The 14 MeV Neutron Irradiation Facility in MARIA Reactor
Creators
- Prokopowicz, R.1
- Pytel, K.1
- Dorosz, M.1
- Zawadka, A.1
- Lechniak, J.1
- Lipka, M.1
- Marcinkowska, Z.1
- Wierzchnicka, M.1
- Malkiewicz, A.1
- Wilczek, I.1
- Krok, T.1
- Migdal, M.1
- Koziel, A.1
- Institute of Electrical and Electronics Engineers - IEEE, 3 Park Avenue, 17th Floor, New York, N.Y. 10016-5997 (United States)
- 1. MARIA Reactor Operations Division, Reactor Measurement and Analysis Group, National Centre for Nuclear Research, Swierk (Poland)
Description
The MARIA reactor with thermal neutron flux density up to 3x1014 cm-2 s-1 and a number of vertical channels is well suited to material testing by thermal neutron treatment. Beside of that some fast neutron irradiation facilities are operated in MARIA reactor as well. One of them is thermal to 14 MeV neutron converter launched in 2014. It is especially devoted to fusion devices material testing irradiation. The ITER and DEMO research thermonuclear facilities are to be run using the deuterium - tritium fusion reaction. Fast neutrons (of energy approximately 14 MeV) resulting from the reaction are essential to carry away the released thermonuclear energy and to breed tritium. However, constructional materials of which thermonuclear reactors are to be built must be specially selected to survive intense fluxes of fast neutrons. Strong sources of 14 MeV neutrons are needed if research on resistance of candidate materials to such fluxes is to be carried out effectively. Nuclear reactor-based converter capable to convert thermal neutrons into 14 MeV fast neutrons may be used to that purpose. The converter based on two stage nuclear reaction on lithium-6 and deuterium compounds leading to 14 MeV neutron production. The reaction chain is begun by thermal neutron capture by lithium-6 nucleus resulted in triton release. The neutron and triton transport calculations have been therefore carried-out to estimate the thermal to 14 MeV neutron conversion efficiency and optimize converter construction. The usable irradiation space of ca. 60 cm3 has been obtained. The released energy have been calculated. Heat transport has been asses to ensure proper device cooling. A set of thermocouples has been installed in converter to monitor its temperature distribution on-line. Influence of converter on reactor operation has been studied. Safety analyses of steady states and transients have been done. Performed calculations and analyses allow designing the converter and formulate its operation limits and conditions. During first tested operation of the converter the 14 MeV neutron flux density was estimated to 109 cm-2 s-1, whereas fast fission neutrons inside converter achieved 1012 cm-2 s-1, and thermal neutrons were reduced down to 109 cm-2 s-1. Taking into account the feasibility of almost incessant converter operation for a number of months, its arisen as one of the most powerful (in terms of fluence), currently available 14 MeV neutron source. Such a converter currently under operation in the MARIA reactor core will be presented. (authors)
Additional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- ANIMMA--2015-IO-82
Conference
- Title
- 4. International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications
- Acronym
- ANIMMA 2015
- Dates
- 20-24 Apr 2015
- Place
- Lisboa (Portugal)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 47102405
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CALCIUM 60; FAST FISSION; FAST NEUTRONS; FLUX DENSITY; HEAVY ION FUSION REACTIONS; IRRADIATION; IRRADIATION PLANTS; ITER TOKAMAK; LITHIUM 6; MARIA REACTOR; MATERIALS TESTING; MEV RANGE; NEUTRON CONVERTERS; NEUTRON FLUX; SAFETY ANALYSIS; STEADY-STATE CONDITIONS; THERMAL NEUTRONS; THERMOCOUPLES; THERMONUCLEAR REACTIONS; TRITONS
- Descriptors DEC
- ALKALINE EARTH ISOTOPES; BARYON REACTIONS; BARYONS; BERYLLIUM MODERATED REACTORS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCIUM ISOTOPES; CHARGED PARTICLES; CLOSED PLASMA DEVICES; ELEMENTARY PARTICLES; ENERGY RANGE; ENRICHED URANIUM REACTORS; EVEN-EVEN NUCLEI; FERMIONS; FISSION; HADRON REACTIONS; HADRONS; HEAVY ION REACTIONS; INTERMEDIATE MASS NUCLEI; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; ISOTOPES; LIGHT NUCLEI; LITHIUM ISOTOPES; MEASURING INSTRUMENTS; METAL MODERATED REACTORS; NEUTRON REACTIONS; NEUTRONS; NUCLEAR FACILITIES; NUCLEAR REACTIONS; NUCLEI; NUCLEON REACTIONS; NUCLEONS; NUCLEOSYNTHESIS; ODD-ODD NUCLEI; POOL TYPE REACTORS; RADIATION FLUX; RADIOISOTOPES; REACTORS; RESEARCH AND TEST REACTORS; STABLE ISOTOPES; SYNTHESIS; TESTING; THERMAL REACTORS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS