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- Title
CALCULATION OF EIGENFUNCTION FLUXES IN NUCLEAR SYSTEMS.
- Authors
Hendricks, John S.; Finch, Joshua P.; Choi, Chan
- Abstract
A new Monte Carlo method is being developed to calculate eigenfunction fluxes in critical or near-critical nuclear systems. The correct estimation of fluxes is essential for radiation protection and shielding near these systems, in addition to isotope production, isotope depletion, nuclear criticality and other applications. The proposed method applies to Monte Carlo criticality eigenvalue calculations in which the fission sites in one generation are used as fission sources in subsequent generations. The usual Monte Carlo power iteration method for such problems often calculates fluxes (eigenfunctions) that are inaccurate and very different in symmetric parts of a problem geometry. The proposed method calculates flux distributions by estimating an approximate fission matrix. The way the fission matrix is estimated and used differs from other recent works. Preliminary results are promising.
- Subjects
NUCLEAR fuels; MONTE Carlo method; RADIATION protection; STOCHASTIC processes; EIGENVALUES; NUMERICAL solutions to boundary value problems
- Publication
Radiation Protection Dosimetry, 2005, Vol 115, Issue 1-4, p69
- ISSN
0144-8420
- Publication type
Article
- DOI
10.1093/rpd/nci190