Measurements of effective total macroscopic cross sections and effective energy of continuum beam
Description
Two practically useful quantities are introduced in this study to characterize a continuum neutron beam and to describe transmission phenomena of the beam in field of quantitative neutron radiography: an effective energy instead of a peak energy or a mean energy of the spectrum and an effective total macroscopic (ETM) cross section instead of a total macroscopic (TM) cross section defined at the monochromatic energy. The effective energy was evaluated by means of energy dependence of ETM cross section. To realize the method a beam quality indicator (BQI) has been proposed recently. Several effective energies were measured for non-filtered, filtered neutron beams, and outputs of neutron guide tubes in world by the BQI. A thermal neutron beam and three beams modulated by Pb filters with different thicknesses are studied to measure ETM cross sections for various materials and summarized in a table. Validity of the effective energy determined by the BQI is discussed relating with ETM cross sections of materials. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 1997 symposium on nuclear data
- Imprint Pagination
- 372 p.
- Journal Page Range
- p. 264-269
- Report number
- JAERI-Conf--98-003
Conference
- Title
- 1997 symposium on nuclear data
- Dates
- 27-28 Nov 1997
- Place
- Tokai, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 29053518
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ALUMINIUM 27 TARGET; BISMUTH; CROSS SECTIONS; CYCLOTRONS; EXPERIMENTAL DATA; GOLD 197 TARGET; LEAD; MODERATORS; NEUTRON REACTIONS; NEUTRON SOURCES; NEUTRON SPECTRA
- Descriptors DEC
- ACCELERATORS; BARYON REACTIONS; CYCLIC ACCELERATORS; DATA; ELEMENTS; HADRON REACTIONS; INFORMATION; METALS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; PARTICLE SOURCES; RADIATION SOURCES; SPECTRA; TARGETS
Optional Information
- Secondary number(s)
- INDC(JPN)--180/U