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*DECK FMAC01
SUBROUTINE FMAC01(IPMACR,IMPX,HPART,LIN,IVERS,NGP,NPART,NGXI,
1 NEDIT,NUCL,NK,NUFIS,MASM3,N,NGPRT,HNPRT,NPMIN,NPMAX,NANIS,MUFIS)
*
*-----------------------------------------------------------------------
*
*Purpose:
* Recover data and 1D cross sections from the FMAC-M ascii file.
*
*Copyright:
* Copyright (C) 2020 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
* IPMACR LCM object address of the MACROLIB.
* IMPX print flag.
* HPART character*1 name of the MACROLIB particle.
* LIN unit number of the FMAC-M ascii file.
* IVERS file version number.
* NGP sum of number of energy groups for all types of particles.
* NPART number of particle types.
* NGXI number of groups with non-zero fission spectrum.
* NEDIT number of additional edit cross sections.
* NUCL number of nuclides.
* NK number of mixtures.
* NUFIS number of fission materials.
* MASM3 length of integer control array.
* N integer control array.
*
*Parameters: output
* NGPRT number of energy groups per particle type.
* HNPRT character*1 names of particle types.
* NPMIN minimum transition group number.
* NPMAX maximum transition group number.
* NANIS number of Legendre orders per energy group.
* MUFIS fission material number per mixture.
*
*-----------------------------------------------------------------------
*
USE GANLIB
*----
* SUBROUTINE ARGUMENTS
*----
TYPE(C_PTR) IPMACR
INTEGER IMPX,LIN,IVERS,NGP,NPART,NGXI,NEDIT,NUCL,NK,NUFIS,
1 MASM3,N(MASM3),NGPRT(NPART),NPMIN(NGP),NPMAX(NGP),NANIS(NGP),
2 MUFIS(NUFIS)
CHARACTER(LEN=1) HPART,HNPRT(NPART)
*----
* LOCAL VARIABLES
*----
PARAMETER(IOUT=6)
TYPE(C_PTR) JPMACR
CHARACTER TEX(50)*6,HSMG*131
*----
* ALLOCATABLE ARRAYS
*----
REAL, ALLOCATABLE, DIMENSION(:) :: H1
REAL, ALLOCATABLE, DIMENSION(:,:) :: H2
REAL, ALLOCATABLE, DIMENSION(:,:,:) :: H3
CHARACTER(LEN=6), ALLOCATABLE, DIMENSION(:) :: HNGAR
*
NGROUP=0
IPART=0
DO K=1,MASM3
LTOT=N(K)
IF(LTOT.EQ.0) CYCLE
IG1=0
IG2=0
SELECT CASE(K)
CASE(1)
* title
READ(LIN,'(12A6)') (TEX(I),I=1,LTOT)
IF(IMPX.GT.0) WRITE(IOUT,1000) (TEX(I),I=1,LTOT)
CASE(2)
* number of energy groups by particle type
IF(LTOT.NE.NPART) CALL XABORT('FMAC01: BAD RECORD 2.')
READ(LIN,'(6I12)') (NGPRT(I),I=1,LTOT)
CALL LCMPUT(IPMACR,'PARTICLE-NGR',NPART,1,NGPRT)
CASE(3)
* particle names by particle type
IF(LTOT.NE.NPART) CALL XABORT('FMAC01: BAD RECORD 3.')
ALLOCATE(HNGAR(LTOT))
READ(LIN,'(12A6)') (HNGAR(I),I=1,LTOT)
DO I=1,LTOT
IF(HNGAR(I).EQ.'NEUT') THEN
HNPRT(I)='N'
ELSE IF(HNGAR(I).EQ.'GAMA') THEN
HNPRT(I)='G'
ELSE IF(HNGAR(I).EQ.'BETA') THEN
HNPRT(I)='B'
ELSE IF(HNGAR(I).EQ.'POSITR') THEN
HNPRT(I)='C'
ELSE IF(HNGAR(I).EQ.'PROT') THEN
HNPRT(I)='P'
ELSE
WRITE(HSMG,'(8HFMAC01: ,A6,26H IS AN INVALID PARTICLE NA,
1 3HME.)') HNGAR(I)
CALL XABORT(HSMG)
ENDIF
ENDDO
DEALLOCATE(HNGAR)
CALL LCMPTC(IPMACR,'PARTICLE-NAM',1,NPART,HNPRT)
DO I=1,NPART
IF(HNPRT(I).EQ.HPART) THEN
IPART=I
GO TO 30
ENDIF
ENDDO
CALL XABORT('FMAC01: PARTICLE '//HPART//' NOT AVAILABLE IN'
1 //' FMAC-M FILE.')
30 CONTINUE
CASE(4)
* rest energies by particle type
IF(LTOT.NE.NPART) CALL XABORT('FMAC01: BAD RECORD 4.')
