Consequence of using LEU fuel on the effectiveness of the absorber system of the German FRJ-2 research reactor
Creators
- 1. Research Center Juelich, Leo-Brandt-Strasse, 52428 Juelich (Germany)
Description
Effectiveness and behavior of the absorber system are of particular significance for the optimum and safe operation of the FRJ-2 research reactor. Due to safety considerations high amount of shutdown reactivity is required at any operating state of the reactor. In case of the use of LEU fuel elements, the effectiveness of the absorber system is considerably influenced depending on loading and mass of U 235, respectively. The effect of the core loading on the behavior of the shutdown system of FRJ-2 was investigated in the framework of the core conversion study using the coupled code system MCNP and BURN. The analysis revealed that in the case of a LEU core with the same thermal power, the loading of the fissile uranium has to be increased by 27%. Due to the high amount of U-238, the thermal flux in the LEU core is reduced and the neutron spectrum becomes harder than in a HEU core. The consequence of changes in neutron flux and spectrum is a reduction of the effectiveness of the absorber systems by an amount of about 15%. Parallel to the loss of effectiveness, the amount of reactivity being needed for the shutdown of the reactor as well as the excess reactivity which is required for the whole operating cycle is reduced so that significant consequences are not expected on the safety of the reactor at any operating state. (author)
Additional details
Publishing Information
- Imprint Title
- ENS RRFM 2003. Transactions
- Imprint Pagination
- p. 119-123
- Report number
- INIS-XA--652
Conference
- Title
- 7. international topical meeting on research reactor fuel management
- Dates
- 9-12 Mar 2003
- Place
- Aix-en-Provence (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34073924
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; B CODES; BURNUP; FRJ-2 REACTOR; HIGHLY ENRICHED URANIUM; M CODES; MONTE CARLO METHOD; NEUTRON ABSORBERS; NEUTRON FLUX; NEUTRON SPECTRA; REACTIVITY WORTHS; REACTOR CONTROL SYSTEMS; REACTOR SHUTDOWN; SLIGHTLY ENRICHED URANIUM
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; COMPUTER CODES; CONTROL SYSTEMS; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; METALS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SHUTDOWN; SPECTRA; TANK TYPE REACTORS; URANIUM
Optional Information
- Notes
- 4 refs., 4 figs., 1 tab.