Re: [fluka-discuss]: How to Calculate DPA in the defined geometry -attached

From: Paola Sala <paola.sala_at_mi.infn.it>
Date: Mon, 2 Mar 2020 08:45:11 +0100

Hello
the energy threshold for DPA has to be provided by the user. There are
useful compilations for various materials in
* R.E.MacFarlane et al, Nucl. Data Sheets 111, 2739 (2010) (Table 2) *
* A.Yu.Konobeyev et al, Nucl. Energy and Tech. 3, 169 (2017) (Table 4) *
* NEA Report Nuclear SCience NEA/NSC/DOC(2015)9 (Table 2.4)

For neutrons below 20 MeV, DPAs evaluation is based on the KERMA factors
calculated by the NJOY code from neutron reaction databases.

To plot DPA along the shield, insert a USERBIN structure, like the one you
have dor "dose110", that covers and segments your shield, asking for
DPA-SCO as quantity.

Hope this helps
Paola
..try to find values for materials similar to the one you are intersterd
in (looks like concrete)
> 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.
>
> ------------------------------------------------------------------------------------------------------------------------------------------------------------------
>
> 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
>
>
> --------------------------------------------------------------------------------------------------------------------------------------------------------------
>
>
> 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
> सद€प र‚œन मितरा S.R. Mitra
> ‰प म–य …भिय‚ता Dy.C.E.
> …भिय‚तरि•ि, ल.दबल.†र Engg-LWR
>
>
>
> ** Radiation exposure to public from NPP is negligible **
>
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Paola Sala
INFN Milano
tel. Milano +39-0250317374
tel. CERN +41-227679148

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Received on Mon Mar 02 2020 - 10:16:20 CET

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