ML20113G421

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Ar-41 Production Calculations for Annual Rept & 10CFR20 Requirements
ML20113G421
Person / Time
Site: University of Maryland
Issue date: 10/30/1993
From: Floyd J
MARYLAND, UNIV. OF, COLLEGE PARK, MD
To:
Shared Package
ML20113G413 List:
References
NUDOCS 9609270208
Download: ML20113G421 (26)


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' MARYLAND UNIVERdlTY TRAINING REACTOR Sheet No 1 of ,_22_

Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 -

Calc file No: Reviewed by: W. J. Chacoas Date: i

Title:

Ar-41 Production Calculations for' Annual Recort and 10CFR20 Reauirements i

1.0 INTRODUCTION

This calculation file documents work done to determine the release of

  • Ar by the Maryland University Training Reactor (MUTR). Docket # 50-166, during the operational
period beginning July 1, 1992, and ending' June 30, 1993. Assumptions made for this  !

calculation are documented herein. These calculations were performed for inclusion in the Annual Operating Report.  ;

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9609270200 960901

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PDR ADOCK 05000166 R PDR

MARYLAND UNIVEhdlTY TRAINING REACTOh Sheet No 2 of ??

Project: Task: Prepared by: J. E. Fl oyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Reouirements .

l 2.0 10CFR20 REQUIREMENTS 10CFR20 [20.1001 - 20.2402] Appendix B. Table 2 documents the maximum permissible l effluent concentrations of radionuclides. Ar has a maximum effluent concentration of 1x10 Ci/mi in air. The calculations contained in this document will show that I in the worst case scenario, the '8Ar released by MUTR is well below the requirement __ l stated above. >

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MARYLAND UNIVERolTY TRAINING REACTOR Sheet No 3 of 22 Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Cale File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Recort and 10CFR20 Recuirements 3.0 SOURCES OF "Ar i

There are five possible sources of "Ar at the MUTR. The sources and there contribution to "Ar production and release are as follows:

i. Pneumatic Transfer System: This system has an air hose which extends down into the fueled region of the core. However, the system is pressurized with CO, during operation and its overall volume is small. Thus when the system is idle the amount of "Ar produced is limited to the amount of "Ar that manages  !

to diffuse into the system when it is not in use. Furthermore any "Ar that '

is created by activation of "Ar must diffuse through over 50 feet of hose before it can enter the reactor building. The time required for such diffusion combined with the negligible amounts of production means that the Pneumatic Transfer System does not contribute to "Ar production and release.

2. Pool Tank: A small amount of air is dissolved in the pool tank. The "Ar contained in this air can be activated and diffuse bank into the reactor building at the pool surface. This amount is not insignificant.
3. Thermal Column: "Ar contained in the small amounts of air trapped in the Thermal Column can be activated. However, this air is assumed not to diffuse j out into the reactor building. The Thermal Column is not a source of "Ar. j
4. Beam Tubes: When plugged there is no mechanism via which "Ar produced inside the Beam Tubes can leave the pool tank region. However, if the plugs are removed during operation "Ar will diffuse through the tube and reach the reactor building. The Beam Tubes are only source of "Ar if the are unplugged during operation.
5. Through Tube: As for the Beam Tubes it is not a source of "Ar when the tube '

is plugged. When unplugged, however, it is a source.

For the operational period covered by the annual report, only items 2 and 5 must be '

accounted for, see sections 4 and 5. Items 1 and 3 are not a source, and the Beam Tubes were never unplugged during operation.

MARYLAND UNIVERd1TY TRAINING REACTOR Sheet No 4 of 22 Project: Task: __ Prepared by: J . E . Floyd Date: 10/30/93 Calc file No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Recort and 10CFR20 Recuirements 4.0 P0OL TANK car PRODUCTION AND RELEASE The SER. page 11-2. states that the "Ar release into the reactor building during an operational. year of 30 MWh is less than 0.1 Ci. During the time period coverea by the annual report the reactor was operated for 31.5 MWh. Thus "Ar release from the pool tank is 0.1 Ci . It was also determined in the SER that such a release amounts

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to less than 1 mrem of dose to the general public. If the MUTR were operated for 400

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MWh the dose to the general public would still be less than 1 mrem.

A 0.1 Ci release over a continuous run of 31.5 MWh would correspond to an ,

equilibrium value of approximately 1 mci of "Ar in the reactor building or a concentration-of 6x107 pCi/ml. When exhausted by the exhaust fans through the upper portion of the reactor building, the "Ar levels will be well below 10CFR20 requirements by the time the "Ar diffuses down to unrestricted areas, i

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l 1VIARYLAND UNIVERdlTY TRAINING REACTOh i

Sheet No 5 of 22 l

Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 i Calc File No: Reviewed by: W. J. Chacoas Date:

l Ti tle: Ar 41 Production Calculations for Annual Reoort and 10CFR20 Recuirements 5.0 THROUGH TUBE *Ar PRODUCTION AND RELEASE

' Ar in the Through Tube is pro'duced by activation of d'Ar by the Through Tube flux.

The flux in the through tube can be considered a cosine shaped flux whose amplitude is equal to the peak flux seen in the Through Tube. Once produced the '!Ar will.only be released in to the reactor building if it diffuses through the tube to the open ,_

end before it decays.

The flux in the Through Tube at any one cross sectional location can be considered constant, the air in the tube is a vacuum to the neutron flux. Thus the production and diffusion in the tube can be handled with a 10 approximation. The 1D values at any point in the tube when multiplied by the cross sectional area will then yield the total value for that portion of the tube. The equation governing '1Ar concentration.in one dimension is:

dN41(x, t) d2N41(x,t)

_ ggo (x, t) + D -

Ndt) dt dx i

Transforming the equation into a form suitable for a finite difference analysis yields:

N 4s(xi, t + 1)- N41(xi, t) , ggo (xxq + D 41(43,0 - 2N 41(xi,0 + N(41,0 - 141N41(xi, t)

At (2a 1 Ax2 Rearranging terms gives:

t N4 t (xi,t + 1) = AtIs0$mucod + 2 [N41(xgt ,1) + N 4t (xp3,1)] + N4s (xi,t) 1 - At 41 + 2 By segmenting the Through tube into a equal number of nodes the d'Ar released into the building can be calculated. There are three conditions required for this problem, an initial and two boundary conditions. The initial condition is that Nei( x . 0 )-0. The first boundary condition is that N,3(xa .t)-0. where xo is an i extrapolated boundary at the open end of the tube. The second boundary condition is dN,3(x,,,t)/dt-0. where x, is the final . node position at the closed end nf the tube.

i It was also assumed that any 42Ar that makes it to the open end of the tube is I

instantaneously diffused through out the reactor building free air volume. A FORTRAN program called AR41 CAL was written to do this calculation. The program listing can be found in Appendix A of this document.

