Angle-integrated neutron emission spectra at 14 MeV for Be, C, F, Mg, Al, Si, V, Fe, Cr, Cu, Pb and Bi
- 1. Osaka Univ., Suita (Japan). Faculty of Engineering
Description
Using measured double differential neutron emission cross sections at 14.1 MeV for 15 to 16 angle-points, angle-integrated neutron emission spectra in the center-of-mass system were deduced for Be, C, F, Mg, Al, Si, V, Fe, Cr, Cu, Pb and Bi. These angle-integrated data are useful to assess partial emission cross sections of elastic, discrete inelastic, continuum inelastic scattering and other reaction channels like (n,2n) given in evaluated nuclear data libraries, e.g., JENDL-3 and ENDF/B-IV. Through comparison between experimental and evaluated emission data, status of JENDL-3T or ENDF/B-IV at 14 MeV has been made clear in this report. Significant improvement has been made by JENDL-3T for most elements except Be and Pb. For Be and Pb, further investigation is needed to improve JENDL-3T. Generally, improvement is needed to reproduce the forward-enhancement of neutron emission in double differential data. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 1987 seminar on nuclear data
- Imprint Pagination
- 519 p.
- Journal Page Range
- p. 279-316.
- Report number
- JAERI-M--88-065
Conference
- Title
- 1987 seminar on nuclear data.
- Dates
- 12-13 Nov 1987.
- Place
- Tokai, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 19086586
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ALUMINIUM; ANGULAR DISTRIBUTION; BERYLLIUM; BISMUTH; CARBON; CHROMIUM; COPPER; DIFFERENTIAL CROSS SECTIONS; ENERGY SPECTRA; EVALUATED DATA; EXPERIMENTAL DATA; FLUORINE; IRON; LEAD; MAGNESIUM; MEV RANGE 10-100; NEUTRON EMISSION; NEUTRON REACTIONS; NUCLEAR DATA COLLECTIONS; SILICON; VANADIUM
- Descriptors DEC
- ALKALINE EARTH METALS; BARYON REACTIONS; CROSS SECTIONS; DATA; DISTRIBUTION; ELEMENTS; EMISSION; ENERGY RANGE; HADRON REACTIONS; HALOGENS; INFORMATION; METALS; MEV RANGE; NONMETALS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; SEMIMETALS; SPECTRA; TRANSITION ELEMENTS
Optional Information
- Secondary number(s)
- NEANDC(J)--127/U; INDC(JPN)--113/L.