NESC9554 ZZ-REAC2.
ZZ REAC-2, Nuclide Activation and Transmutation
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-REAC-2 | NESC9554/01 | Arrived | 13-FEB-2002 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NESC9554/01 | CRAY 1 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
Flux library
============
FORMAT: special format
NUMBER OF GROUPS: 63 group fluxes
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: Fred Mann (Westinghouse, Hanford)
WEIGHTING SPECTRUM: --
Cross Section library
=====================
FORMAT: special format
NUMBER OF GROUPS: 63 group cross section
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: Fred Mann (Westinghouse, Hanford)
WEIGHTING SPECTRUM: --
Decay Data library
==================
FORMAT: special format
NUMBER OF GROUPS: --
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: Fred Mann (Westinghouse, Hanford)
WEIGHTING SPECTRUM: --
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
REAC2 calculates the change in composition of materials in a
radiation field and related activation quantities. It is best suited to problems where many variables (e.g. materials, facilities or locations within facilities, powerhistories) are to be investigated. Where very accurate results are needed, the user must access the accuracy of the cross section base (e.g. source, flux weighting) as in the use of any neutronics code.
REAC2 consists of three programs - SREAC, SLSTCOM, and SLIB. SREAC calculates the transmutation of nuclides in a radiation field. SLSTCOM reads the output file produced by SREAC and produces listings of abundances, decay rates, dose rates, heating rates, etc. in a user-specified file format. SLIB converts one or more card-image format libraries into binary form for program use.
Two auxiliary codes, LISTCRS and LISTDCY, are included to edit the cross section and decay binary data files, respectively.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
Flux library
============
FORMAT: special format
NUMBER OF GROUPS: 63 group fluxes
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: Fred Mann (Westinghouse, Hanford)
WEIGHTING SPECTRUM: --
Cross Section library
=====================
FORMAT: special format
NUMBER OF GROUPS: 63 group cross section
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: Fred Mann (Westinghouse, Hanford)
WEIGHTING SPECTRUM: --
Decay Data library
==================
FORMAT: special format
NUMBER OF GROUPS: --
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po.
ORIGIN: Fred Mann (Westinghouse, Hanford)
WEIGHTING SPECTRUM: --
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
REAC2 calculates the change in composition of materials in a
radiation field and related activation quantities. It is best suited to problems where many variables (e.g. materials, facilities or locations within facilities, powerhistories) are to be investigated. Where very accurate results are needed, the user must access the accuracy of the cross section base (e.g. source, flux weighting) as in the use of any neutronics code.
REAC2 consists of three programs - SREAC, SLSTCOM, and SLIB. SREAC calculates the transmutation of nuclides in a radiation field. SLSTCOM reads the output file produced by SREAC and produces listings of abundances, decay rates, dose rates, heating rates, etc. in a user-specified file format. SLIB converts one or more card-image format libraries into binary form for program use.
Two auxiliary codes, LISTCRS and LISTDCY, are included to edit the cross section and decay binary data files, respectively.
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4. METHOD OF SOLUTION
The spectrum-averaged cross section is obtained by collapsing the multigroup cross sections with the multigroup flux. The equations used assume that the cross sections are for a point in space and ignore the spatial transport of material and the time dependence of the cross sections. In order to provide a fast, stable solution to the transmutation equation, REAC2 lessens the couplings between nuclides implied by the transmutation equation. The code assumes that during any time period of arbitrary length (1) the flux is constant as a function of time, (2) no reaction occurs on a reaction product or a decay product, and (3) at most six decays can occur for a reaction product or the initial nuclide. Using these assumptions, REAC2 calculates exactly the resulting distribution of nuclides. Once the distribution is known, other quantities of interest such as the decay rate, dose rate, transmutations, etc. can be calculated from a linear combination of the nuclide amounts.