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i MARYLAND UNIVERu17Y TRAINING REACTOR Sheet No 6 of 22 Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Cale File No: Reviewed by: W. J. ChaDDas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Recuirements Three cases were run using this code. The first case represents a typical reactor run of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at full power. The second case represents a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> run at full power to represent an equilibrium activation of "Ar in the through tube. The third case l is a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> run at full power. This run condition can not be reached at the MUTR do to the buildup of Xenon. Each case was run for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> beyond the reactor run.

This was done to account for the Through Tube plug not being replaced immediately at the e'dd of a run. The value of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> allows for 5 "Ar half-lives to pass;

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therefore, any "Ar remaining in the Through Tube af ter 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> will be insignificant compared to the original levels and will not affect the end results.

The case outputs are given in Appendix B. The following table shows the results of these three cases.

J Case Production Release Maximum Level (mci) (mci) (mci /ml)

I hour 2.408 3.014 3.07x104'

{0 hours 24.08 0.164 8.33x104' 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 240.8 1.705 8.70x1048 1 l

From these cases it can be seen that less than 0.02 mci of "Ar are released into the reactor building for every hour of full power run with the Through Tube unplugged. Furthermore, the concentration levels inside the reactor building are well below 10CFR20 requirements.

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,M RYLAND UNIVERolTY TRAINING REACTOk Sheet No 7 of 22 Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date.

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Recuirements  ;

6.0 CONCLUSION

S I During the worst case scenario, operating the reactor for over 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> at full l power with the Through Tube unplugged, the "Ar exhausted from the reactor building will be below 10CFR20 requirements in unrestricted areas. Even if the run time approached 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of continuous operation, the "Ar levels will still be below 10CFR20 requirements in unrestricted areas:~ Since it is unlikely that the reactor j will ever be operated for a continuous period of time longer than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. it can be said that "Ar releases from the MUTR will never be greater than 10CFR20 requirements in unrestricted areas. ,

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" MARYLAND UNIVEhdlTY TRAINING REACTOL Sheet No 8 of 22 P ro'j ect : Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc file No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Reauirements APPENDIX A AR41 CAL FORTRAN LISTING PROGRAM AR41 CAL C***********************************************************************

C PROGRAM AR41 CAL ( Argon 41 Calculation)

C C PURPOSE This program calculates the Argon 41 production in the C MUTR reactor building with one through tube plug open. l C The net results are given in mCiimi in the building. _ _ _

C The leve's are given in 1/2 hour time steps from the C begining Jf the run. Also the max level is given. The I C program ca;ulates the level using a ID diffusion calc  !

C assuming a t, sine flux distibution across the active I C length of the through tube.

C C AUTHOR Jason E. Floyd C***********************************************************************

COMMON /CASEINF/ POWER,RTIME.DELT,0ELX,0UTINT.MAXTIME COMMON /TUBEDIM/TUBEBEG.TUBEEND.COREBEG COREEND.MAXP05,CORELEN.EXB COMMON /ARCAL/NAR41,MAXFLUX.SIGMAAR. LAMBDA.DIFF.Pl, PROD DOUBLE PRECISION MAXFLUX.SIGMAAR LAMBDA, POWER PROD. RELEASE,

/ DELX,DELT DIFF, RADIUS,v0LUME.BLEVEL.CI,MAXLEVEL,ACTVTY,

/ NAR41(402.2),CORELEN EXB.PI INTEGER TUBEBEG.TUBEEND.COREBEG.COREEND,MAXPOS,RTIME MAXTIME.

/ OUTTIME,0VTINT. TIME.NTSTEP .

C***********************************************************************

C VARIABLE LIST FOR AR41 CAL C \

C ACTVTY: ACTIVITY LEVEL IN mci /mi C BLEVEL: BUILDING AR 41 LEVELS IN ATOMS /ml I C CI: 1 CURIE C COREBEG: NODE LOCATION OF BEGINNING OF ACTIVE TUBE LENGTH C COREEND: NODE LOCATION OF END OF ACTIVE TUBE LENGTH C CORELEN: ACTIVE CORE LENGHT C DELX: NODE SPACING FOR ID CALCULATION C DELT: TIME STEP C DIFF: AR-41 DIFFU$ ION COEFFICIENT C EXB: EXTRAPOLATED CORE BOUNDARY C LAMBDA: ARGON 41 DECAY CONSTANT C MAXFLUX: PEAK THROUGH TUBE FLUX (n/cm^2 kW)

C MAXLEVEL: MAXIMUM AR 41 LEVELS IN BUILDING C MAXPOS: MAXIMUM NODE POSITION C MAXTIME: TIME TO END CALCULATION AT C NAR41(X,T): ARGON 41 NUMBER DENSITY AT TUBE CENTERLINE FOR NODE X C T - 1/2 CURRENT TIME STEP /NEXT TIME STEP C NTSTEP: NUMBER OF TIME STEPS IN CASE C OUTINT: TIME INTERVAL BETWEEN LEVEL OUTPUTS C OUTTIME: TIME OF NEXT OUTPUT C POSIT: CURRENT NODE '

C POWER: CORE POWER LEVEL DURING RUN C RADIUS: THROUGH TUBE RADIUS C RTIME: RUN TIME C SIGMAAR: MACROSCOPIC ABSORPTION CX FOR AR40 C TIME: CURRENT TIME C TUBEBEG: NODE POSITION OF OPEN TUBE END C TUBEEND: NODE POSITION OF CLOSED TUBE END C VOLUME: FREE AIR VOLUME OF BUILDING C***********************************************************************

C LOAD CONSTANTS AND INITIALI2E ARRAY C

C1 - 3.7E+10

A iVIARYLAND UNIVERdlTY TRAINING REACTOh Sheet No 9 22 Project: Task: Prepared by: J. E. Floyd Date: ' 9 3_.

Calc File No: Reviewed by: W. J. Chacoas Date: _.

Title:

Ar-41 Product'on Calculations for Annual Reoort and 10CFR20 Recuirements DELX - 2.

DELT - 4 DIFF .25 EXB - -306 1/DIFF LAMBDA - 0.000105 MAXFLUX - 1.6E+09 MAXPOS - 309 OUTINT - 900 OUTTIME - 900 PROD - 0.

- -- RELEASE - O.

SIGMAAR - 1.6306E-07 RADIUS - 7.62 PI - 3.14159 4 l

TIME - 0 TUBEBEG - 2 TUBEEND - 401 COREBEG - 136 COREEND - 308 i

CORELEN = 72

, VOLUME - 1.700E+09 00 100 POSIT - 1.MAXP05 g NAR41(POSIT.1)-0 .

NAR41(POSIT.2)-0 100 CONTINUE '  !

