Estimation of fission source bias in Monte Carlo eigenvalue calculations
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6844680
- Argonne National Laboratory, IL (United States)
- Mississippi State Univ., Mississippi State, MS (United States)
Monte Carlo eigenvalue calculations using a fixed number of histories per generation are biased. Previous work has shown that the bias in eigenvalue is generally smaller than observed standard deviations. In this paper, the authors propose a method for bounding [delta][psi] the bias in the unnormalized fission source. In addition, the authors construct a plausibility argument suggesting that the bias is generally insignificant. Results presented are for discretized diffusion calculations based on a Monte Carlo-generated source. Additional calculations have been run for true transport problems using a very fast, but more conventional, Monte Carlo code.
- OSTI ID:
- 6844680
- Report Number(s):
- CONF-931160--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
- Country of Publication:
- United States
- Language:
- English
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