Precision of standard count. e,:

3. Error due to background. e,:

c) Total Error TE=SE + RE = 4. '4 '/* RE= + e ' + e ', + e '3 = 1. 4 */.

r IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a numcer of nuclides. based on the blind assay (and later NBS

, certification) of Standard Reference Materials.

. NOTES

(/) The error giv'en is calculated at the 9.9  % confidence level.

(/ ) This calibration isr%+// indirectly based on NBS Standard Reference Material No. 294-I.f 4 d I 'ULIGl garios A. Henkel O'

( ,

lke\[ 2 ISOTOPE PRODUCTS LABORATORIES Quality Assurance 1800 No Keystone St . Buca% C.skfornia 9f 604 f

mm .

U.S. DEPARTMEtlT OF COMMERCE NATIONA1. BUREAU OF STANDARDS WASHINGTON, D.C. 30334 ,

REPORT OF TEST for General Atomics San Diego, California -

Radionuclide Xenon-133 Source description Gas in a lecture Bottle -

provided by General Atomics Gas composition Xenon-133 and nitrogen Activity 1.29 x 109 Bq mol-1 s-Imol-1) 5.28 x 104 Bq ,(cm3)-1(at STP (0*C, Reference time 1200 EST August 16, 1982 Random uncertainty 0.13 percent (1)

Systematic- un:ertainty 1.75 percent (2)

Total uncertainty 1.88 percent (Rand:m plus systematic)

Photon-emitting impurities 131mXe/133 X e: 0.021 t 0.001 (3)

(Activity ratios at reference time)

Half life 5.245 i 0.006 days (4)

Measuring instrument NBS pressurized "4w"Y ionization chamber A calibrated by internal ,

gas-proportional counting For the Director, ,

', N L ,1 /. !il }!"' ,"

Washington, D.C. 20234 Dale D. Hoppes, Group Leader August 20, 1982 Radioactivity Group P.O. #806253 Center for Radiation Research

• flotes on following page 9 S

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FOOTNOTES (1) Half the 99-percent confidence interval of the mean (2.640 times the standard error computed f rom 89 ionization-chamber measurements).

(2) Linear sum of estimated uncertainty limits due to:

- a) calibration of pressurized "4n"Y ionization chamber A, which is the linear sum of the estimated uncertainty limits due to:

1) half the 99-percent confidence interval of the weighted mean of three series of gas-counting measurements 0.66 percent

2) extrapolation of the gas-counting data 0.22 percent

3) half the 99-percent confidence interval of the mean of three series of ionization-chamber measurements 0.01. pe rce nt

4) radium-226 reference sources ratios ~0.36 percent b) gram mole measurement 0.50 percent (3) Limits of detection as a percentage of the gamma-ray-emission rate of the 81-kev gamma rays emitted in the de:ay of xenon-133 are 0.1 percent between 37 kev and 76 kev 0.01 percent between 86 kev and 1900 kev, provided that impurity photons are separated in energy by 5 kev or more from photons emitted in the decay of xenon-133.

(4) NCRP Report No. 58, 1978, p. 387.

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i GENERAL ATotAfC CoMPAN~/ ,

P.O. Box 8-6C8 .

SAN c: ego. CAUFCAMA 92138 (714) 455 3000 CERTIFICATION OF RADIOACTIVITY STANDARD Radionuclide Kr-8S

-Nominal A:tivity 10pCi/cc Method of Measurement

[X] 1. Calibration derived frca Sigma 2 Ccmputer Ga=ma Ray Spectro =eter calibrated with NBS Standards.

[] 2. Calibration derived f rom Ioni=ation Chamber Calibrated to Sigma 2 Computer Cacma Ray Spectrometer.

[] 3. Calibration derived from 2n internal gas proportici.al counter calibrated to Sigma 2 Cc=puter Gamma Ray Spectrc=eter.

=r3 )

%/ / Accuraev Overall I.init of Error fic

• Systematic)

-+ 20".

Remarks , ,

Recalibration of IPL Standard S/N 65010A.

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We certify that the activity (ies) uns(vere) as follows: .