C***********************************************************************

C OBTAIN POWER LEVEL AND RUNTIME FROM USER. PREPARE OUTPUT HEADER C

CALL CASINIT

  • C******************?****************************************************

C CALCULATE NUMBER OF TIME STEPS AND BEGIN CACULATION C

NTSTEP - INT (Mt.XTIME/ FELT)

TIME - 0 00 200 1 - 1.NTSTEP TIME - TIME + DELT I C***********************************************************************

C CALL NUMCAL TO CALCULATE ARGON-41 FOR THE CURRENT TIME STEP C

CALL NUMCAL(TIME)

C***********************************************************************

C CALCULATE BULDING CONCENTRATION AND UPDATE RELEASE AND ALSO C MAX LEVEL If NEEDED C

BLEVEL - BLEVEL * (1 - LAMBDA

  • BLEVEL
  • DELT)

BLEVEL - BLEVEL+NAR41(TUBEBEG.1)*P!* RADIUS ** 2 / VOLUME RELEASE - RELEASE +NAR41(TUBEBEG.1)

IF (BLEVEL.GE.MAXLEVEL) THEN MAXLEVEL - BLEVEL ENDIF j C*********************************************************************** i C UPDATE OUPUT FILE !F NEEDED C

IF (TIME.EO.0UTTIME) THEN OUTTIME - OUTTIME + OUTINT ACTVTY - BLEVEL

  • LAMBDA / CI
  • 1000 WRITE (6.900) TIME.ACTVTY.

WRITE (7.900) TIME. ACTVTY ENDIF 200 CONTINUE C***********************************************************************

C WRITE MAXLEVEL. TOTAL PRODUCTION. AND RELEASE TO OUTPUT FILE r

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4 MARYLAND UNIVERolTY TRAINING REACTOR , ,

Sheet No

! 10 of 22 Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File NO: Reviewed by: W. J. Chacoas Date: l

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Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Reauirements '

i ACTVTY - MAXLEVEL

  • LAMBDA / CI
  • 1000 l RELEASE - RELEASE
  • RADIUS **2
  • LAMBDA / CI
  • 1000 1 PROD - PROD
  • P1
  • RADIUS **2
  • LAMBDA / CI
  • 1000 l URITE(6.910) ACTVTY WRITE (7.910) ACTVTY ]

WRITE (6.920) PROD '

WRITE (7.920) PROD I WRITE (6.930) RELEASE URITE(7.930) RELEASE CLOSE(7)

.STOP .

900 FORMAT (17.7.10X E18.10) 910 FORMAT (' MAXIMUM AR 41 CONCENTRATION IS: '.E18.10.* mci /ml >

920 FORMAT (' TOTAL AR 41 PRODUCTION IS: '.E18.10.' mci') J 930 FORMAT (' TOTAL AR-41 RELEASE: '.E18.10.' mC1')

END SUBROUTINE CASINIT C***********************************************************************

C ROUTINE CASEINT (CASE INITIALIZATION) o C

C PURPOSE Gets input data from user on runtime and power level.

C Opens output file and prints header.

C C AUTHOR ' Jason E. Floyd C***********************************************************************

COMMON / CASE!NF/POWFR,RTIME.DELT.DELX.00 TINT,MAXTIME DOUBLE PRECISION POWER.DELX.0ELT INTEGER RTIME.0VTINT.MAXTIME C ,

WRITE (6.900) '

READ (5.*) POWER WRITE (6.910)

READ (5 *) RTIME  :

C***********************************************************************

C DETERMINE TIME TO END CASE  !

C MAXTIME - 1800 + 1800

  • INT ((RTIME+36000)/1800)

C***********************************************************************

C OPEN OUTPUT FILE AND WRITE CASE HEADER C

l OPEN(7 FILE ' ARGON 41.0VT'. STATUS ' UNKNOWN')

WRITE (6.920) POWER.RTIME WRITE (7.920) POWER.RT!ME WP.ITE(6.930) MAXTIME WRITE (7.930) MAXTIME WRITE (6.940) DELX.DELT.0VTINT WRITE (7.940) DELX DELT.0VTINT WRITE (6.950)

WRITE (7.950)

C*********************************************************************** .

C RETURN TO AR41 CAL

  • l C RETURN i 900 FORMAT (' CORE POWER LEVEL IN KW')

910 FORMAT ('RUNTIME IN SECONDS *)

920 FORMAT ( ' ARGON-41 FOR POWER * ,F10.5.

  • KW FOR ' .16.6. ' SECONDS * )

930 FORMAT (' CASE WILL BE RUN UNTIL TIME '.17.7.* SECONDS')

940 FORMAT (' NODE SPACING '.F5.2.' CM. TIME STEP 'F5.2' S. OUTPUT INTER

/ VAL *!5.5' S')

950 FORMAT (' TIME ACTIVITY IN mci /ml')

END SUBROUTINE NUMCAL(TIME) re.........**..........................................................

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' MARYLAND UNIVEhelTY TRAINING REACTOk Sheet No 11 of 22

[ Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File NO: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Recuirements __,

C ROUTINE NUMCAL (Number Density Calculation) l' C

C PURPOSE This routine uses a 1D nodal diffusion calculation to -4 l C determine Ar 41 concentraions in the through tube. A I i C zero boundary condition is at the extrapolated boundary l C of the open end of the tube, and a reflection boundary l l C condition is set at the open end of the tube, I I

l C Production of Ar-41 assumes a cosine flux shape over

! C the active length of the tube for the duration of the C run.

l-C l

C AUTHOR Jason E, Floyd i

C***********************************************************************

COMMON /CASEINF/ POWER,RTIME.DELT.DELX,0UTINT,MAXTIME

' . COMMON /TUBEDIH/TUBEBEG,TUBEEND.COREBEG.COREEND.MAXPOS,CORELEN,EXB

! COMMON /ARCAL/NAR41,MAXFLUX,SIGMAAR, LAMBDA,01FF,PI, PROD i DOUBLE PRECISION MAXFLUX,SIGMAAR, LAMBDA. POWER. PROD, l

/

l DELX,0ELT DIFF. RADIUS. VOLUME BLEVEL.CI.MAXLEVEL,ACTVTY, I

/ NAR41(402.2),CORELEN EXB P!

l INTEGER TUBEBEG.TUBEEND.COREBEG.COREEND.MAXP05,RTIME MAXTIME,

! / OUTTIME,0UTINT T!HE C***********************************************************************

l C ZERO CONCENTRATION AT EXTRAF0 LATED BOUNDARY CONDITION C

NAR41(1,2)'- 0 DO 100 POSIT - 2.TUBEEND NAR41(POSIT,2) - DELT / DELX**2

  • DIFF * (NAR41(POSIT-1,1) +

/ NAR41(POSIT +1,1)) + NAR41(POSIT,1) * (1 - DELT

  • l / (LAMBDA + 2
  • DIFF / DELX**2))

! C***********************************************************************

C IF IN THE ACTIVE REGION OF THE THRU TUBE AND THE REACTOR IS AT i

! C POWER CALCblATE THE AR-41 PRODUCTION i

! C IF ((POSIT.GE.COREBEG). AND.(POSIT.LE.COREEND). AND.(TIME.LE.

