Dear Experts
I hv created the following input file for shielded source of Pu-Be
Neutron and calculating flux and dose beyond a serpentine concrete wall.
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TITLE
* Set the defaults for precision simulations
DEFAULTS PRECISIO
* Define the beam characteristics
BEAM -0.015 10000. NEUTRON
* Define the beam position
BEAMPOS 0.0 0.0 -8.
SOURCE
GEOBEGIN COMBNAME
0 0
* Black body
SPH blkbody 0.0 0.0 0.0 100000.
* Void sphere
SPH void 0.0 0.0 0.0 10000.
* Void sphere
SPH med 0.0 0.0 0.0 9500.
SPH det 0.0 0.0 45. 0.5
SPH det1 0.0 0.0 -8.6 0.3
SPH det2 -14. 0.0 -8. 0.5
RPP wll3 -13. 13. -13. 13. -21. 6.
RPP wll2 -9. 9. -9. 9. -17. 1.
RPP wll1 -6. 6. -6. 6. -14. -2.
RPP sc -1. 1. -1. 1. -9. -7.
TRC cnn 0.0 0.0 6. 0.0 0.0 -5. 1. 1.
TRC cnn1 0.0 0.0 1. 0.0 0.0 -3. 1. 1.
TRC cnn2 0.0 0.0 -2. 0.0 0.0 -5. 1. 1.
RPP shld -50. 50. -50. 50. 20. 40.
END
* Black hole
BLKBODY 5 +blkbody -void
* Void Arround
VOID 5 +void-med
* Void Arround
MED 5 +med-wll3-shld-det-det2
CNN 5 +cnn
CNN1 5 +cnn1
CNN2 5 +cnn2
SHLD 5 +shld
DET 5 +det
DET1 5 +det1
DET2 5 +det2
COLL 5 +wll3-wll2-cnn
ABS 5 +wll2 -wll1-cnn1
SC 5 sc-det1
MOD 5 +wll1 -sc-cnn2
END
GEOEND
* 104 Air dry (near sea level)
*
MATERIAL .00120484 AIR
COMPOUND -1.248E-4 CARBON -0.755267 NITROGEN -0.231781 OXYGENAIR
COMPOUND -0.012827 ARGON AIR
* 276 Water liquid H2O
* Chemical Formula: H -- O -- H
MATERIAL 1. WATER
COMPOUND 2. HYDROGEN 1. OXYGEN WATER
MATERIAL 19. 0.862 POTASSIU
* Concrete portland
* Concrete has a wide variation in density and composition.
MATERIAL 2.3 PORTLAND
COMPOUND -0.01 HYDROGEN -0.001 CARBON -0.529107 OXYGENPORTLAND
COMPOUND -0.016 SODIUM -0.002 MAGNESIU -0.033872
ALUMINUMPORTLAND
COMPOUND -0.337021 SILICON -0.013 POTASSIU -0.044 CALCIUMPORTLAND
COMPOUND -0.014 IRON PORTLAND
MATERIAL 48. 8.65 CADMIUM
MATERIAL 17. 0.003214 CHLORINE
* Polyvinylidene chloride saran (C2_H2_Cl2)n
*
MATERIAL 1.7 SARAN
COMPOUND -0.020793 HYDROGEN -0.247793 CARBON -0.731413 CHLORINESARAN
MATERIAL 24. 7.18 CHROMIUM
* Concrete Serpentine
* concentration varries with host rock
MATERIAL 2.3 SERPENTI
COMPOUND -0.016 HYDROGEN -0.004 CARBON -0.511 OXYGENSERPENTI
COMPOUND -0.004 SODIUM -0.134 MAGNESIU -0.019
ALUMINUMSERPENTI
COMPOUND -0.208 SILICON -0.004 POTASSIU -0.067 CALCIUMSERPENTI
COMPOUND -0.001 CHROMIUM -0.031 IRON -0.001 NICKELSERPENTI
ASSIGNMA BLCKHOLE BLKBODY BLKBODY
ASSIGNMA VACUUM VOID VOID
ASSIGNMA LEAD COLL COLL
ASSIGNMA CADMIUM ABS ABS
ASSIGNMA SARAN MOD MOD
ASSIGNMA AIR SC SC
ASSIGNMA AIR CNN CNN
ASSIGNMA AIR CNN2 CNN2
ASSIGNMA AIR CNN1 CNN1
ASSIGNMA AIR MED MED
ASSIGNMA SERPENTI SHLD SHLD
ASSIGNMA AIR DET DET
ASSIGNMA AIR DET1 DET1
ASSIGNMA AIR DET2 DET2
USRBIN 12. NEUTRON -21. DET dose310
USRBIN DET 1. 1. 1. &
USRBIN 12. DOSE-EQ -22. DET dose210
USRBIN DET 1. 1. 1. &
USRBIN 10. NEUTRON -23. 50. 50. 75.dose110
USRBIN -50. -50. -30. 100. 100. 100. &
USRTRACK -1. NEUTRON -24. DET1 0.113112 50.
