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Manuscript Title: SPECTRUM, a computer code for prompt fission neutron spectrum and prompt neutron multiplicity calculation.
Authors: G. Vladuca, A. Tudora
Program title: SPECTRUM
Catalogue identifier: ADLH_v1_0
Distribution format: gz
Journal reference: Comput. Phys. Commun. 125(2000)221
Programming language: Fortran, Quickbasic.
Computer: PC-Pentium 200MHz.
Operating system: MS-DOS, Windows95.
RAM: 500K words
Word size: 32
Keywords: Nuclear physics, Fission process, Prompt fission neutron, Spectrum, Average prompt neutron, Multiplicity, Neutron emission, In fission, Post-scission, Number of prompt, Neutrons per fission, Energy distribution of, Secondary neutrons.
Classification: 17.23.

Nature of problem:
Prompt fission neutron spectrum and average prompt neutron multiplicity are calculated.

Solution method:
Prompt fission neutron spectrum and average prompt neutron multiplicity are calculated in the frame of Los Alamos model with multiple fission chances. Energy dependence of the compound nucleus cross sections of inverse process and incident neutron energy dependence of model parameters are considered.

Restrictions:
Only the neutrons evaporated prior to scission are considered, the pre-equilibrium effects are neglected. The maximum number of compound nuclei undergoing fission (or fission chances) is four.

Unusual features:
Dependence on the incident neutron energy of model parameters, graphics and possibility to compare the results with data of external input files.

Running time:
Five minutes in the option of the energy dependence of the compound nucleus cross sections of the inverse process and less than 1 minute in the option of constant compound nucleus cross sections.

References:
[1] Madland, D.G., Nix, J.R. Nucl. Sci. Eng. 81 (1982), 213-271.
[2] Madland, D.G., LaBauve, R.J., Nix, J.R. "Physics of Neutron Emission in Fission", Proc. of a consultants meeting on physics of neutron emission in fission, Mito, Japan (1988), IAEA INDC(NDS)-220 (1989), 259-281.
[3] Madland, D.G. "Post-scission fission theory", H4-SMR/1056-10,11, Workshop on Nucl. Reac. Data and Nucl. Reactors, Physics, Design and Safety, ICTP-Trieste, Italy (1998).