l / RTIME)) THEN l NAR41(POSIT,2) - NAR41(POSIT,2) + DELT

  • POWER
  • MAXFLUX
  • i / SIGMAAR
  • COS(Pl*(EXB+ POSIT *DELX)/CORELEN)

I PROD - PROD + DELT

  • POWER
  • MAXFLUX
  • SIGMAAR *

( / COS(Pl*(EXB+ POSIT *0ELX)/CORELEN) i ENDIF C*********************************************************************** i l C MAKE THE NODE AFTER THE LAST NODE E0UAL TO THE NODE BEFORE THE l C LAST NODE TO MEET THE REFECTION BOUNDARY CONDITION C

i IF (POSIT.EO.TUBEEND 1) THEN t

NAR41(MAXP05,2) - NAR41(POSIT,2) l ENDIF 100 CONTINUE 00 200 POSIT - 1.TUBEEND NAR41(POSIT.1) - NAR41(POSIT,2) i 200 CONTINUE

  • C***********************************************************************

l C RETURN TO AR41 CAL

! C RETURN END d

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l WIARYLAND UNIVERolTY TRAINING REACTOh Sheet No 12 of 22 Project: Task: Prepared by: J . E . Floyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Reauirements APPENDIX B AR41 CAL CASE OUTPUTS ,

1 Hour at Full Power ARGON 41 FOR POWER- 250.00000 KW FOR 003600 SECONOS CASE WILL BE RUN UNTIL TIME 0041400 SECONOS NODE SPACING- 2.00 CM. TIME STEP- 4.00 S. OUTPUT INTERVAL-00900 S

- TIME- ACTIVITY IN mC1/ml 0000900 0.1070969988E-51 0001800 0.5162039140E-32 0002700 0.1867650207E 24 0003600 0.7298393504E 21 0004500 0.1133527619E-18 0005400 0.3519077431E 17 i 0006300 0.4307693578E-16 0007200 0.2920954381E 15 0008100 0.1327047791E 14 0009000 0.4531208049E-14 ,

0009900 0.1250763710E 13 l 0010800 0.2928986189E-13 l 0011700 0.6016728670E-13 0012600 ' O.1110881687E 12 0013500 0.1877688714E-12 0014400 0.2947226932E 12 0015300 0.4344135621E-12 i 0016200 0.6066857717E 12 l 0017100 '0.8085598381E-12 0018000 0.1034426223E-11 0018900 0.1276607432E-11 j 0019800 0.1526194370E-11 0020700 0.1774008479E-11 0021600 0.2011518147E-11 0022500 0.2231559265E 11 0023400 0.2428769672E-11 0024300 0.2599722588E-11  ;

0025200 0.2742808224E-11 i 0026100 0.2857948308E-11 l 0027000 0.2946233184E-11 l' 0027900 0.3009554426E-11 0028800 0.3050280186E-11 0029700 0.3070995730E-11 0030600 0.3074313207E-11 i 0031500 0.3062743624E-11 0032400 0.3038619087E 11 0033300 0.3004052530E-11 0034200 0.2960923557E-11 ,

0035100 0.2910881217E 11 i 0036000 0.2855356952E 11  ;

0036900 0.2795582900E 11 0037800 0.2732612417E-11 0038700 0.2667340801E 11 0039600 0.2600525069E-11 0040500 0.2532802155E 11 0041400 0.2464705284E 11 MAXIMUM AR 41 CONCENTRATION IS: 0.3074992466E-11 mci /ml

TOTAL AR 41 PRODUCTION IS
0.2408635586E+01 mC1 TOTAL AR 41 RELEASE: 0.1463356457E 01 mci I

l > MARYLAND UNIVEhdlTY TRAINING REACTOs l Sheet No 13 of 22 Project: Task: Prepared by: J. E. Flovd Date: 10/30/93

! Calc File No: Reviewed by: W. J. Chacoas Date:

l

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Reauirements 10 HoarS at Full Power l ARGON 41 FOR POWER- 250.00000 KW FOR 036000 SECONOS i I

CASE WILL BE RUN UNTIL TIME 0073800 SECONOS N00E SPACING- 2.00 CM. TIME STEP- 4.00 5. DUTPUT INTERVAL-00900 S  !

TIME ACTIVITY IN mci /ml 1 0000900 0.1070969988E-51 l 0001800 0.5162039140E 32 0002700 0.1867650207E-24 l 0003600- 0.7298393504E 21 - - -

0004500 0.1133527619E 18 0005400 0.3519077431E-17 0006300 0.4307693597E-16 0007200 0.2920961679E-15 i 0008100 0.1327161142E 14 0009000 0.4534726880E-14 0009900 0.1255070334E-13 ,

0010800 0.2958174648E-13 l 0011700 0.6149204934E-13 l 0012600 0.1156048686E-12 i 0013500 0.2002206799E-12 l 0014400 0.3238812076E-12 1 0015300 - 0.4944238875E 12 l 0016200 0.7178968866E-12 l 0017100 0.9974553735E-12 0018000 0.1332428969E 11 0018900 0.1717804008E-11 0019800 10.2144349318E 11 0020700 '0.2599490629E 11 0021600 0.3068822342E-11 0022500 0.3537924044E 11 0023400 0.3994039746E 11 0024300 0.4427244412E-11 0025200 0.4830925919E 11 0026100 0.5201639490E-11 0027000 0.5538542944E 11 0027900 0.5842658081E-11 1 0028800 0.6116153837E 11 l 0029700 0.6361763149E-11 0030600 0.6582369770E 11 0031500 0.6780752161E 11 0032400 0.6959449287E-11 0033300 0.7120709432E-11 0034200 0.7266488972E-11 0035100 0.7398477059E-11 0036000 0.7518130600E-11 0036900 0.7626710530E-11 0037800 0.7725314848E 11 .

0038700 0.7814906703E-11 '

0039600 0.7896337291E 11 .

0040500 0.7970364016E 11 l 0041400 0.8037662377E 11 l 0042300 0.8098816191E-11 l 0043200 0.8154246718E 11 ,

0044100 0.8204055517E 11  !