The spectrum-averaged cross section is obtained by collapsing the multigroup cross sections with the multigroup flux. The equations used assume that the cross sections are for a point in space and ignore the spatial transport of material and the time dependence of the cross sections. In order to provide a fast, stable solution to the transmutation equation, REAC2 lessens the couplings between nuclides implied by the transmutation equation. The code assumes that during any time period of arbitrary length (1) the flux is constant as a function of time, (2) no reaction occurs on a reaction product or a decay product, and (3) at most six decays can occur for a reaction product or the initial nuclide. Using these assumptions, REAC2 calculates exactly the resulting distribution of nuclides. Once the distribution is known, other quantities of interest such as the decay rate, dose rate, transmutations, etc. can be calculated from a linear combination of the nuclide amounts.
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NESC9554/01
miscellaneous mag tapeTape contents description MISTPsource program mag tapeSubroutine library Fortran source SRCTP
source program mag tapeSREAC Fortran source SRCTP
source program mag tapeSLSTCOM Fortran source SRCTP
source program mag tapeSLIB Fortran source SRCTP
symb data lib mag tapeMaterial library of alloys and compounds LBSTP
symb data lib mag tapeMaterial library of isotopes LBSTP
symb data lib mag tapePMaterial library of elements LBSTP
symb data lib mag tapeFlux library containing 63-group fluxes LBSTP
symb data lib mag tape63-group cross section library LBSTP
symb data lib mag tapeDecay data library LBSTP
source program mag tapeREAC2 compilation notes SRCTP
report mag tapeREAC2 machine-readable documentation REPTP
test-case data mag tapeControl information to execute REAC2 DATTP
source program mag tapeUPDATE comdecks machine-independent subrou.SRCTP
source program mag tapeUPDATE comdecks machine-specific subrou. SRCTP
source program mag tapeUPDATE MFE-spec. subroutines UPDATE source SRCTP
source program mag tapeUPDATE LANL-spec. subroutines UPDATE sourceSRCTP
source program mag tapeI/O Suboutines UPDATE source SRCTP
source program mag tapeInteger I/O Subroutines UPDATE source SRCTP
source program mag tapeStack Subroutines UPDATE source SRCTP
source program mag tapeUtility Subroutines UPDATE source SRCTP
test-case data mag tapeControl information to create SLDR DATTP
source program mag tapeSLIB UPDATE source part 1 SRCTP
source program mag tapeSLIB UPDATE source part 2 SRCTP
source program mag tapeSLIB UPDATE source part 3 SRCTP
source program mag tapeSLIB UPDATE source part 4 SRCTP
test-case data mag tapeControl information to create SLIB DATTP
source program mag tapeSLSTCOM UPDATE source part 1 SRCTP
source program mag tapeSLSTCOM UPDATE source part 2 SRCTP
source program mag tapeSLSTCOM UPDATE source part 3 SRCTP
source program mag tapeSLSTCOM UPDATE source part 4 SRCTP
source program mag tapeSLSTCOM UPDATE source part 5 SRCTP
source program mag tapeSLSTCOM UPDATE source part 6 SRCTP
source program mag tapeSLSTCOM UPDATE source part 7 SRCTP
test-case data mag tapeControl information to create SLSTCOM DATTP
source program mag tapeSREAC UPDATE source part 1 SRCTP
source program mag tapeSREAC UPDATE source part 2 SRCTP
source program mag tapeSREAC UPDATE source part 3 SRCTP
source program mag tapeSREAC UPDATE source part 4 SRCTP
source program mag tapeSREAC UPDATE source part 5 SRCTP
source program mag tapeSREAC UPDATE source part 6 SRCTP
source program mag tapeSREAC UPDATE source part 7 SRCTP
source program mag tapeSREAC UPDATE source part 8 SRCTP
test-case data mag tapeControl information to create SREAC DATTP
source program mag tapeLISTCRS UPDATE source SRCTP
source program mag tapeLISTDCY UPDATE source SRCTP
Keywords: activation analysis, cross sections, decay, isotopes, materials, radiation effects, transmutation.