Monte Carlo approach to sequential neutron emission from fission fragments
- Theoretical Division, Nuclear Physics Group, Los Alamos National Laboratory, Los Alamos, New Mexico, 87545 (United States)
We have implemented a Monte Carlo simulation of fission fragment statistical decay by sequential neutron emission. Within this approach, we calculate the center-of-mass and laboratory prompt neutron energy spectra as a function of the mass of fission fragments and integrated over the whole mass distribution. We also assess the prompt neutron multiplicity distribution P({nu}), both the average number of emitted neutrons and the average neutron energy as a function of the mass of the fission fragments [respectively {nu}(A) and <E>(A)]. We investigate the average total energy available for prompt {gamma}-ray emission as a function of the mass of the fission fragments E{sub {gamma}}(A). We also calculate neutron-neutron correlations such as the full matrix {nu}(A,TKE) as well as correlations between neutron energies. Two assumptions for partitioning the total available excitation energy among the light and heavy fragments are considered. Results are reported for the neutron-induced fission of {sup 235}U (at neutron energy of 0.53 MeV) and for the spontaneous fission of {sup 252}Cf.
- OSTI ID:
- 20698909
- Journal Information:
- Physical Review. C, Nuclear Physics, Vol. 72, Issue 2; Other Information: DOI: 10.1103/PhysRevC.72.024601; (c) 2005 The American Physical Society; Country of input: International Atomic Energy Agency (IAEA); ISSN 0556-2813
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CALIFORNIUM 252
CENTER-OF-MASS SYSTEM
COMPUTERIZED SIMULATION
CORRELATIONS
ENERGY SPECTRA
EXCITATION
FISSION FRAGMENTS
GAMMA RADIATION
MASS DISTRIBUTION
MEV RANGE
MONTE CARLO METHOD
MULTIPLICITY
NEUTRON EMISSION
PROMPT NEUTRONS
SPONTANEOUS FISSION
URANIUM 235