0045000 0.8247828825E 11 0045900 0.8284508465E-11 1 0046800 0.8312413768E 11 i 0047700 0.8329425020E 11 0048600 0.8333271506E-11 0049500 0.8321840202E-11

a s-,m-L--2 e _. _

MARYLAND UNIVEhdlTY TRAINING REACTOk Sheet No 14 of 22__

Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

l

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Recui rements 1

0050400 0.8293433021E-11 0051300 0.8246932190E-11 0052200 0.8181865951E-11 0053100 0.8098389736E-11 0054000 0.7997208670E-11 0054900 0.7879468182E-11 0055800 0.7746634848E-11 0056700 0.7600382767E 11 0057600 0.7442494404E 11 l 0058500 0.7274779718E-11

! 0059400 0.7099014009E-11 _ __

l 0060300 0.6916892923E-11 0061200 0.6730002078E 11 l 0062100 0.6539798531E-11 i 0063000 0.6347601436E-11 0063900 0.61d4589553E 11 0064800 0.5961803670E 11 0065700 0.5770152401E-11 0066600 0.5580420143E 11 0067500 0.5393276299E-11 0068400 0.5209285100E 11 0069300 0.5028915546E-11

, 0070200 0.4852551144E-11 ,,

0071100 ' 0.4680499216E 11 l 0072000 O.4512999648E-11 0072900 0.4350233005E 11 0073800 0.4192327968E-11 MAXIMUM AR 41 CONCENTRATION 15: 0.8333668028E-11 mci /mi TOTAL AR 41 PRODUCTION IS: 0.2408635586E+02 mci TOTAL AR-41 RELEASE: 0.1636378986E+00 mci l

l .

e i

r 1

, l

l MARYLAND UNIVEReilTY TRAINING REACTOFs l Sheet No 15 of _22_,

Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 l Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Reouirements 100 Hours at Full Power 1

I ARGON-41 FOR POWER- 250.00000 KW FOR 360000 SECON05 l CASE WILL BE RUN UNTIL TIME 0397800 SECONOS l

N00E SPACING- 2.00 CM TIME STEF- 4.00 S. OUTPUT INTERVAL-00900 S TIME ACTIVITY IN mci /ml 0000900 -0.1070969988E 51 0001800 0.5162039140E-32 0002700 0.1867650207E-24 0003600 0.7298393504E 21 0004500 0.11335ii619E 18 0005400 0.3519077431E 17 0006300 0.4307693597E-16 0007200 0.2920961679E 15 0008100 0.1327161142E-14 1 0009000 0.4534726880E 14 0009900 0.1255070334E 13 0010800 0.2958174648E-13 0011700 0.6149204934E-13 0012600 0.1156048686E-12 0013500 0.2002206799E-12 0014400 0.3238812076E-12 1 0015300 - 0.4944238875E-12 )

0016200 0.7178968866E-12 1 0017100 0.9974553735E 12 l 0018000 0.1332428969E-11 0018900 0.171780400aE-11 0019800 0.2144349318E-11 0020700 0.2599490629E-11 0021600 0.3068822342E 11 0022500 0.3537924044E-11 0023400 0.3994039746E-11 0024300 0.4427244412E 11 0025200 0.4830925919E-11 0026100 0.5201639490E 11 0027000 0.5538542944E-11 0027900 0.5842658081E-11 ,

0028800 0.6116153837E 11  !! '

0029700 0.6361763149E 11 0030600 0.6582369770E-11 l 0031500 0.6780752161E 11 l 0032400 0;6959449287E-11 0033300 0.7120709432E 11 0034200 0.7266488972E 11 0035100 0.7398477059E 11 0036000 0.7518130600E 11 0036900 0.7626710530E 11 0037800 0.7725314848E-11 -

0038700 0.7814906703E-11 ,

0039600 0.7896337292E 11 0040500 0.7970364117E 11 0041400 0.8037665389E 11 j 0042300 0.8098851363E 11 0043200 0.8154473330E-11 0044100 0.8205030838E 11 0045000 0.8250977572E 11 0045900 0.8292726239E-11 0046800 0.8330652694E-11 0047700 0.8365099491E 11 0048600 0.8396378975E-11 0049500 0.8424776014E 11

I =

MARYLAND UNIVEk6lTY TRAINING REACTOR Sheet No 16 of 22 Project: Task: Prepared by: J. E. Flovd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Re00rt and 10CFR20 Reauirements 0050400 0.8450550440E-11 0051300 0.8473939239E-11 0052200 0.8495158533E-11 0053100 0.8514405380E 11 0054000 0.8531859415E 11 0054900 0.8547684346E-11 0055800 0.8562029324E-11 0056700 0.85/5030198E-11 0057600 0.8586810660E-11 0058500 0.8597483302E-11

0059400 0.8607150576E-11 - _ _ _

0060300 0.8615905682E 11 0061200 0.8623833372E-11 0062100 0.8631010696E-11 0063000 0.8637507681E 11 0063900 0.8643387948E-11 0064800 0.8648709289E-11 0065700 0.8653524177E 11 0066600 0.8657880250E 11 0067500 0.8661820742E 11 0068400 0.8665384879E-11 ~

0069300 0.8668608244E-11 0070200 0.8671523106E-11 0071100 , 0.8674158724E-11 0072000- 0.8676541617E-11 0072900 0.8678695821E-11 0073800 0.8680643115E-11 0074700 0.8682403226E 11 0075600 ,0.8683994024E-11 0076500 10.8685431689E-11 0077400 0.8686730873E-11 0078300 0.868)904837E-11 0079200 0.8688965587E 11 0080100 0.8689923984E-11 0081000 0.8690789859E-11 0081900 0.8691572103E-11 0082800 0.8692278761E 11 0083700 0.8692917109E-11 0084600 0.8693493727E 11 ,

0005500 0.8694014564E 11 ,

0086400 0.8694485001E-11 0087300 0.8694909900E-11 ,

0088200 0.8695293659E-11 0089100 0.8695640251E-11 0090000 0.8695953268E-11 0090900 0.8696235957E 11 0091800 0.8696491251E-11 0092700 0.8696721801E-11 0093600 0.8696930002E 11  : 1 0094500 0.8697118017E-11 0095400 0.8697287801E 11

' )

l- 0096300 0.8697441122E-11 0097200 0.8697579573E 11

, 0098100 0.8697704596E-11 l 0099000 0.8697817493E-11 0099900 0.8697919440E-11 1

0100800 0.8698011498E 11

! 0101700 0.8698094626E-11

. 0102600 0.8698169691E 11 0103500 0.8698237475E-11 0104400 0.8698298684E 11 0105300 0.8698353956E-11 ninsonn n osonaninsve.ii t

l

MARYLAND UNIVEMITY TRAINING REACTOh Sheet No 17 of .22 Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Reauirements 0107100 0.8698448937E 11 0108000 0.8698489636E 11 0108900 0.8698526389E 11 0109800 0.8698559577E-11 l 0110700 0.8698589547E 11 )

0111600 0.8698616612E-11 1 0112500 0.8698641053E 11 0113400 0.8698663124E 11 0114300 0.8698683056E-11 0115200 0.86987010565.-11 0116100 0.8698717312E-11 . __

0117000 0.8698731993E-11 0117900 0.8698745251E 11 0118800 0.8698757225E-11 0119700 0.8698768039E 11 0120600 0.8698777806E-11 0121500 0.8698786627E 11 0122400 0.8698794593E-11 0123300 0.8698801789E-11 0124200 0.8698808287E-11 0125100 0.8698814157E-11 0126000 0.8698819459E 11 jj 0126900 0.8698824248E-11 .j 0127800 ' 0.8698828573E-11 f 0128700 O.8698832480E-11 l 0129600 0.8698836009E 11 0130500 0.8698839197E 11 0131400 0.8698842076E-11 0132300 0.8698844678E-11 .

