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*DECK LIBE3R
SUBROUTINE LIBE3R(CFILNA1,CFILNA2,MAXR,NEL,NBESP,IMPX,ITNAM,
1 ITZEA,KPAX,BPAX,ENER)
*
*-----------------------------------------------------------------------
*
*Purpose:
* Read depletion data on an APOLIB-3 formatted library.
*
*Copyright:
* Copyright (C) 2022 Ecole Polytechnique de Montreal
* This library is free software; you can redistribute it and/or
* modify it under the terms of the GNU Lesser General Public
* License as published by the Free Software Foundation; either
* version 2.1 of the License, or (at your option) any later version.
*
*Author(s): A. Hebert
*
*Parameters: input
* CFILNA1 APOLIB-3 cross section file name.
* CFILNA2 APOLIB-3 depletion file name.
* MAXR number of reaction types.
* NEL number of isotopes on library.
* NBESP number of energy-dependent fission yield matrices.
* IMPX print flag.
*
*Parameters: output
* ITNAM reactive isotope names in chain.
* ITZEA 6-digit nuclide identifier:
* atomic number z*10000 (digits) + mass number a*10 +
* energy state (0 = ground state, 1 = first state, etc.).
* KPAX complete reaction type matrix.
* BPAX complete branching ratio matrix.
* ENER output energy mesh corresponding to a yield macrogroup.
*
*-----------------------------------------------------------------------
*
USE GANLIB
USE hdf5_wrap
*----
* SUBROUTINE ARGUMENTS
*----
CHARACTER CFILNA1*(*),CFILNA2*(*)
INTEGER MAXR,NEL,NBESP,IMPX,ITNAM(3,NEL),ITZEA(NEL),
1 KPAX(NEL+MAXR,NEL)
REAL BPAX(NBESP,NEL+MAXR,NEL),ENER(NBESP+1)
*----
* LOCAL VARIABLES
*----
TYPE(C_PTR) IPAP1,IPAP2
DOUBLE PRECISION SUM
PARAMETER (IOUT=6,MAXR2=12)
PARAMETER (KDECAY=1,KFISSP=2,KCAPTU=3,KN2N=4,KN3N=5,KN4N=6)
CHARACTER RECNAM*80,HSMG*131,NMDEPA(MAXR2)*6
*----
* ALLOCATABLE ARRAYS
*----
INTEGER, ALLOCATABLE, DIMENSION(:) :: IA,IZ
REAL, ALLOCATABLE, DIMENSION(:) :: BRANCH,FSYIELDS,YIELDEN
CHARACTER(LEN=100), ALLOCATABLE, DIMENSION(:) :: LIST
CHARACTER(LEN=24), ALLOCATABLE, DIMENSION(:) :: NAMES,DEPLNAMES,
> FSISNAMES,FSPRNAMES,PNAMES,REACID
*----
* DATA STATEMENTS
*----
SAVE NMDEPA
DATA NMDEPA/'DECAY ','NUFISS','MT102 ','MT16 ',
> 'MT17 ','MT37 ','MT107 ','MT103 ',
> 'MT108 ','MT28 ','MT104 ','MT105 '/
*----
* OPEN APOLIB FILES
*----
CALL hdf5_open_file(CFILNA1,IPAP1,.true.)
IF(IMPX.GT.1) THEN
CALL hdf5_list_groups(IPAP1,"/",LIST)
WRITE(*,*)
WRITE(*,*) 'LIBE3R: GROUP TABLE OF CONTENTS FOR FILE ',CFILNA1
DO I=1,SIZE(LIST)
WRITE(*,*) TRIM(LIST(I))
ENDDO
DEALLOCATE(LIST)
ENDIF
IPAP2=C_NULL_PTR
IF(CFILNA2.NE.' ') THEN
CALL hdf5_open_file(CFILNA2,IPAP2,.true.)
IF(IMPX.GT.1) THEN
CALL hdf5_list_groups(IPAP2,"/",LIST)
WRITE(*,*)
WRITE(*,*) 'LIBE3R: GROUP TABLE OF CONTENTS FOR FILE ',CFILNA2
DO I=1,SIZE(LIST)
WRITE(*,*) TRIM(LIST(I))
ENDDO
DEALLOCATE(LIST)
ENDIF
ENDIF
*----
* RECOVER INFORMATION FROM Head AND PhysicalData GROUPS IN IPAP1
*----
CALL hdf5_read_data(IPAP1,"Head/nbIs",NISOT)
IF(NISOT.NE.NEL) CALL XABORT('LIBE3R: INVALID VALUE OF NEL.')