11.1 pCf /cc on 6/25/80 at 1200.

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%3_~ u(._1.sc- - #  %...

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(L CERT!F!CATE OF RADIOACTIVITY CAi_!BRATION 9

Isotope: Sr. c)o Half-Life: 29.<2ro.y y Source No./;0d4 8 Was assayed as containing: 10.2.pd:

As of: Il-J '

.- METHOD OF Call 8 RATION:

( ) The source was assayed on a 3" x 3" Nat (TI) crystal in conjunction with a single-channel analyzer, using the MeV peak (a value of gamma rays per decay was used in the calculations), against standard No. ,in the same geometrical arrangement.

(v) The source was assayed in a windowless internal proportional counter against standard No. ins-l G.%)

( ) The source was assayed by alpha spectrometry on a surface barrier

, detector in conjunction with a single-channel analyzer, against standard No. in the same geometrical arrangement.

( (/} The source was prepared from a we;ghed aliquut of a sciutron wnose activity in uCi/gm was determined by the method indicated above.

. ERROR CALACULATION:

a) Systematic errors (SE) b) Randon errors (RE)

1. Accuracy of the standard: t 2.0'/. 1. Precision of source count, e,:

2. W $ld.y vo.- 164 2. Precision of standard count. e,:

3. Error due to background, e,:

c) Total Error TE=SE + RE = 2 S.2 4., RE= + e ' + e,' + e *3 = t /.64 IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NSS certification) of Standard Reference Materials.

NOTES

(. J ) The error given is calculated at the 99  % confidence level.

( .f ) This calibration is d4_ q 4ndirectly based on NBS Standard Reference Material No. 499 b a

1. 6  ; &cL,t/

74 d 'GIirios A. Henkel C/uality Assurance i ISOTOPE PRODUCTS LADORATORIES e 1800 No Keystanc St . Ourcana. CaYetnia 91504 4

y CERTIFICATE OF

(:

RADIOACTIVITY CALIBRATION .

Isotope: C'I % Half-Life: (3.co t o.ct) ao'y Source No.#db4 9

, Was assayed as containing: /0 4pc As of: 12 -1 f:-

METHOD OF CAllBRATION: ,

( ) The source was assayed on a 3" x 3" Nal (TI) crystal in cor junction with a single-channel analyzer, using the MeV peak (a value of gamma rays per decay was used in the calculations), against standard No. ,in the same geometrical arrangement.

(/) The source was assayed in a windowless internal proportional counter against standard No.UT037 (Cl 3')

( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunc. tion with a single-channel artalyzer, against standard No. In the same geometrical arrangement.

(j} The cource was prepared from a weighed alic;uot of a solution wi.o e activity in uCi/gm was determined by the method indicated above.

((

ERROR CALACULATION:

a) Systematic errors (SE) b) Randon errors (RE)

1. Accuracy of the standard: 2. 5'l 1. Precision of source count, e,:

2. W20$ 44,y mvr 07*4 2. Precision of standard count, e,:

3. Error due to background, e3:

c) Total Error TE=SE + RE = i 5. o'/. RE= + c i + e ', + e *3 = 1 I. 8'/.

IPL participates in a NBS measurement assurance program to establish and ~.aintain -

implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials. ,

NOTES

(/) The error given is calculated at the 99 % confidence level.

(/ ) This calibration is p-edy/ indirectly based on NBS Standard Reference

. Material No. 4crei f*?'*}, ./ l $ j l I#- .Y. Garlos A. Henkel Guality Assurance i

te\[. m ISOTOPE PRODUCTS LABORATORIES 1800 No Keystone st.. Buscana. Cahfornea 91504 E

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CERTIFICATE OF RADIOACTIVITY CALIBRATION Isotope: Tc.w Half-Life:(2.8Wo.05)ti/j Source No.M:64-h

- Was assayed as containing: /0. C As of: 81 9 '-

• • METHOD OF CAllBRATION:

( ) The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the MeV peak (a value of gamma rays per decay was used in the calculations),against standard No. , in the same geometrical arrangement.

(/) The source was assayed in a windowless internal proportional counter against standard No. n)s92-1 (Tc-93)

( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No. in the same geometrical arrangement.