0133200 10.8698847027E-11  !

0134100 0.8698849150E-11 l' 0135000 0.8698851067E-11 il 1 0135900 0.8698852799E 11 0136800 0.8698854364E 11 0137700 0.8698855778E 11 0138600 0.8698857055E 11 0139500 0.8698858209E-11 i 0140400 0.8698859251E-11 0141300 0.8698860193E-11 0142200 0.8698861044E-11 0143100 0.8698861812E-11 0144000 0.8698862507E 11 0144900 0.8698863134E-11 0145800 0.8698863701E 11 0146700 0.8698864214E-11 l 0147600 0.8698864676E 11 0148500 0.8698865095E 11 0149400 0.8698865473E-11 0150300 0.8698865814E 11 0151200 0.8698866123E-11 ,

0.8698866401 E- 11 .

0152100 0153000 0.8698866653E-11 0153900 0.8698866881E-11 0154800 0.8698867087E-11 0155700 0.8698867273E 11 0156600 0.8698867441E 11 0157500 0.8698867592E-11 0158400 0.8698867730E-11 0159300 0.8698867854E-11 0160200 0.8698867966E 11 0161100 0.8698868067E-11 0162000 0.8698868158E-11 A18906A A Q4000CQ9A1C.11 s

MARYLAND UNIVEholTY TRAINING REACTOh Sheet No 18 of 22 Project: Task: Prepared by: J . E . Flovd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Recuirements 0163800 0.8698868316E-11 0164700 0.8698868383E-11 0165600 0.8698868445E-11 0166500 0.8698868500E-11 0167400 0.8698868550E 11 0168300 0.8698868595E-11 0169200 0.8698868635E-11 0170100 0.8698868672E-11 0171000 0.8698868706E-11 0171900 0.8698868736E-11

-- 0172800 0.8698868763E-11 0173700 0.8698868787E-11 0174600 0.8698868810E 11 0175500 0.8698868830E 11 0176400 0.8698868848E 11 0177300 0.8698868864E 11 0178200 0.8698868879E-11 0179100 0.8698868892E 11 0180000 0.8698868905E 11 0180900 0.8698868916E 11 0181800 0.8698868925E 11 0182700 0.8698868934E-11 0183600 0.8698868943E 11 0184500 0.8698868950E-11 0185400 O.8698868956E 11 0186300 0.8698868962E 11 0187200 0.8698868968E-11 0188100 0.8698868973E-11 0189000 0.869886897.7E 11 0189900 'O.8698868981E-11 0190800 0.8698868985E 11 0191700 0.8698868988E 11 0192600 0.8698868991E 11 0193500 0.8698868994E-11 0194400 0.8698868996E 11 0195300 0.8698868998E-11 0196200 0.8698869000E-11 ,

0197100 0.8698869002E-11 0198000 0.8698869004E 11 0198900 0.8698869005E-11 0199800 0.8698869006E 11 0200700 0.8698869008E 11 0201600 i 0.8698869009E-11 0202500 0.8698869310E-11  !

0203400 0.8698869010E 11 0204300 0.8698869011E-11 0205200 0.8698869012E-11 0206100 0.8698869013E-11 i 0207000 0.8698869013E-11  ;

0207900 0.8698869014E-11 . j 0208800 0.8698869014E-11 .

0209700 0.8698869015E-11 .l 0210600 0.8698869015E-11 0211500 0.8698869015E-11 0212400 0.8698869016E-11 0213300 0.8698869016E-11 0214200 0.8698869016E-11 0215100 0.8698869017E-11 0216000 0.8698869017E 11 0216900 0.8698869017E-11 0217800 0.8698869017E-11 0218700 0.8698869017E 11 A7104A6 A QC000CCA11r.11 e

iVIARYLAND UNIVEhdlTY TRAINING REACTOk Sheet NO 19 of 22 Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File NO: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Recuirements 0220500 0.8698869018E-11 0221400 0.8698869018E 11 0222300 0.8698869018E 11 0223200 0.8698869018E 11 1 0224100 0.8698869018E 11 0225000 0.8698869018E 11 0225900 0.8698869018E-11 4 0226800 0.8698869018E-11 l 0227700 0.8698869018E-11 0228600 0.8698869018E-11 0229500 0 8698869018E 11 - - - -

0230400 0.8698869018E 11 0231300 0.8698869018E-11 0232200 0.8698869018E 11 0233100 0.8698869018E-11 0234000 0.8698869019E-11 0234900 0.8698869019E-11 l 0235000 0.8698869019E-11 0236700 0.8698869019E-11 0237600 0.8698869019E-11 0238500 0.8698869019E 11 0239400 0.8698869019E 11 0240300 0.8698869019E 11 0241200 0.8698869019E-11 0242100 ' O.8698869019E 11 0243000 0.8698869019E-11  ;

0243900 0244800 0.8698869019E 11 0.8698869019E-11 0245700 ,0.8698869019E 11 i 0246600 0.8698869019E-11 I 0247500 0.8698869019E 11 0248400 0.8698869019E-11 -

0249300 0.8698869019E-11 0250200 0.8698869019E 11 0251100 0.8698869019E-11 j 0252000 0.8698869019E-11 i 0252900 0.8698869019E 11 0253800 0.8698869019E 11  !

0254700 0.8698869019E 11 'I 0255600 0.8698869019E-11 0256500 0.8698869019E-11 0257400 0.8698869019E-11 0258300 0.8698869019E-11 0259200 - 0.8698869019E-11 0260100 0.8698869019E 11 0261000 0.8698869019E-11 0261900 0.8698869019E-11 0262800 0.8698869019E-11 0263700 0.8698869019E 11 .

0264600 0.8698869019E 11 i 0265500 0.8698869019E-11 i 0266400 0.8698869019E-11 0267300 0.8698869019E 11 0268200 0.8698869019E 11 0269100 0.8698869019E-11 0270000 0.8698869019E-11 0270900 0.8698869019E-11 0271800 0.8698869019E 11 0272700 0.8698869019E-11 0273600 0.8698869019E 11 0274500 0.8698869019E 11 0275400 0.8698869019E-11 A91C1AA A OC000C0A10r.11

MARYLAND UNIVEhdlTY TRAINING REACTOk l Sheet No 20 of 77 i Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar-41 Production Calculations for Annual Recort and 10CFR20 Recuirements 0277200 0.8698869019E-11 0278100 0.8698869019E-11 0279000 0.8698869019E 11 0279900 0.8698869019E-11 l 0280800 0.8698869019E 11 0281700 0.8698869019E 11 0282600 0.8698869019E 11 0283500 0.8698869019E-11 l 0284400 0.8698869019E 11 0285300 0.8698869019E-11 .l 0286200 0.8698869019E-11 _ _ _ .

