Thermal neutron distribution measurement at core of the LVR-15 reactor - 169
Creators
- 1. Nuclear Research Institute Rez plc, 250 68 Rez (Czech Republic)
Description
The LVR-15 reactor is a light water research type which is situated in Rez near Prague. The maximum thermal power is 10 MW. The LVR-15 reactor is used mostly for irradiation of material specimens for a given period with appropriate neutron fluence rate. It is important for such experiments to know neutron fluence and energy spectrum in the sample. The paper describes measurement of thermal neutron distribution in four vertical channels in core of the LVR-15 reactor. The activation method with Cu foils was used for the measurement. The mean power during the irradiation was 0.1 MW. The gamma activities were measured with spectrometric assembly including the HPGe detector. Nearly all the data were loaded automatically without any manual typing which guarantees the high reliability of final results. The results of the measurement have been compared with data calculated with three computer codes - with a diffusion nodal program NODER in a four group approximation, with the general purpose Monte Carlo radiation transport code MCNP-4B and the DLC-189 library, and with the two-dimensional transport code DORT. The measurement and calculation was applied for reactor core configuration which was specially designed for boron neutron capture therapy experiments in June of 1999. (author)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 12 p.
Conference
- Title
- ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium
- Acronym
- Physor 2000
- Dates
- 7-12 May 2000
- Place
- Pittsburgh, PA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54119192
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON; COMPUTER CODES; DESIGN; DIFFUSION; ENERGY SPECTRA; FOILS; HIGH-PURITY GE DETECTORS; IRRADIATION; LVR-15 REACTOR; MONTE CARLO METHOD; NEUTRON CAPTURE THERAPY; NEUTRON FLUENCE; RADIATION TRANSPORT; REACTOR CORES; THERMAL NEUTRONS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FERMIONS; GE SEMICONDUCTOR DETECTORS; HADRONS; MEASURING INSTRUMENTS; MEDICINE; NEUTRON THERAPY; NEUTRONS; NUCLEAR MEDICINE; NUCLEONS; RADIATION DETECTORS; RADIOLOGY; RADIOTHERAPY; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEMICONDUCTOR DETECTORS; SEMIMETALS; SPECTRA; TANK TYPE REACTORS; THERAPY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWR TYPE REACTORS; ZERO POWER REACTORS
Optional Information
- Notes
- 5 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)