Thermodynamic performance tests of the cold neutron source at the reactor KUR
Creators
- 1. Kyoto Univ., Osaka (Japan)
Description
This report described thermodynamic performance tests of the Kyoto University Reactor (KUR) Cold Neutron Source (CNS), which is operated by a closed thermosiphon cooling loop. Close agreement between observed and numerical simulations of the normal operations of the CNS was obtained. Dynamic factors relating to the time-delay caused by the mass transfer in the moderator transfer tube were not considered in those simulations. The authors conclude that time-delaying phenomena due to pressure and flow oscillations in the line are estimated to be negligible in their CNS. The data of TOF spectra showed that the ratio of the fraction of cold neutrons in the cold moderator to that in the ambient moderator is about 20 where the wavelengths are longer than 6 A using liquid hydrogen as a moderator
Additional details
Publishing Information
- Imprint Title
- International workshop on cold neutron sources
- Imprint Pagination
- 666 p.
- Journal Page Range
- p. 593-604.
- Report number
- LA--12146-C
Conference
- Title
- International workshop on cold neutron sources.
- Dates
- 5-8 Mar 1990.
- Place
- Los Alamos, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24006756
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLD NEUTRONS; COMPUTERIZED SIMULATION; COOLING SYSTEMS; DATA; KUR REACTOR; MASS TRANSFER; MODERATORS; NEUTRON SOURCES; NEUTRON SPECTRA; OPERATION; PERFORMANCE TESTING; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; THERMODYNAMICS; TIME DELAY
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; INFORMATION; NEUTRONS; NUCLEONS; PARTICLE SOURCES; POOL TYPE REACTORS; RADIATION SOURCES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SIMULATION; SPECTRA; TESTING; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9003100--.