USRTRACK 15E-2 1E-10 &
USRTRACK -1. NEUTRON -25. DET2 0.523667 50.
USRTRACK 15E-2 1E-10 &
USRTRACK -1. NEUTRON -26. DET 0.523667 50.
USRTRACK 15E-2 1E-10 &
* Set the random number seed
RANDOMIZ 1.
* Set the number of primary histories to be simulated in the run
START 1E7
STOP
-------------------------------------------------------------------------------------------------------------------------------------------------
and following source file
*$ CREATE SOURCE.FOR
*COPY SOURCE
*
*=== source ===========================================================*
*
SUBROUTINE SOURCE ( NOMORE )
INCLUDE '(DBLPRC)'
INCLUDE '(DIMPAR)'
INCLUDE '(IOUNIT)'
*----------------------------------------------------------------------*
* Version for isotropic Pu-Be source.
*
c*****DIMENSION CFCUM(0:72), ENEDGE(73), ANG(0:40), CUMANG(0:40)
DIMENSION CFCUM(0:48), ENEDGE(49), ANG(0:48), CUMANG(0:48)
*----------------------------------------------------------------------*
*
INCLUDE '(BEAMCM)'
INCLUDE '(CASLIM)'
INCLUDE '(FHEAVY)'
INCLUDE '(FLKSTK)'
INCLUDE '(IOIOCM)'
INCLUDE '(LTCLCM)'
INCLUDE '(PAPROP)'
INCLUDE '(SOURCM)'
INCLUDE '(SUMCOU)'
*
LOGICAL LFIRST
SAVE LFIRST
DATA LFIRST / .TRUE. /
*----------------------------------------------------------------------*
* Neutron energy group boundaries
c**** Pu-Be neutron spectrum
* Neutron energy group boundaries
DATA ENEDGE /
&1.220000E-02, 1.20000E-02,1.18000E-02,
&1.15000E-02,1.13000E-02,1.10000E-02,1.08000E-02,1.05000E-02,
&1.03000E-02,1.00000E-02,9.75000E-03,9.50000E-03,9.25000E-03,
&9.00000E-03,8.75000E-03,8.50000E-03,8.25000E-03,8.00000E-03,
&7.75000E-03,7.50000E-03,7.25000E-03,7.00000E-03,6.75000E-03,
&6.50000E-03,6.25000E-03,6.00000E-03,5.75000E-03,5.50000E-03,
&5.25000E-03,5.00000E-03,4.75000E-03,4.50000E-03,4.25000E-03,
&4.00000E-03,3.75000E-03,3.50000E-03,3.25000E-03,3.00000E-03,
&2.75000E-03,2.50000E-03,2.25000E-03,2.00000E-03,1.75000E-03,
&1.50000E-03,1.25000E-03,1.00000E-03,7.50000E-04,5.00000E-04,
&2.50000E-04/
*
* Cumulative Pu-Be spectrum in group strcuture
DATA CFCUM / 0.D0,
&7.85000E-09,1.77900E-08,
&3.03900E-08,7.13390E-07,6.15134E-05,6.78513E-04,2.70851E-03,
&6.38851E-03,1.25585E-02,2.23285E-02,3.60285E-02,5.19285E-02,
&6.87285E-02,8.64285E-02,1.05429E-01,1.26429E-01,1.49629E-01,
&1.74429E-01,1.99829E-01,2.25329E-01,2.50829E-01,2.75829E-01,
&2.97329E-01,3.13429E-01,3.32729E-01,3.54029E-01,3.78429E-01,
&4.09729E-01,4.47329E-01,4.87629E-01,5.30129E-01,5.74629E-01,
&6.21829E-01,6.72329E-01,7.25329E-01,7.80529E-01,8.25129E-01,
&8.54729E-01,8.77829E-01,8.98429E-01,9.15129E-01,9.26829E-01,
&9.42929E-01,9.61229E-01,9.79329E-01,9.93979E-01,9.99729E-01,
&1.000000000E+00/
*...+....1....+....2....+....3....+....4....+....5....+....6....+....7..