1 0287100 0.8698869019E 11 0288000 0.8698869019E 11 0288900 0.8698869019E 11 0289800 0.8698869019E-11 0290700 0.8698869019E 11 0291600 0.8698869019E-11 0292500 0.8698869019E 11 0293400 0.8698869019E-11 0294300 0.8698869019E-11 0295200 0.8698869019E-11 0296100 0.8698869019E 11 0297000 0.8698869019E 11 j 0297900

' 0.8698869019E-11 0298800 O.8698869019E 11 0299700 0.8698869019E-11 0300600 0.8698869019E-11 0301500 0.8698869019E-11 0302400 0.8698869019E 11 i 0303300 IO.8698869019E-11 0304200 0.8698869019E 11 0305100 0.8698869019E 11 0306000 0.8698869019E-11 .

0306900 0.8698869019E-11 1 0307800 0.8698869019E 11 l 0308700 0.8698869019E 11 0309600 0.8698869019E-11 0310500 0.8698869019E 11 0311400 0.8698869019E-11 0312300 0.8698869019E 11 0313200 0.8698869019E-11 0314100 0.8698869019E-11 0315000 0.8698869019E-11 0315900 0.8698869019E-11 0316800 0.8698869019E 11 0317700 0.8698869019E-11 0318600 0.8698869019E-11 0319500 0.8698869019E-11 0320400 0.8698869019E 11 0321300 0.8698869019E 11 0322200 0.8698869019E-11 >

0323100 0.8698869019E 11 0324000 0.8698869019E-11 0324900 0.8698869019E-11 0325800 0.8698869019E 11 0326700 0.8698869019E-11 0327600 0.8698869019E-11 0328500 0.8698869019E-11 0329400 0.8698869019E 11 0330300 0.8698869019E 11 0331200 0.8698869019E 11 0332100 0.8698869019E-11 0111hoo A QC000Kon10r.11

$1ARYLAND UNIVEhcilTY TRAINING REACTOh Sheet No 21 of 22 Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

5

Title:

Ar-41 Production Calculations for Annual Reoort and 10CFR20 Recuirements l 0333900 0.8698869019E-11 l 0334800 0.8698869019E-11 0335700 0.8698869019E 11

, 0336600 0.8698869019E-11 i 0337500 0.8698869019E 11 '

0338400 0.8698869019E 11 0339300 0.8698869019E-11  !

0340200 0.8698869019E 11 i

. 0341100 0.8698869019E 11 l 0342000 0.8698869019E-11

- - 0342900 0.8698869019E-11 0343800 0.8698869019E-11 0344700 0.8698869019E-11 1

0345600 0.8698869019E-11 a 0346500 0.8698869019E 11 1 0347400 0.8698869019E-11 I 0348300 0.8698869019E-11 l

0349200 0.8698869019E 11 l 0350100 0.8698869019E-11 0351000 0.8698869019E-11 ')-

- 0351900 0.8698869019E-11 0352800 0.8698869019E-11 4 0353700 0.8ti98869019E 11 0354600 0.8698869019E-11 0355500 ' O.8696869019E-11 0356400 0.8698869019E 11 0357300 0.8698869019E-11 0358200 0.8698869019E 11 0359100 .0.8698869019E-11 i 0360000 '0.8698869019E-11 l 0360900 0.8698869019E-11 0361800 0.8698869019E 11

  • 0362700 0.8698869019E-11

- 0363600 0.8698869018E-11  !

0364500 0.8698868918E 11 0365400 0.8698866043E 11

! 0366300 0.8698834343E-11 0367200 0.8698645961E 11 0368100 0.8697910189E-11 0369000 0.8695776277E-11 0369900 0.8690802033E-11 0370800 0.8680969885E 11 0371700 0.8663860519E-11 0372600 0.8636929173E 11 0373500 0.8597803632E-11 0374400 0.8544534133E 11 0375300 0.8475755572E 11 0376200 0.8390753647E-11 0377100 0.8289448756E-11 0378000 0.8172322084E 11 i 0378900 0.8040309559E-11

  • 0379800 0.7894685126E 11 4 0380700 0.7736948470E-11 0381600 0.7568726137E-11

. 0382500 0.7391690121E-11 0383400 0.7207494591E-11 0384300 0.7017729434E-11 j 0385200 0.6823888276E 11 0386100 0.6627348334E 11 0387000 0.6429359524E-11 0387900 0.6231040553E 11 l

0388800 0.6033380072E-11 A1001nn A CD17?A11C1C.11 e

1hlARYLAND UNIVEhdlTY TRAINING REACTOh Sheet No 22 of _Z2_

Project: Task: Prepared by: J. E. Floyd Date: 10/30/93 Calc File No: Reviewed by: W. J. Chacoas Date:

Title:

Ar 41 Production Calculations for Annual Recort and 10CFR20 Reauirements 0390600 0.5643369274E-11 0391500 0.5452398111E 11 0392400 0.5264863641E-11 0393300 0.5081206474E-11 0394200 0.4901787279E 11 0395100 0.4726892648E 11 0396000 0.4556744077E-11 0396900 0.4391505762E-11 0397800 0.4231291772E-11 MAXIMUM AR 41 CONCENTRATION 15: 0.8698869019E 11 mci /mi TOTAL AR 41 PRODUCTION IS: 0.2408635586E+03 mCf. _

TOTAL AR-41 RELEASE: 0.1705623475E+01 mci 9

I l

l $

l u

( ENCLOSURE 2:

l Ar-41 Production Calculation for This Reporting Period l

i i

l I

l i

l l

l 12

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CORE POWER LEVEL IN KW l KUNTIME IN SECONDS ARGON-41 FOR POWER = 250.00000 KW FOR 138456 SECONDS CASE WILL BE RUN UNTIL TIME 0174600 SECONDS NODE SPACING = 2.00 CM, TIME STEP = 4.00 S, OUTPUT INTERVAL-00900 S TIME ACTIVITY IN mci /ml 1

0000900 -0.107 096998 8 E-51 0001800 0.5162039140E-32 l 0002700 0.1867650207E-24 0003600 0.7298393504E-21 0.1133527619E-18 l 0004500 0005400 0.3519077431E-17 0006300 0. 4 307 693597 E-16 l 0007200 0.2920961679E-15 0000100 0.1327161142E-14 t 0009U00 0.4534726800E-14 l 0009900 0.1255070334E-13 '

0010000 0.2958174648E-13 0011700 0.6149204934E-13 _. __

0012600 0.1156048686E-12 4 l

0013500 0.2002206799E-12 0014400 0.3238812076E-12 0015300 0.4944238875E-12 0016200 0. 717 8 968 0 66E-12 0017100 0.9974553735E-12 0018000 0.1332428969E-11 0018900 0.1717804000E-11 ,

0019800 0.2144349318E-11 0020700 0.2599490629E-11 l 0.3060822342E-11  !

