sp-fispact2001 - ENEA AFS Cell

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3. Input the main nuclide which composes the material irradiated in the MCNPX problem. The isotope must be indicated with the ID number as used internally by FISPACT (see [9] or the file EAF_INDEX_20010 in the directory „eaf2001‟). It is allowed to input only a single isotope. If the material is composed of more than one isotope then choose the most abundant. SP-FISPACT2001 will perform calculations as if all the residual nuclei provided by HTAPE3X were produced by this isotope. The new code word is TARGET. Example: if the material irradiated is natural Pb, Pb 208 can be chosen as representative of the whole material and write TARGET 1631. 4. Input the number of atoms of the isotope chosen in the above paragraph. The new code word is ATTARGET. Example: if there are 1E29 atoms of Pb 208 , then write: ATTARGET 1E29. 5. The standard code word NOERROR (see [4], p. 44) must be used because the error data for the interactions above 20MeV are not present. 6. Specify one of the following two new code words as alternative to the standard code word COLLAPSE: TCOLLAPSE or HCOLLAPSE. -TCOLLAPSE stands for „Total Collapse‟. This code word collapses both the standard FISPACT cross-sections and the pseudo cross-sections >20MeV. All the values are written in the file COLLAPX. Example: if the cross section library in 175 groups is to be used, then: TCOLLAPSE 175. -HCOLLAPSE stands for „High Collapse‟. This code word collapses only the pseudo crosssection >20MeV created from MCNPX and not the standard FISPACT2001 cross-section. This option can be used if only the effects of interactions >20MeV are to be investigated. Example: HCOLLAPSE 175. Here is an another example of preliminary input file „collapx.i‟ for an accelerator of 30mA, providing a flux under 20MeV of 3.43E14 neutrons/cm 2 sec in 4.92E25 atoms of 9 Be. The energy group VITAMIN-J is used under 20MeV. FLUX 3.43E14 CURRENT 30 TARGET 15 ATTARGET 4.92E25 NOERROR TCOLLAPSE 175 FISPACT * COLLAPSE VITAMIN-J END * END OF RUN /* 12
As in the standard FISPACT procedure prepare the preliminary file arrayx.i and run: spfisp01 collapx.out spfisp01 arrayx.out 3.3 Preparation of the main input The main input is a standard FISPACT input with the following constraints: 1. It is necessary to use the code word FUEL (with the DENSITY code word) and not the code word MASS. 2. The number of atoms of the material irradiated in MCNPX and specified in the preliminary input (code word ATTARGET) has to be provided again with the code word FUEL (it must obviously have the same value). 3. The value of the flux under 20MeV has to be provided again (it must obviously have the same value). Here is an example of the main input for the same example as the previous preliminary input: AINP FISPACT *Residual nuclei at all energies DENSITY 1.8477 FUEL 1 BE9 4.92E25 MIND 1.0E5 FLUX 3.43E14 ATOMS LEVEL 100 8 TIME 1 YEARS ATOMS FLUX 0. ZERO TIME 1 HOURS ATOMS END * END /* Finally, run: spfisp01 output 13
Page 1: SP-FISPACT2001 A COMPUTER CODE FOR
Page 5: TABLE OF CONTENTS 1. Introduction .
Page 8 and 9: protons) in a 3-D geometry. Neutron
Page 10 and 11: output (with flux
Page 14 and 15: 4. Warnings 1. Not all the nuclides
Page 16 and 17: 5. Conclusions SP-FISPACT2001 makes
Page 18 and 19: c Initialisation NUCLF=0 NUCLH=0 NM
Page 20 and 21: HISOT(IZM(I),INM(I))=HISOT(IZM(I),I
Page 22 and 23: The differences between the two fma
Page 24 and 25: COMMON /SPAL3/ NP2(15000),ND2(15000
Page 26 and 27: dNi ( t) �24 � �� ij N j (
Page 28: References [1] Laurie S. Waters, Ed

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