* Angle cosines
*Deleted
*----------------------------------------------------------------------*
*...+....1....+....2....+....3....+....4....+....5....+....6....+....7..
*----------------------------------------------------------------------*
NOMORE = 0
* +-------------------------------------------------------------------*
* | First call initializations:
IF ( LFIRST ) THEN
* | *** The following 3 cards are mandatory ***
TKESUM = ZERZER
LFIRST = .FALSE.
LUSSRC = .TRUE.
* | *** User initialization ***
write(lunout,*)
write(lunout,'(a,132a)') ("*",i=1,132)
write(lunout,*)
write(lunout,*)
write(lunout,'(a)') "Pu-Be"
write(lunout,*)
write(lunout,*)
write(lunout,'(a,132a)') ("*",i=1,132)
write(lunout,*)
END IF
* |
* +-------------------------------------------------------------------*
* Sample the energy group
XI = FLRNDM(DUMMY)
DO 500 K = 1, 48
IF(XI .LE. CFCUM(K)) THEN
NEUGRP = K+2
ENERGY = ENEDGE(K) -
& (XI-CFCUM(K-1))*(ENEDGE(K)-ENEDGE(K+1))/(CFCUM(K)-CFCUM(K-1))
GO TO 600
END IF
500 CONTINUE
STOP ' Failed to sample the energy group'
600 CONTINUE
kount=kount+1
*
*Added this Start
COSTHE = TWOTWO*FLRNDM()-ONEONE
SINTHE = SQRT(ONEONE-COSTHE**2)
PHI = TWOPIP*FLRNDM()
COSPHI=COS(PHI)
SINPHI = SIN(PHI)
*Added this end
* Npflka is the stack counter: of course any time source is called it
* must be =0
NPFLKA = NPFLKA + 1
* Wt is the weight of the particle
WTFLK (NPFLKA) = ONEONE
WEIPRI = WEIPRI + WTFLK (NPFLKA)
* Particle type (1=proton.....). Ijbeam is the type set by the BEAM
* card
* +-------------------------------------------------------------------*
* | Heavy ion:
IF ( IJBEAM .EQ. -2 ) THEN
IJHION = IPROZ * 1000 + IPROA
IJHION = IJHION * 100 + KXHEAV
IONID = IJHION
CALL DCDION ( IONID )
CALL SETION ( IONID )
ILOFLK (NPFLKA) = IJHION
* |
* +-------------------------------------------------------------------*
* | Normal hadron:
ELSE
IONID = IJBEAM
ILOFLK (NPFLKA) = IJBEAM
END IF
* |
* +-------------------------------------------------------------------*
* From this point .....