(/) The source was prepared from a weighed aliquot of a solution whose activity in UCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systemauc errors (Sii) b) Randon errors (RE)

1. Accuracy of the standard: 1 J,1 */, 1. Precision of source count, e,:

2. D44c;4,ej ew 0.,7f 2. Precision of standard count, e,:

3. Error due to background, e,:

c) Total Error TE=SE + RE = 1 7. 3'/, RE= + e l + e l + e $ = 1 3. W, e

IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES 1

(') The error given is calculated at the 9') % confidence level

(/ ) This calibration is direc47/ indirectly based on NBS Standard Reference i Material No. ems . 2ce, B ,

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b XNLL) c Obarlos A. Henr.el ality Assurance

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ISOTOPE PRODUCTS LABORATORIES 1800 No Keystone St eutt,ank. Canternia J1504 i

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CERT!FICATE OF ('

RADIOACT]VITY CALIBRATION -

Isotope: Co.60 Half-Life: -

6.J-7sio.vo/ 7 Source No.: / ooc */ S Was assayed as containing: i t. 6 ,.

As of: Il- Lil.-

METHOD OF CAllBRATION:

( /) The source was assayed on a 3 x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the {jQ MeV peak (a value of gT]f gamma rays per decay was used in the calculations), against Ch* stanoard No. iagu t. , in the same geometrical arrangement.

( ) The source was assayed in a windowless internal proportional counter against standard No.

( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single channel analyzer, against standard No. In the same geometrical arrangement.

[

( ) The souice was prepered from a weighed aliquot of a solution whose \_

activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systematic errors (SE) b) Randon errors (RE)

1. Accuracy of the standard: 1 N. 1. Precision of source count, e,:

J. 2. Precision of standard count, e,:

3. Error due to background,0 3:

c) Total Error TE=SE + RE = 2 4.06 RE = +o#+ e ', + o '3 = 1 /. 3 %

IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides. based on the blind assay (andlater NBS ,

certification) of Stanoard Reference Materials.

NOTES

(/) The error given is calculated at the 99 % confidence level.

( /) This calibration is w// indirectly based on NBS Standard Reference

. Material No. 49'fC S l [p,,,---ras s

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1 1 W \ 'arlos A. Henkel

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uality Assurance ISOTOPE PRODUCTS LADORATORIES

.. l isoo rm kuvuono st eurcan=. curetnia 9604 1

( CERTIFICATE OF RADIOACTIVITY CALIBRATION Isotope: C5.837 Half-Life: 30.030,2 Source No.: loc 64 4 Was assayed as containing: /O # Cc As of: It-t -st-

.. METHOD OF CAllBRATION:

(/) The source was assayed on a 3" x 3" Na! (TI) crystal in conjunction with a single-channel analyzer, using the o.l=> MeV peak (a value of 0. ew gamma rays per decay was used in the calculations), against 4 9 standard No. se}oi4 ,in the same geometrical arrangement.

( ) The source was assayed in a windowless internal proportional counter against standard No.

( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No. in the same geornetncal arrangement.

( ( ) Tite source was preparco from a weigneo aliquot of a solution whose activity in uCi/gm was determined by the method incicated above.

ERROR CALACULATION:

a) Systematic errors (:sE) b) Randon errors (RE)

1. Accuracy of the standard: 3. 3#/* 1. Precision of source count, e,:

2. 2. Precision of standard count, e,:

3. Error due to background, e,:

c) Total Error TE=SE + RE = 1 'f SS RE= + e ' + e ' + e '3 = t /. :t */.

IPL participates in a NBS measurement assurance program to establish and maintain Implicit traceability for a number of nuclides, based on the blind assay (and later NBS r certification) of Standard Reference Materials.

• NOTES

( ,/' ) The error given is calculated at the 99 % confidence level.

( /) This calibration is s'.==:;9pindirectly based on NBS Standard Reference Material No. soOf i 84bfb'

.d - * ** \ Qstlos A. Henkel N Quality Assurance

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P.O. Box S1608 San.Diegos California 9213E

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