Neutron emission from (α,n) reaction in nuclear fuel
Creators
- 1. Nippon Atomic Industry Group Co. Ltd., Kawasaki, Kanagawa. Nuclear Research Lab.
Description
Nuclear fuels emit neutrons originated in spontaneous fission of heavy elements and in (α,n) reactions of light elements contained in the fuel. These neutron emission data are required in the fields of radiation shielding design of various nuclear facilities and non-destructive measurement of nuclear materials concerning with the process control and safeguarding nuclear materials. The requested (α,n) data in these fields are thick target neutron yield and energy spectrum of emitted neutrons. The present status of the experimental data are reviewed briefly. As an example, thick target neutron yield and emitted neutron energy spectrum are calculated for the O-18(α,n)Ne-21 reaction, which is the most significant (α,n) reaction in oxide fuels. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 1986 seminar on nuclear data
- Imprint Pagination
- 371 p.
- Journal Page Range
- p. 14-18.
- Report number
- JAERI-M--87-025
Conference
- Title
- 1986 seminar on nuclear data.
- Dates
- 26-27 Nov 1986.
- Place
- Tokai, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18075395
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALPHA REACTIONS; CROSS SECTIONS; ENERGY SPECTRA; NEON 21; NEUTRON EMISSION; NEUTRON SPECTRA; NEUTRONS; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; OXYGEN 18 TARGET; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; BARYONS; CHALCOGENIDES; ELEMENTARY PARTICLES; EMISSION; ENERGY SOURCES; EVEN-ODD NUCLEI; FERMIONS; FUELS; HADRONS; ISOTOPES; LIGHT NUCLEI; MATERIALS; NEON ISOTOPES; NUCLEAR REACTIONS; NUCLEI; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; SPECTRA; STABLE ISOTOPES; TARGETS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Secondary number(s)
- NEANDC(J)--123/U; INDC(JPN)--109/L.