CALL hdf5_read_data(IPAP1,"Head/IsNames",NAMES)
DO ISO=1,NISOT
READ(NAMES(ISO),'(3A4)') (ITNAM(II,ISO),II=1,3)
ENDDO
CALL hdf5_read_data(IPAP1,"PhysicalData/MassNb",IA)
CALL hdf5_read_data(IPAP1,"PhysicalData/AtomicNb",IZ)
*----
* RECOVER INFORMATION FROM "Yields GROUP IN IPAP2
*----
IF(C_ASSOCIATED(IPAP2)) THEN
CALL hdf5_list_groups(IPAP2,"Chain",DEPLNAMES)
CALL hdf5_read_data(IPAP2,"Yields/FsIsNames",FSISNAMES)
CALL hdf5_read_data(IPAP2,"Yields/FsPrNames",FSPRNAMES)
CALL hdf5_read_data(IPAP2,"Yields/FsYields",FSYIELDS)
CALL hdf5_read_data(IPAP2,"Yields/YieldEnMshInMeV",YIELDEN)
NDEP=SIZE(DEPLNAMES)
NDFI=SIZE(FSISNAMES)
NDFP=SIZE(FSPRNAMES)
*----
* FISSION YIELD NORMALIZATION
*----
DO IGF=1,NBESP
DO IFI=1,NDFI
SUM=0.0D0
DO IFP=1,NDFP
IOF=((IFP-1)*NDFI+IFI-1)*NBESP+IGF
SUM=SUM+FSYIELDS(IOF)
ENDDO
DO IFP=1,NDFP
IOF=((IFP-1)*NDFI+IFI-1)*NBESP+IGF
FSYIELDS(IOF)=2.0*FSYIELDS(IOF)/REAL(SUM)
ENDDO
ENDDO
ENDDO
ELSE
NDEP=0
NDFI=0
NDFP=0
ENDIF
*----
* MAIN LOOP OVER ISOTOPES
*----
NDFP2=0
BPAX(:NBESP,:NEL+MAXR,:NEL)=0.0
DO ISO=1,NISOT
ITZEA(ISO)=IZ(ISO)*10000+IA(ISO)*10
II=LEN(TRIM(NAMES(ISO)))
IF(NAMES(ISO)(II:II).EQ."M") ITZEA(ISO)=ITZEA(ISO)+1
*----
* DECAY AND BURNOUT OF ISOTOPE ISO
*----
WRITE(RECNAM,'(10HIsotopeXS/,A,10H/DecayData)') TRIM(NAMES(ISO))
IF(hdf5_group_exists(IPAP1,TRIM(RECNAM))) THEN
CALL hdf5_read_data(IPAP1,TRIM(RECNAM)//"/Lambda",DECAY)
IF(DECAY.NE.0.0) THEN
KPAX(NEL+KDECAY,ISO)=1
BPAX(:,NEL+KDECAY,ISO)=DECAY*1.E8
ENDIF
ENDIF
WRITE(RECNAM,'(10HIsotopeXS/,A,12H/ReactionXS/)')
1 TRIM(NAMES(ISO))
IF(hdf5_group_exists(IPAP1,TRIM(RECNAM))) THEN
CALL hdf5_list_datasets(IPAP1,TRIM(RECNAM),LIST)
DO IREAC=2,MAXR
II=LEN(TRIM(NMDEPA(IREAC)))
DO I=1,SIZE(LIST)
IF(LIST(I)(:II).EQ.NMDEPA(IREAC)) THEN
KPAX(NEL+IREAC,ISO)=1
EXIT
ENDIF
ENDDO
ENDDO
DEALLOCATE(LIST)
ENDIF
IF(IMPX.GT.2) THEN
WRITE(IOUT,100) NAMES(ISO),BPAX(1,NEL+KDECAY,ISO)
WRITE(IOUT,110) (NMDEPA(I),KPAX(NEL+I,ISO),I=1,MAXR)
ENDIF
*----
* PARENT REACTIONS OF ISOTOPE ISO
*----
IF(.NOT.C_ASSOCIATED(IPAP2)) CYCLE
DO I=1,NDEP
IF(NAMES(ISO).EQ.DEPLNAMES(I)) GO TO 10
ENDDO
GO TO 25
10 WRITE(RECNAM,'(6HChain/,A,9H/NBPARENT)') TRIM(NAMES(ISO))
CALL hdf5_read_data(IPAP2, RECNAM, NBPAR)
IF(NBPAR.EQ.0) GO TO 25
WRITE(RECNAM,'(6HChain/,A,1H/)') TRIM(NAMES(ISO))
