ML20211G411
| ML20211G411 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/03/1985 |
| From: | Goetchius E, Danni Smith CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | |
| Shared Package | |
| ML20211G399 | List: |
| References | |
| NUDOCS 8702250378 | |
| Download: ML20211G411 (25) | |
Text
, _ _ _ _ _ _ .
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.* .* Indian Point Station Effnetivo Mnxicun Botn Ennrgy and the Determination of RO-2, 2A Response Factors l
l Written By: D. Smith Radiological Engineer 4/19/85 Checked By: Ed Goetchius Associate Engineer 7/3/85 G702250370 PDR 999939 ADOCK 05000247 PDR
e f
. D - Cantonts Page f Effective Maximum Beta Energy De t e rmina tio n Theory and Empirical Treatments 1 Test Using Reference Sources 1 Smear Counting 3 Transmission Curves and Absorption Coefficients 3 Estimated Effective Maximum Beta Energy, 4 Average Beta Energy Camma Spectrometric Analysis of Smears 5 Lens of Eye Dose 6 RO-2, RO-2A Response Factor Calculated and Measured Dose Rates 6 Spectra Approximations 7 Recommendation of Appropriate Response Factor- 7 Plant Usage References 8 Appendix:
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' O [EffectivoMexinunBataEnergyDatorninntion Pago 1 Theory and Empirical Treatments To a first approximation, the absorption of beta particles passing through an absorbing medium is ex po n en ti al in nature. This is represented mathematically by:
p' hi
(=
where [ = beta flux density at absorber thickness x f = uncollided flux density ( flux in the absence of absorbers) hk)= apparent mass absorption coefficient When the thickness, x, is given in g/cm2, the absorption coefficient is given in cm 2/g. If x is the thickness which reduces the flux to one half of its original value, then the absorption coefficient is given as:
a a -
)ht 2
/ $
Since the count rate of a beta-sensitive instrument is very nearly proportional to the flux, the count rate as a function of absorber thickness will be exponential in nature also. A semi-log plot of ceunt rate vs. thicknesses will yield a straight line over a range of absorber thickness. Mass absorption coefficients have been dete rmined by T. Baltakmens (Ba77) for a number of beta emitters.
A fit of the data obtained has shown that a simple power function may be used to determine effcetive maximum beta energy from the apparent absorption coefficient:
Eg , 6 47 ((
where E max is the maximum (endpoint) beta energy in MeV. From this
- empirical treatment and an estimate of the absorption coefficient, the mat inum beta energy in a s ample may be dete rmined.
Test Using Reference Sources
! Co-60 and Sr-90, Y-90 sources were used to test the ability of the method to predict maximum beta energy. Paper absorbers, 5.7 ag/cm2 thick, were used to partially absorb beta emissions from the two thin sources. The sources were counted with an RP-210 probe and scaler for two minutes. Counting data may be found in the Appendix. A background correction was taken. A dead-time correction was taken i
according to the following:
I J %
Cc Cf ( l -K,
)
i,su. C, a n ~ w acC d e*" &
C* cswedcw d R = Zsn f C M A+b
- y - & Jead km) y H F-zlo uad e k W 4sec.
i e- - - - - - - - - ...,-.%. - - - - - - - - - . --,-m--_ . . . - - - . . . - - . , . . - - - - - - - . - . - - - . - . . , . , . . . . - ~ . . . - - - - - - , -
t' Conotont courco to datoctor distance eco maintained throughout.
For the Co-60 ocurce, the count rato under 30 oboorbero eco "cosumed dua to photono only; this count rate offect eso used to correct the counts. For Sr-90,Y-90, the instrument background was used to correct the dead-time corrected gross counts. Also, an initial loading of 30 absorbers on this source was assumed to suppress all the contributions to the gross count from Sr-90.
The re fo re , the response is due to Y-90 betsa only. Transmission curves were generated for both sources. From the curves, the j response was seen to be exponential in nature (linear on a semi-log plot) for each source. The apparent thickness needed to halve the response was determined graphically. This half-valve thickness was used to calculate absorption coefficients for Y-90 and Co-6 0:
For Co-60, half-value thickness = 8.4 ag/cm2 u in 2 _
= 82.5 cm 2fg ,
p = 8.4 mg/ca' For Y-90, half value thickness = 123 ag/cm2 (first measure)
= 130 mg/cm2 (second measure) i l 127 ag/cm2 (average) f
~
u = In 2 = 5.46 cm 2fg p 127 ag/ca' t
The maximum beta energy for Co-60 is calculated:
l -0.661 i E max = 6.47 (82.5) = 0.350 MeV = 350 kev (RHH value is 314 kev)
The maximum beta energy for Y-90 calculated:
l
-0.661 E max = 6.47 (5.46) = 2.11 MeV (RHH value is 2.27 MeV)
The percent differences from the reference (RHH) values are:
+ 11.5% for Co-60 7.6% for Y-90 This is considered good agreement. It is concluded that the power f unction method for dete rmining maximum beta energies , as given by Baltaksens, is appropriate.