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DO I=1,LTOT
H1(I)=H1(I)*1.0E6
ENDDO
CALL LCMPUT(IPMACR,'PARTICLE-MC2',NPART,2,H1)
DEALLOCATE(H1)
CASE(5)
* energy mesh boundaries for all particles
IF(LTOT.NE.NGP+NPART) CALL XABORT('FMAC01: BAD RECORD 5.')
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
DO I=1,LTOT
H1(I)=H1(I)*1.0E6
ENDDO
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)+1
ENDDO
IG2=IG1+NGPRT(IPART)
NGROUP=NGPRT(IPART)
JPMACR=LCMLID(IPMACR,'GROUP',NGROUP)
CALL FMAC04(NGPRT,NGP,NPART,1,H1(1))
CALL LCMPUT(IPMACR,'ENERGY',NGROUP+1,2,H1)
DEALLOCATE(H1)
CASE(6)
* group velocities
IF(LTOT.NE.NGP) CALL XABORT('FMAC01: BAD RECORD 6.')
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(7)
* nuclide names
IF(LTOT.NE.NUCL) CALL XABORT('FMAC01: BAD RECORD 7.')
READ(LIN,'(12A6)') (TEX(I),I=1,LTOT)
CASE(8)
* nuclide nuclear densities and averaged temperatures by
* materials
IF(LTOT.NE.(NUCL+1)*NK) CALL XABORT('FMAC01: BAD RECORD 8.')
ALLOCATE(H2((NUCL+1),NK))
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NUCL+1),J=1,NK)
DEALLOCATE(H2)
CASE(9)
* nuclide temperatures by materials
IF(LTOT.NE.NUCL*NK) CALL XABORT('FMAC01: BAD RECORD 9.')
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(10)
* additional edit cross section names
IF(LTOT.NE.NEDIT) CALL XABORT('FMAC01: BAD RECORD 10.')
IF(IVERS.GE.5) THEN
READ(LIN,'(12A6)') (TEX(I),I=1,LTOT)
ELSE
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
ENDIF
CASE(11)
* PMIN array
IF(LTOT.NE.NGP) CALL XABORT('FMAC01: BAD RECORD 11.')
READ(LIN,'(6I12)') (NPMIN(I),I=1,LTOT)
CASE(12)
* PMAX array
IF(LTOT.NE.NGP) CALL XABORT('FMAC01: BAD RECORD 12.')
READ(LIN,'(6I12)') (NPMAX(I),I=1,LTOT)
CASE(13)
CALL XABORT('FMAC01: This record (13) is UNDEFINED in the ve'
1 //'rsion.ge.3 of format FMAC-M.')
CASE(14)
* number of scattering cross-section moments
IF(LTOT.NE.NGP) CALL XABORT('FMAC01: BAD RECORD 14.')
READ(LIN,'(6I12)') (NANIS(I),I=1,LTOT)
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
CASE(15)
* total cross sections
IF(LTOT.NE.NK*NGP) CALL XABORT('FMAC01: BAD RECORD 15.')
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)
ENDDO
IG2=IG1+NGPRT(IPART)-1
ALLOCATE(H2(NK,NGP))
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NK),J=1,NGP)
CALL FMAC02(IPMACR,NK,IG2-IG1+1,H2(1,IG1),'NTOT0')
DEALLOCATE(H2)
CASE(16)
* absorption cross sections
IF(LTOT.NE.NK*NGP) CALL XABORT('FMAC01: BAD RECORD 16.')
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)
ENDDO
IG2=IG1+NGPRT(IPART)-1
ALLOCATE(H2(NK,NGP))
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NK),J=1,NGP)
CALL FMAC02(IPMACR,NK,IG2-IG1+1,H2(1,IG1),'ABS')
DEALLOCATE(H2)
CASE(17)
* mixture corresponding to each fissile mixture
IF(LTOT.NE.NUFIS) CALL XABORT('FMAC01: BAD RECORD 17.')
READ(LIN,'(6I12)') (MUFIS(I),I=1,LTOT)
CASE(18)
* fission cross sections
IF(LTOT.NE.NUFIS*NGP) CALL XABORT('FMAC01: BAD RECORD 18.')
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(19)
* neutron production cross sections by fission material
IF(LTOT.NE.NUFIS*NGP) CALL XABORT('FMAC01: BAD RECORD 19.')
IF(NUFIS.EQ.0) CALL XABORT('FMAC01: NO FISSILE MIXTURES.')
IF(NGROUP.EQ.0) CALL XABORT('FMAC01: NGROUP UNDEFINED.')
ALLOCATE(H2(NUFIS,NGP),H3(NK,NUFIS,NGROUP))
H3(:NK,:NUFIS,:NGROUP)=0.0
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NUFIS),J=1,NGP)
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)
ENDDO
IG2=IG1+NGPRT(IPART)-1
DO I=1,NUFIS
IK=MUFIS(I)
IF((IK.LE.0).OR.(IK.GT.NK)) CALL XABORT('FMAC01: WRONG MUF'
1 //'IS VALUE.')
