Neutronic analysis of boral plate irradiation experiments
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:411768
- Univ. of Michigan, Ann Arbor, MI (United States)
In support of accelerated radiation aging tests of boral, a neutron absorbing material comprising B{sub 4}C, iron foils were irradiated in and around boral samples at the Ford Nuclear Reactor (FNR) of the University of Michigan. Monte Carlo calculations were performed with the MCNP code, to simulate the foil activation and to determine the neutron absorption rate within the boral samples so that an equivalent gamma dose of boral plates in spent fuel storage pools may be estimated. Using a first-flight transport model, verified through the MCNP simulations, we suggest a simple method to determine the neutron absorption rate within a boral plate from the neutron flux measured at the absorber surface.
- OSTI ID:
- 411768
- Report Number(s):
- CONF-951006--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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