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- Snonr Counting I Radiation Protection Section obtained smears from the following i locations: '
Unit 1 Unit 2
- 11 WCT Cell #21 Charging Pump Cell
- 22 RHR Cell (2)
Non-Regen He at Exchanger (1)
Non-Regen Heat Exchanger (2)
Counts of the smears under varying numbers of paper absorbers were obtained. Several thousand counts were obtained in most cases in order to obtain decent counting statistics. This is not critical since the graphical method of dete rmining the half-value thick-nesses will smooth any uncertainties in counting as long as a reasonable number of measurements is taken. The data may be found in the Appendix along with the transmission curves.
Transmission Curves and Absorption Coefficients The transmission curves in all instances show that linear behavior on a semi-log plot is evident. At very low transmissions ( <10%), a small amount of beta range straggling was observed. All half-value thicknesses were obtained from the first observed linear portions of the transmission curves. The results are as follows:
Location ( Sme a r) Half-value thickness , Absorption coefficient
- 11 WCT 16.5 mg/cm2 42.0 cm2 fg
- 12 WCT (1) 2 2.5 mg/cm2 30.8 cm 2/g
- 12 WCT (2) 16.5 mg/cm2 42.0 cm 2fg
- 13 WCT 21.5'ag/cm2 32.2 cm 2 /g
- 21 Charging Pump 3 7.0 mg/cm2 18.7 cm 2 /g 51' el. Pipe Pen (1) 2 6.6 ag/cm2 26.1 cm 2fg 51' el. Pipe Pe n (2) 2 7.0 mg/cm2 25.7 cm2/g
- 22 RER (1) 17.7 ag/cm2 39.2 cm 2/g
- 22 RHR (2) 18.2 mg/cm2 38.1 cm 2/g Non-Regan EX (1) 23.7 ag/cm2 29.2 cm 2fg l Non-Regen EX (2) 21.6 mg/cm2 32.1 cm2/g ave. 22.6 ag/cm2 ave. = 32.4 cm 2 /g
v ,
.Entinntad Effnetive Mnxinun Botn Enargy, Avornge Botn Energy The calculated ef fective maximum and average beta energies are as follows:
Location (Smear) effective maximus beta energy, MeV average (MeV)*
- 11 WCT 0.547 0.179
- 12 WCT (1) 0.671 0.226
- 12 WCT (2) 0.547 0.179
- 13 WCT 0.651 0.218 d21 Charging Pump 0.934 O.327 51' el. Pipe Pen (1) 0.750 0.255 51' el. Pipe Pen (2) 0.757 0.258 22 RHR (1) 0.572 0.188 22 RHR (2) 0.583 0.193 Non-Regen EX (1) 0.695 0.234 Non-Regen HX (2) 0.653 0.219 ave.= 0.669 MeV ave.=0.225 MeV u- 0.745
- From Baltaksens: E ave. = 2.90 p The values of energies for smears taken at the same location show good agreement. The energies fall in the range of 500 to 800 Kev; the arithme tic ave rage of 669 kev is taken to be representative of our maximum beta energies.
Note that the results of a similar study at Surry and North Anna by VEPCO show that the beta endpoint energy at those plants is approximately 630 kev.
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- *Gennn Spoetronotric Annlynio of Snacro Gamma spectrometric analysis of smears indicated the following:
Location (Smear) % Composition /Nuclide Reference E.,x, y,y fil WCT 66.8% Co-60 33.2% Cs-137 Co-58 0.474 (B+)
- 21 Charging Pump 28.4% Co-60 27.1% Cs-134 44.5% Cs-137 51' el. Pipe Pen (1) 35.7% Co-60 26.0% Cs-134 ,
38.3% Cs-137 51' el. Pipe Pen (2) 14.8% Co-60 ^-
31.9% Cs-134 53.3% Cs-137 22 RHR (1) 2.0% Co-58 ;
78.5% Co-60 4.1% Cs-134 22 RHR (2) 5.1% co-58 73.6% Co-60 5.9% Cs-134 .
15.4% Cs-137
- t y
Locntion (Snonr) % Componition/Nuclida
~
Non-Regen EX (1) 61.1% Co-60 38.9% Cs-137 Non-Regen HI (2) 54.8% Co-60 10.2% Co-134 35.0% Cs-137 The percent c om po sition s are obtained from positively indicating nuclides.
The analysis shows that the nuclides of concera are isotopes of cobalt and cesium.
Lens of the Eye Dose The effective maximum beta energy has been calculated to be 6 69 ke V.
