Nuclear heat load calculations for the NBSR cold neutron source using MCNP
Creators
- 1. Nuclear Center in Negev, Beer-Sheva (Israel)
- 2. National Institute of Standards and Technology, Gaithersburg, MD (United States)
Description
A liquid-hydrogen (LH2) cold neutron source is being designed for installation in the 20-MW National Bureau of Standards reactor (NBSR) at National Institute of Standards and Technology to replace the D2O-ice cold source currently in use. An accurate estimate of the heat deposited in the cold source is needed to ensure that it can be adequately cooled for successful operation. The heat load is caused by the interaction of neutrons and gamma rays with the cold moderator and the walls of the moderator chamber. The Monte Carlo code, MCNP (Version 4.2), was used to model the entire NBSR core and both the existing and the proposed cold sources. The model was used to calculate not only the heat load but also the reactivity and neutron gain of each source
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 69
- Journal Page Range
- p. 404-405.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 14-18 Nov 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26026202
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLD NEUTRONS; COOLING; GEOMETRY; HEAT TRANSFER; M CODES; MATHEMATICAL MODELS; MONTE CARLO METHOD; NBSR REACTOR; NEUTRON SOURCES; REACTOR PHYSICS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTER CODES; ELEMENTARY PARTICLES; ENERGY TRANSFER; FERMIONS; HADRONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MATHEMATICS; NEUTRONS; NUCLEONS; PARTICLE SOURCES; RADIATION SOURCES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS
Optional Information
- Secondary number(s)
- CONF-931160--.