Published 1985
| Version v1
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Reexamination of 2200 meter/second cross section experiments for neutron capture and fission standards
Description
Neutron capture and fission reaction cross sections are usually measured relative to a standard basis. The most common absolute cross sections which are used in the thermal neutron energy region are 197Au and 59Co for capture reactions and 235U and 239Pu for fission reactions. Values for these four cross sections have been compiled and evaluated for the purpose of recommending standard values. 24 refs., 5 tabs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE86001191.Files
17024112.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- BNL-NCS--36965
Conference
- Title
- 33. IUPAC general assembly.
- Dates
- 30 Aug - 7 Sep 1985.
- Place
- Lyon (France).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17024112
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BREIT-WIGNER FORMULA; CAPTURE; COBALT 59 TARGET; CROSS SECTIONS; EVALUATED DATA; GOLD 197 TARGET; ISOMERIC NUCLEI; NEUTRON REACTIONS; PLUTONIUM 239 TARGET; THERMAL FISSION; THERMAL NEUTRONS; URANIUM 235 TARGET
- Descriptors DEC
- BARYON REACTIONS; BARYONS; DATA; ELEMENTARY PARTICLES; FERMIONS; FISSION; HADRON REACTIONS; HADRONS; INFORMATION; NEUTRONS; NUCLEAR REACTIONS; NUCLEI; NUCLEON REACTIONS; NUCLEONS; NUMERICAL DATA; TARGETS
Optional Information
- Secondary number(s)
- CONF-8508138--3.