A minimum of 800 kev is needed for the beta to penetrate to the lens of the eyeA which is taken to be at a depth of 300mg/cm2, per NRC Form #5. 700 kev beta can penetrate only 240mg/cm ; therefore, the beta fields at Indian Point do not deliver dose to the lens of the eye. The lens of the eye dose is due to gamma radiation.
Smear data for normally inaccessible areas, such as the steam generator channelheads, is not av ail able at this time. Smears will be collected and analyzed at the next opportunity.
RO-2, R0-2A, Response Factor Calculated and Measured Dose Rates E. Darois of Yanke e Atomic has done extensive wo rk using several plaque and several point beta sources to try to correlate R0-2 r e s po ns e to dose rates aescored with extrapolation chambers (Da unpublished). He has pointed out common errors made using uranium i slab and other sources fo r calibrating 10-2 ins truments to beta-only radiation. These are summarised as follows:
i Contact dose rates are made with the instrument resting on the uranium slab. These dose rates are correlated to extrapolation chamber readings using a surface measurement. The 10-2 type
! instrument's sensitive volume center is not at the surface of the instrument case. As a result, the extrapolation chamber readings are more closely a " contact" dose rate whereas the
" contact" RO-2 measurements are several centimeters from the placque (slab) surf ace. Thus the ratio of instrument response to measured outrapolation chamber dose rate is smaller at closer distances than at further distances. Also, since the general rule of detector versus irradiation distance is more severely violated at closer distances , a complicating solid angle geometry iffect is seen. E. Darios has made careful measurements using the sensitive chamber volume centerline as e
wmmm mw, - w w m ~ - o w o-~-m , ._mwme-,p--.
, Pago 7
,- .' Cniculatnd and Maccured Done Rnteo (Continued) '
the reference distance. Fo r placque sources, he has noted linear behavior (constant ratio) dose rates for a wide range of beta
, energies. The apparent ratio between measured and extrapolation chamber dose rates is a factor of 0.6. To correct for this under-i response by the 10-2, the open window minus closed window reading should be multiplied by the reciprocal of 0.6, i.e. 1.7. ;
Sometimes the calibration of instruments is made with point sources. At suf ficien tly large distance s , the point source may be appropriate since geometry effects would be more easily compensated for. Also, field meas urements resemble
- point sources less than they do distributed sources which are better simicked by placque or slab sources. The linearity over a wide range of beta average energies suggests that plaque or slab thickness is not a critical factor.
l The Eberline Product and Se rvice s Ca talogue (1979) shows a plot of R0-2, RO-2A res ponse relative to the tissue dose rate at chamber
, center. The first part of the curve suggests strong solid angle detector effects which are not easily compensated for on the basis of distance only. The finite size of the detection volume relative to the irradiation distance is easily inferred. At distances greater than 10 cm , the response falls off nearly linearly. From 20 cm to 30 cm, the relative res ponse drops by 20%.
1 l Spectra Approximations i
From Rich (Ri 82, page 20), it is seen that at 10 cm from a T1-2 04 source, the e nd poin t energy has dropped from the theoretical value of 766 kev to 725 kev. At 20 cm the endpoint energy has effectively become 622 kev. An interpolated value of 16.5 cm of air (separation) can be inferred to yield an endpoint energy of 669 kev. At 16.5 cm, the ratio of instrument re s pon se to dose rate is also 0.6, using the Eberline-supplied curve fo r T1-204. Therefore, the multiplying response factor is, again, 1.7, i.e. the reciprocal of 0.6.
1 Recommendations of Appropriate Response Factor - Plant Usage For ease of use, and for a small degree of conservation (15%), it is r e c om me nd ed that a factor of 2 be used to multiply the difference in R0-2 and R0-2A open-and closed-window readings to estimate beta dose rates. Additionally, no compensation for measuring distance is warranted.
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, v . Pcgo 8 References Ba77 Baltaksens, T., " Accuracy of Absorption Methods in the Identification of Beta Emitters", Nuclear Instruments and Methods, 1977, Vol. 142, pp. 535-538 RHH Radiological Health Handbook (1970) U.S. Department of He al t h , Education and Welfare Da Darois, E. (unpublished) "The Use of Large Energy Spatial Equilibium Beta Placques as Calibration Sources for Personnel Dosimetry and Survey Meters" Ri82 Rich, B.L., " Applied Beta Dosimetry", presented at the Health Physics Society Meeting, June 1982, EGG-SD-5916 An84 Anderson, D. W. " Absorption of Ionizing Radiation" (1984)
University Park Press, Appendix 9: Mass Stopping Powers (for wa ter)
g Y L Sm cf E,4ual A-4b nOr<s "
d %et u.2a 144/LL 00 '
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