Development of a Pulsed Slowing-Down-Time Benchmark of Neutron Thermalization in Graphite
Conference
·
· Transactions of the American Nuclear Society
- North Carolina State Univ., Raleigh, NC (United States)
Graphite is a classic neutronic material that has been used as both a reactor reflector and moderator in various nuclear reactor systems. The ability to accurately predict the slowing down and thermalization of neutrons in graphite can have significant implications on the safety and operation of such reactor systems. In reactors, the neutron thermalization process is quantified using the thermal scattering law (TSL) and related cross sections for a given moderator. An ideal approach to assess the validity of TSL data is using benchmark measurement based on the pulsed Slowing-Down-Time technique and its comparison with the appropriate graphite nuclear library. In this work, experimental measurement and computational Monte Carlo simulations were performed to benchmark the slowing down characteristics and thermalization of neutrons in nuclear (reactor-grade) graphite. Given the density of graphite, various graphite libraries were selected for the benchmark analysis.
- Research Organization:
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)
- DOE Contract Number:
- AC52-07NA27344
- OSTI ID:
- 1902126
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Issue: 1 Journal Volume: 124
- Country of Publication:
- United States
- Language:
- English
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