H3(IK,I,:NGROUP)=H2(I,IG1:IG2)
ENDDO
CALL FMAC02(IPMACR,NK*NUFIS,NGROUP,H3(1,1,1),'NUSIGF')
DEALLOCATE(H3,H2)
CASE(20)
* fission spectra by fission material
IF(LTOT.NE.NUFIS*NGXI) CALL XABORT('FMAC01: BAD RECORD 20.')
IF(NUFIS.EQ.0) CALL XABORT('FMAC01: NO FISSILE MIXTURES.')
IF(NGROUP.EQ.0) CALL XABORT('FMAC01: NGROUP UNDEFINED.')
ALLOCATE(H2(NUFIS,NGXI),H3(NK,NUFIS,NGROUP))
H3(:NK,:NUFIS,:NGROUP)=0.0
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NUFIS),J=1,NGXI)
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)
ENDDO
IG2=IG1+NGPRT(IPART)-1
DO I=1,NUFIS
IK=MUFIS(I)
IF((IK.LE.0).OR.(IK.GT.NK)) CALL XABORT('FMAC01: WRONG MUF'
1 //'IS VALUE.')
H3(IK,I,:NGXI)=H2(I,IG1:IG2+NGXI-NGROUP)
ENDDO
CALL FMAC02(IPMACR,NK*NUFIS,NGROUP,H3(1,1,1),'CHI')
DEALLOCATE(H3,H2)
CASE(21)
* fission nuclide numbers
READ(LIN,'(6I12)') (N(I),I=1,LTOT)
CASE(22)
* summary parts of delayed fission neutrons by fission nuclides
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(23)
* relative delayed group parts of delayed fission neutrons
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(24)
* decay constants of delayed neutrons
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(25)
* fission spectra of instantaneous fission neutrons
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(26)
* fission spectra of delayed fission neutrons
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(27)
* blocked microscopic neutron production cross sections
ALLOCATE(H1(LTOT))
READ(LIN,'(6E12.0)') (H1(I),I=1,LTOT)
DEALLOCATE(H1)
CASE(28:34)
CALL XABORT('FMAC01: This record (28:34) is UNDEFINED in the'
1 //' version.ge.3 of format FMAC-M.')
CASE(35)
* restricted stopping power
IF(LTOT.NE.NK*(NGP+NPART)) CALL XABORT('FMAC01: INVALID RECO'
1 //'RD 35.')
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)+1
ENDDO
IG2=IG1+NGPRT(IPART)
ALLOCATE(H2(NK,NGP+NPART))
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NK),J=1,NGP+NPART)
IF((HPART.EQ.'N').OR.(HPART.EQ.'G')) THEN
DEALLOCATE(H2)
CYCLE
ENDIF
CALL FMAC04(NGPRT,NGP,NPART,NK,H2(1,1))
CALL FMAC02(IPMACR,NK,IG2-IG1+1,H2(1,IG1),'ESTOPW')
DEALLOCATE(H2)
CASE(36)
* restricted momentum transfer cross section
IF(LTOT.NE.NK*NGP) CALL XABORT('FMAC01: BAD RECORD 36.')
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)
ENDDO
IG2=IG1+NGPRT(IPART)-1
ALLOCATE(H2(NK,NGP))
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NK),J=1,NGP)
IF((HPART.EQ.'N').OR.(HPART.EQ.'G')) THEN
DEALLOCATE(H2)
CYCLE
ENDIF
CALL FMAC02(IPMACR,NK,IG2-IG1+1,H2(1,IG1),'EMOMTR')
DEALLOCATE(H2)
CASE(37)
* energy deposition cross section
IF(LTOT.NE.NK*NGP) CALL XABORT('FMAC01: BAD RECORD 37.')
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)
ENDDO
IG2=IG1+NGPRT(IPART)-1
ALLOCATE(H2(NK,NGP))
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NK),J=1,NGP)
CALL FMAC02(IPMACR,NK,IG2-IG1+1,H2(1,IG1),'H-FACTOR')
DEALLOCATE(H2)
CASE(38)
* charge deposition cross section
IF(LTOT.NE.NK*NGP) CALL XABORT('FMAC01: BAD RECORD 38.')
IF(IPART.EQ.0) CALL XABORT('FMAC01: PARTICLE TYPE UNDEFINED.')
IG1=1
DO I=1,IPART-1
IG1=IG1+NGPRT(I)
ENDDO
IG2=IG1+NGPRT(IPART)-1
ALLOCATE(H2(NK,NGP))
READ(LIN,'(6E12.0)') ((H2(I,J),I=1,NK),J=1,NGP)
CALL FMAC02(IPMACR,NK,IG2-IG1+1,H2(1,IG1),'C-FACTOR')
DEALLOCATE(H2)
CASE DEFAULT
CALL XABORT('FMAC01: This record (>38) is UNDEFINED in the'
1 //' version.ge.3 of format FMAC-M.')
END SELECT
ENDDO
RETURN
1000 FORMAT(/9H FMAC01: ,12A6)
END
|
