Thermal and intermediate-energy reference neutron flux irradiation facilities development at the Romanian TRIGA Reactor
Creators
- 1. Institute for Nuclear Research - Pitesti, PO Box 78, RO-0300 Pitesti (RO)
- 2. SENDRA Nuclear Technologies, Ltd., Bucharest (RO)
Description
The development of the nuclear energy imposed the knowledge with high accuracy of the neutron characteristics in the nuclear reactors, for control and safety, for the calibration of the equipment working in the neutron fields. In order to standardize the neutron measurements different nuclear facilities, with different neutron characteristics, producing standard neutron fields, were created. The aim of our project is to develop thermal and intermediate energy neutron irradiation facilities at the steady state core of the Romanian TRIGA Reactor. The Romanian TRIGA Reactor is a dual core reactor having a 14 MW steady-state core and a pulsating annular core. The steady-state TRIGA reactor is a pool type reactor, using high-enriched U-ZrH fuel, water moderated and cooled. At present a mixed core, using high-enriched and low-enriched uranium, is operated. The Reactor is under operation since 1979 at the Institute for Nuclear Research, Pitesti. The neutron flux spectrum measurements, performed in TRIGA Reactor thermal column, show some discrepancies due to the contribution of high-energy neutrons (En > 3 MeV). The thermal flux measurements show the presence of a significant epithermal contribution (about 10%). The Cadmium ratio for Gold is below 20. The TRIGA Reactor thermal column is significant smaller than in other similar facilities. Therefore, the graphite thickness around the cavity decreases up to 10 cm on the bottom and upper sides. Also, the presence of the water layout between the graphite cells affects the spectral composition, in comparison with a pure graphite thermal column. By analyzing a few solutions to improve the thermal flux cavity spectral characteristics, we have chosen to move away the central cavity with 14.3 cm from the core (one row of graphite bricks). So we obtained acceptable values for the Cadmium ratio for Gold (> 50) as well as a flux attenuation of about 2 times, in the present configuration. The analysis is based on computational results, obtained also by using the MCNP-4C code. The thermal column reconfiguration will be done in the near future. The spectrum computation for this new configuration does not show significant spectral modifications, as compared with the actual measurement results. The thermal flux cavity and the intermediate-energy reference spectrum irradiation facilities are now operational at the TRIGA Reactor at Pitesti. The computational and measurement program will be continued in order to improve the spectral characterization, to determine the neutron spatial distribution inside the irradiation systems, the gamma dose and the temperature
Availability note (English)
Available from author(s) or Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (RO) or University Politehnica of Bucharest, Splaiul Independentei 313, Sector 6, RO-77206 Bucharest (RO)Additional details
Identifiers
Publishing Information
- Publisher
- Romanian Nuclear Energy Association, AREN
- Imprint Place
- Bucharest (Romania)
- Imprint Title
- Programme of the International Symposium on Nuclear Energy SIEN 2003, Nuclear Power - A New Challenge
- Imprint Pagination
- 606 p.
- Journal Page Range
- p. 395-400
Conference
- Title
- SIEN 2003, International Symposium on Nuclear Energy, Nuclear Power - A New Challenge
- Dates
- 22-25 Oct 2003
- Place
- Bucuresti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 35052654
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACTIVATION DETECTORS; CROSS SECTIONS; INTERMEDIATE NEUTRONS; M CODES; MONTE CARLO METHOD; NEPTUNIUM 237; NEUTRON FLUX; NEUTRON SPECTRA; PLUTONIUM 239; REACTOR CONTROL SYSTEMS; REACTOR EXPERIMENTAL FACILITIES; REACTOR SAFETY; THERMAL COLUMNS; THERMAL NEUTRONS; TRIGA-2-PITESTI REACTOR; URANIUM 235; URANIUM 238
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BARYONS; CALCULATION METHODS; COMPUTER CODES; CONTROL SYSTEMS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FERMIONS; HADRONS; HEAVY NUCLEI; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPE PRODUCTION REACTORS; ISOTOPES; MEASURING INSTRUMENTS; MINUTES LIVING RADIOISOTOPES; NANOSECONDS LIVING RADIOISOTOPES; NEPTUNIUM ISOTOPES; NEUTRON DETECTORS; NEUTRONS; NUCLEI; NUCLEONS; ODD-EVEN NUCLEI; PLUTONIUM ISOTOPES; PULSED REACTORS; RADIATION DETECTORS; RADIATION FLUX; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; SPECTRA; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; TRIGA TYPE REACTORS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 9 refs., 5 figs., 3 tabs.