BN-600 hybrid core benchmark analyses
- 1. International Atomic Energy Agency (IAEA), Vienna (Austria)
- 2. ANL (USA)
Description
Benchmark analyses for the hybrid BN-600 reactor that contains three uranium enrichment zones and one plutonium zone in the core, have been performed within the frame of an IAEA sponsored Coordinated Research Project. The results for several relevant reactivity parameters obtained by the participants with their own state-of-the-art basic data and codes, were compared in terms of calculational uncertainty, and their effects on the ULOF transient behavior of the hybrid BN-600 core were evaluated. The comparison of the diffusion and transport results obtained for the homogeneous representation generally shows good agreement for most parameters between the RZ and HEX-Z models. The burnup effect and the heterogeneity effect on most reactivity parameters also show good agreement for the HEX-Z diffusion and transport theory results. A large difference noticed for the sodium and steel density coefficients is mainly due to differences in the spatial coefficient predictions for non fuelled regions. The burnup reactivity loss was evaluated to be 0.025 (4.3 $) within ∼ 5.0% standard deviation. The heterogeneity effect on most reactivity coefficients was estimated to be small. The heterogeneity treatment reduced the control rod worth by 2.3%. The heterogeneity effect on the k-eff and control rod worth appeared to differ strongly depending on the heterogeneity treatment method. A substantial spread noticed for several reactivity coefficients did not give a significant impact on the transient behavior prediction. This result is attributable to compensating effects between several reactivity effects and the specific design of the partially MOX fuelled hybrid core. (author)
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34079854.pdf
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Additional details
Publishing Information
- Imprint Title
- The fourth research co-ordination meeting (RCM) on 'Updated codes and methods to reduce the calculational uncertainties of liquid metal fast reactors reactivity effects'. Working material
- Imprint Pagination
- 444 p.
- Journal Page Range
- p. 107-122
- Report number
- IAEA-RC--803.4
Conference
- Title
- 4. research co-ordination meeting (RCM) on 'Updated codes and methods to reduce the calculational uncertainties of liquid metal fast reactors reactivity effects'
- Dates
- 19-23 May 2003
- Place
- Obninsk (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34079854
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BELOYARSK-3 REACTOR; BENCHMARKS; BURNUP; COMPARATIVE EVALUATIONS; CONTROL ROD WORTHS; COORDINATED RESEARCH PROGRAMS; CYLINDRICAL CONFIGURATION; HETEROGENEOUS REACTOR CORES; IAEA; LOSS OF FLOW; MIXED OXIDE FUELS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; REACTIVITY; REACTIVITY COEFFICIENTS; REACTOR CORES
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; CONFIGURATION; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENERGY SOURCES; EPITHERMAL REACTORS; EQUATIONS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; FUELS; INTERNATIONAL ORGANIZATIONS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; NUCLEAR FUELS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR CORES; REACTOR MATERIALS; REACTORS; RESEARCH PROGRAMS; SODIUM COOLED REACTORS; SOLID FUELS; TRANSPORT THEORY
Optional Information
- Notes
- 16 refs, 7 figs, 6 tabs Imprint:Web site: http://www.iaea.org/inis/aws/fnss/twgfr/working_materials.html
- Secondary number(s)
- TWG-FR--113