* Particle generation (1 for primaries)
LOFLK (NPFLKA) = 1
* User dependent flag:
LOUSE (NPFLKA) = 0
* User dependent spare variables:
DO 100 ISPR = 1, MKBMX1
SPAREK (ISPR,NPFLKA) = ZERZER
100 CONTINUE
* User dependent spare flags:
DO 200 ISPR = 1, MKBMX2
ISPARK (ISPR,NPFLKA) = 0
200 CONTINUE
* Save the track number of the stack particle:
ISPARK (MKBMX2,NPFLKA) = NPFLKA
NPARMA = NPARMA + 1
NUMPAR (NPFLKA) = NPARMA
NEVENT (NPFLKA) = 0
DFNEAR (NPFLKA) = +ZERZER
* ... to this point: don't change anything
* Particle age (s)
AGESTK (NPFLKA) = +ZERZER
AKNSHR (NPFLKA) = -TWOTWO
* Group number for "low" energy neutrons
IGROUP (NPFLKA) = NEUGRP
* Kinetic energy of the particle (GeV)
TKEFLK (NPFLKA) = ENERGY
* Particle momentum
PMOFLK (NPFLKA) = SQRT ( TKEFLK (NPFLKA) * ( TKEFLK (NPFLKA)
* + TWOTWO * AM (ILOFLK(NPFLKA)) ) )
* Cosines (tx,ty,tz) (make sure they are properly normalized)
TZFLK (NPFLKA) = COSTHE
TYFLK (NPFLKA) = SINTHE * COSPHI
TXFLK (NPFLKA) = SQRT(ONEONE-TZFLK(NPFLKA)**2-TYFLK(NPFLKA)**2)
IF(FLRNDM(COSPHI) .LE. HLFHLF) TXFLK (NPFLKA) = -TXFLK (NPFLKA)
* Polarization cosines:
TXPOL (NPFLKA) = -TWOTWO
TYPOL (NPFLKA) = +ZERZER
TZPOL (NPFLKA) = +ZERZER
* Particle coordinates
XFLK (NPFLKA) = XBEAM
YFLK (NPFLKA) = YBEAM
ZFLK (NPFLKA) = ZBEAM
* Calculate the total kinetic energy of the primaries: don't change
IF ( ILOFLK (NPFLKA) .EQ. -2 .OR. ILOFLK (NPFLKA) .GT. 100000 )
& THEN
TKESUM = TKESUM + TKEFLK (NPFLKA) * WTFLK (NPFLKA)
ELSE IF ( ILOFLK (NPFLKA) .NE. 0 ) THEN
TKESUM = TKESUM + ( TKEFLK (NPFLKA) + AMDISC (ILOFLK(NPFLKA)) )
& * WTFLK (NPFLKA)
ELSE
TKESUM = TKESUM + TKEFLK (NPFLKA) * WTFLK (NPFLKA)
END IF
* Flag this is prompt radiation
LRADDC (NPFLKA) = .FALSE.
RADDLY (NPFLKA) = ZERZER
* Here we ask for the region number of the hitting point.
* NREG (NPFLKA) = ...
* The following line makes the starting region search much more
* robust if particles are starting very close to a boundary:
CALL GEOCRS ( TXFLK (NPFLKA), TYFLK (NPFLKA), TZFLK (NPFLKA) )
CALL GEOREG ( XFLK (NPFLKA), YFLK (NPFLKA), ZFLK (NPFLKA),
& NRGFLK(NPFLKA), IDISC )
* Do not change these cards:
CALL GEOHSM ( NHSPNT (NPFLKA), 1, -11, MLATTC )
NLATTC (NPFLKA) = MLATTC
CMPATH (NPFLKA) = ZERZER
CALL SOEVSV
RETURN
*=== End of subroutine Source =========================================*
END
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Can I use DPA-SCO in Region SHLD for neutron damage with thickness of
Serpentine concrete for calculation
Is it required to use another card MAT-PROP for which Mat=SERPENTIN in
my case.
1 . What will be DPA Eth ( energy threshold) ?
2. How does DPA - SCO calculate damage for neutrons ?
3. How to plot DPA along thickness of shld ?
Pl help.
Regards
--
सादर Regards
सुदीप रंजन मित्रा S.R. Mitra
उप मुख्य अभियंता Dy.C.E. अभियंत्रिकि, एल.दब्लु.आर Engg-LWR
** Radiation exposure to public from NPP is negligible **
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Received on Tue Feb 25 2020 - 17:07:32 CET