CALL hdf5_read_data(IPAP2,TRIM(RECNAM)//"BRANCHRATIO",BRANCH)
CALL hdf5_read_data(IPAP2,TRIM(RECNAM)//"PARENTNAME",PNAMES)
CALL hdf5_read_data(IPAP2,TRIM(RECNAM)//"REACTIONID",REACID)
IF(IMPX.GT.2) WRITE(IOUT,120) (PNAMES(IPAR),IPAR=1,NBPAR)
DO IPAR=1,NBPAR
JSO=0
DO I=1,NISOT
IF(PNAMES(IPAR).EQ.NAMES(I)) THEN
JSO=I
GO TO 20
ENDIF
ENDDO
WRITE(HSMG,'(38HLIBE3R: UNABLE TO FIND PARENT ISOTOPE ,A,
1 8H OF SON ,A,19H IN DEPLETION LIST.)') TRIM(PNAMES(IPAR)),
2 TRIM(NAMES(ISO))
CALL XABORT(HSMG)
20 IF(REACID(IPAR)(:5).EQ.'DRTYP') THEN
KPAX(ISO,JSO)=KDECAY
ELSE IF(REACID(IPAR).EQ.'REAMT102') THEN
KPAX(ISO,JSO)=KCAPTU
ELSE IF(REACID(IPAR).EQ.'REAMT16') THEN
KPAX(ISO,JSO)=KN2N
ELSE IF(REACID(IPAR).EQ.'REAMT17') THEN
KPAX(ISO,JSO)=KN3N
ELSE IF(REACID(IPAR).EQ.'REAMT37') THEN
KPAX(ISO,JSO)=KN4N
ELSE
WRITE(HSMG,'(36HLIBE3R: UNKNOWN PRODUCTION REACTION ,A)')
1 TRIM(REACID(IPAR))
CALL XABORT(HSMG)
ENDIF
BPAX(:,ISO,JSO)=BRANCH(IPAR)
ENDDO
DEALLOCATE(REACID,PNAMES,BRANCH)
*----
* FISSION YIELD OF ISOTOPE ISO
*----
25 IFP=0
DO I=1,NDFP
IF(NAMES(ISO).EQ.FSPRNAMES(I)) THEN
IFP=I
GO TO 30
ENDIF
ENDDO
GO TO 50
30 DO IPAR=1,NDFI
JSO=0
DO I=1,NISOT
IF(FSISNAMES(IPAR).EQ.NAMES(I)) THEN
JSO=I ! fissile isotope
GO TO 40
ENDIF
ENDDO
WRITE(HSMG,'(39HLIBE3R: UNABLE TO FIND FISSILE ISOTOPE ,A,
1 8H OF SON ,A,19H IN DEPLETION LIST.)') TRIM(PNAMES(IPAR)),
2 TRIM(NAMES(ISO))
CALL XABORT(HSMG)
40 KPAX(ISO,JSO)=KFISSP
DO I=1,NBESP
IOF=((IFP-1)*NDFI+IPAR-1)*NBESP+I
BPAX(I,ISO,JSO)=FSYIELDS(IOF)
ENER(I)=YIELDEN(I)*1.E6
ENDDO
ENER(NBESP+1)=YIELDEN(NBESP+1)*1.E6
ENDDO
50 DO IPAR=1,NDFP
IF(FSPRNAMES(IPAR).EQ.NAMES(ISO)) THEN
NDFP2=NDFP2+1
GO TO 60
ENDIF
ENDDO
60 CONTINUE
ENDDO
IF(NDFP2.NE.NDFP) CALL XABORT('LIBE3R: MISSING FISSION PRODUCT.')
IF(C_ASSOCIATED(IPAP2)) DEALLOCATE(YIELDEN,FSYIELDS,FSPRNAMES,
1 FSISNAMES,DEPLNAMES)
DEALLOCATE(IZ,IA,NAMES)
CALL hdf5_close_file(IPAP1)
CALL hdf5_close_file(IPAP2)
*----
* FIND FISSION PRODUCTS
*----
DO ISO=1,NISOT
DO JSO=1,NISOT
IF(KPAX(JSO,ISO).EQ.KFISSP) KPAX(NEL+KFISSP,JSO)=-1
ENDDO
ENDDO
RETURN
*
100 FORMAT(/44H LIBE3R: DECAY AND BURNOUT DATA FOR ISOTOPE=,A/
1 5X,6HDECAY=,1P,E12.5,7H E-8 /S)
110 FORMAT(5X,12(A6,2H= ,I1,2X))
120 FORMAT(5X,14HPARENT NAMES: ,12A8/(19X,12A8))
END
|