0021600 00:2500 0.3537924044E-11 l

0023400 0.3994039746E-11 0024300 0.4427244412E-11 0025200 0.4830925919E-11 0026100 0.5201639490E-11 j 0027000 0.5538542944E-11 0027900 0.5842658001E-11 0028800 0.6116153837E-11 0029700 0.6361763149E-11 0030600 0.6582369770E-11 0031500 0. 67 8 07 52161E-11 0032400 0.6959449287E-11 0033300 0.7120709432E-11 0034200 0. 72 6 64 8 8 072E-il 0035100 0.7398477059E-11 0036000 0. 7 518130600E-11 0036900 0. 7 626710530E-11 0037800 0.7725314848E-11 0038700 0.7814906703E-11 0039600 0.7896337292E-11 0040500 0.7970364117E-11 0041400 0.Bu37665389E-11 0042300 0.8098851363E-11 0043200 0.8154473330E-11 0044100 0.8205030838E-11 0045000 0. 825097757 2E-11 0045900 0.8292726239E-11 0046800 0.8330652694E-11 0047700 0.8365099491E-11 0048600 0.8396378975E-11 0049500 0.8424776014E-11 0050400 0.8450550440E-11 0051300 0.8473939239E-11 0052200 0.8495158533E-11 0053100 0.8514405300E-11 0054000 0.8531859415E-11 0054900 0.8547684346E-11 0055800 0.8562029324E-11 0056700 0.8575030198E-11 0057600 0.8586810660E-11 0058500 0.8597483302E-11 0059400 0.8607150576E-11 0060300 0.8615905682E-11 0061200 0.8623833372E-11 0062100 0.8631010696E-11

1 w I 0

0 <

i 0063000 0.8637507681E-11 1 0063900 0.864338794BE-11 1 0064800 0.8648709289E-11 i 0065700 0.8653524177E-11 0066600 0.8657880250E-11 l 0067500 0.8661820742E-11 0068400 0.8665384879E-11 <

l 0069300 0.8668608244E-11 0070200 0.8671523106E-11 0071100 0.8674158724E-11 0072000 0.8676541617E-11 l 0072900 0.8678695821E-11 l 0073800 0.8600643115E-11 0074700 0.8682403226E-11 0075600 0.8683994024E-11 0076500 0.8685431689E-11 0077400 0.8606730873E-11 ]

0078300 0.8607904837E-11 l

. 0079200 0.8680965587E-11 0080100 0.8689923984E-11 - --

0081000 0.8690789859E-11 0081900 0.8691572103E-11 0082800 0.8692278761E-11 1 l

0083700 0.8692917109E-11 0084600 0.8693493727E-11 0085500 0.8694014564E-11 0086400 0.0694485001E-11 0007300 0.8694909900E-11 0088200 0.8695293659E-11 0089100 0.8695640251E-11 0090000 0.0695953268E-11 0090900 0.8696235957E-11 )

0091800 0.8696491251E-11 I 0092700 0.8696721801E-11 0093600 0.8696930002E-11 0094500 0.8697118017E-11 0095400 0.8697287801E-11 0096300 0.8697441122E-11 0097200 0.8697579573E-11 1 0098100 0.8697704596E-11 l 0099000 0.8697817493E-11 0099900 0.8697919440E-11 0100800 0.0698011498E-11 0101700 0.8698094626E-11 0102600 0.8698169691E-11 0103500 0.8698237475E-11 0104400 0.8698298684E-11 0105300 0.8698353956E-11 0106200 0.8698403867E-11 0107100 0.8698448937E-11 0100000 0.8698489636E-11 i 0108900 0.8690526389E-11 '

0109800 0.8698559577E-11 0110700 0.8698589547E-11 0111600 0.8698616612E-11 0112500 0.8698641053E-11 0113400 0.8698663124E-11 0114300 0.8698683056E-11 0115200 0.0698701056E-11 0116100 0.8698717312E-11 0117000 0.8698731993E-11 0117900 0.8698745251E-11 0118800 0.8698757225E-11 0119700 0.8698768039E-11 0120600 0.8698777006E-11 0121500 0.8698786627E-11 0122400 0.8698794593E-11 0123300 0.8698801789E-11 0124200 0.8698808287E-11 0125100 0.8698014157E-11 0126000 0.8698819459E-11 0126900 0.8698824248E-11 0127800 0.0698828573E-11 0128700 0.8698832480E-11 0129600 0.8698836009E-11

v e

4 0130500 0.8698839197E-11 ,

0131400 0.8690042076E-11 0132300 0.8698844678E-11 0133200 0.8698847027E-11 0134100 0.8698849150E-11 0135000 0.8698851067E-11 0135900 0.869B852799E-11 0136000 0.8698854364E-11 0.8698855778E-11 0137700 0138600 0.86988570555-11 0139500 0.8698858209E-11 0140400 0.8698859251E-11 0141300 0.8698860193E-11 0142200 0.8698861042E-11 0143100 0.8698861625E-11 0144000 0.8698857866E-11 ,

0144f00 0.8698814828E-11 0145800 0.8698575352E-11 1 0146700 0.8697687986E-11 l 0147600 0. 8 6 95213018E-11 0148500 0.8689610739E-11 0149400 0.8678784065E-11  ;

0150300 0.8660273501E-11 l 0151200 0.8631542416E-11 0152100 0.8590271378E-11 j 0153000 0.0534595811E-11 1 0153900 0.8463252682E-11 0154800 0.8375632144E-11 0155700 0.8271750420E-11 0156600 0.8152169087E-11 0157500 0.8017886030E-11 0158400 0.7870218592E-11 0159300 0.771069297 4 E-11 0160200 0. 7 54 094 7 9 91E-11 {

0161100 0. 7302 65657 8 E-11 l 0162000 0.7177465334E-11 0162900 0.6986950555E-11 0163800 0.6792588328E-11 0164700 0.6595736025E-11 0165600 0.6397622681E-11 0166500 0.6199346010E-11 0167400 0.6001874214E-11 0168300 0.5006051107E-11 0169200 0.5612603379E-11 3 0170100 0.5422149138E-11 1 0171000 0.5235207084E-11 l 0171900 0.5052205840E-11 i 0172800 0.4873493134E-11 l 0173700 0.4699344593E-11 l 0174600 0.4529972039E-11 l MAXIML'M AR-41 CONCENTRATION IS: 0.3698861625E-11 mC1/mi TOTAL AR-41 FRODUCTION IS: 0.926361246373 ^J n c.

TOTAL AR-41 RELEASE: 0.649657716?E+C0 .

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