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Journal Articles

Comparison of JSFR design with EDF requirements for future SFR

Uematsu, Mari Mariannu; Pr$`e$le, G.*; Mariteau, P.*; Sauvage, J.-F.*; Hayafune, Hiroki; Chikazawa, Yoshitaka

Journal of Nuclear Science and Technology, 52(3), p.434 - 447, 2015/03

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Electricite de France (EDF) and JAEA have signed a bilateral agreement for research and development cooperation and information exchange on future sodium-cooled fast reactors (SFR) since 2008. Within the bilateral framework, a comparison of Japan sodium-cooled fast reactor (JSFR) design with future French SFR concept has been done based on, firstly the requirement of the investor operator (EDF) of future French SFRs and secondly the French safety baseline that could be applicable to these reactors which is currently under preparation. This paper describes the comparison work results of JSFR and EDF requirements for future SFRs where the specific designs of JSFR were evaluated as interesting from EDF point of view. The comparison work pointed out the differences in safety baselines between two countries as well.

Journal Articles

Effects of nuclear data library and ultra-fine group calculation for large size sodium-cooled fast reactor OECD benchmarks

Kugo, Teruhiko; Sugino, Kazuteru; Uematsu, Mari Mariannu; Numata, Kazuyuki*

Proceedings of International Conference on the Physics of Reactors; The Role of Reactor Physics toward a Sustainable Future (PHYSOR 2014) (CD-ROM), 12 Pages, 2014/09

The present paper summarizes calculation results for an international benchmark proposed under the framework of the Working Party on scientific issues of Reactor Systems (WPRS) of the Nuclear Energy Agency of the OECD. It focuses on the large size oxide-fueled SFR. Library effect for core performance characteristics and reactivity feedback coefficients is analyzed using sensitivity analysis. The effect of ultra-fine energy group calculation in effective cross section generation is also analyzed. The discrepancy is about 0.4% for a neutron multiplication factor by changing JENDL-4.0 with JEFF-3.1. That is about -0.1% by changing JENDL-4.0 with ENDF/B-VII.1. The main contributions to the discrepancy between JENDL-4.0 and ENDF/B-VII.1 are $$^{240}$$Pu capture, $$^{238}$$U inelastic scattering and $$^{239}$$Pu fission. Those to the discrepancy between JENDL-4.0 and JEFF-3.1 are $$^{23}$$Na inelastic scattering, $$^{56}$$Fe inelastic scattering, $$^{238}$$Pu fission, $$^{240}$$Pu capture, $$^{240}$$Pu fission, $$^{238}$$U inelastic scattering, $$^{239}$$Pu fission and $$^{239}$$Pu nu-value. As for the sodium void reactivity, JEFF-3.1 and ENDF/B-VII.1 underestimate by about 8% compared with JENDL-4.0. The main contributions to the discrepancy between JENDL-4.0 and ENDF/B-VII.1 are $$^{23}$$Na elastic scattering, $$^{23}$$Na inelastic scattering and $$^{239}$$Pu fission. That to the discrepancy between JENDL-4.0 and JEFF-3.1 is $$^{23}$$Na inelastic scattering. The ultra-fine energy group calculation increases the sodium void reactivity by 2%.

Journal Articles

Evaluation of OECD/NEA/WPRS benchmark on medium size metallic core SRF by deterministic code system; MARBLE and Monte Carlo code: MVP

Uematsu, Mari Mariannu; Kugo, Teruhiko; Numata, Kazuyuki*

Proceedings of International Conference on the Physics of Reactors; The Role of Reactor Physics toward a Sustainable Future (PHYSOR 2014) (CD-ROM), 15 Pages, 2014/09

In the frame work of the working party on reactor and system (WPRS) of the OECD/NEA, the benchmark on SFR was conducted. Within the OECD/NEA/WPRS benchmark, study on medium size metallic fuel core was performed using a code system for fast reactor core calculation with deterministic method MARBLE and with a Monte Carlo method MVP. The latest nuclear library JENDL-4.0 is used for evaluation of eigenvalues (k$$_{rm eff}$$) and reactivity (sodium void, Doppler and control rod worth) calculations. Depletion calculations are conducted using MARBLE/BURNUP with deterministic method for flux calculation and MVP-BURN with Monte Carlo method. The analysis results and discrepancies between different analysis methods are summarized in this paper. Sensibility studies of eigenvalue and sodium void reactivity of the medium size metallic fuel benchmark core are also conducted to determine the main reactions contributing to the difference between JENDL-4.0 and other libraries JEFF-3.1 and ENDF/B-VII.

Journal Articles

Evaluation of large 3600 MWth sodium-cooled fast reactor OECD neutronic benchmarks

Buiron, L.*; Rimpault, G*; Fontaine, B.*; Kim, T. K.*; Stauff, N. E.*; Taiwo, T. A.*; Yamaji, Akifumi*; Gulliford, J.*; Fridmann, E.*; Pataki, I.*; et al.

Proceedings of International Conference on the Physics of Reactors; The Role of Reactor Physics toward a Sustainable Future (PHYSOR 2014) (CD-ROM), 16 Pages, 2014/09

Within the activities of the Working Party on Scientific Issues of Reactor Systems (WPRS) of the OECD, an international collaboration is ongoing on the neutronic analyses of several Generation-IV Sodium-cooled Fast Reactor (SFR) concepts. This paper summarizes the results obtained by participants from institutions of different countries (ANL, CEA, ENEA, HZDR, JAEA, CER, KIT, UIUC) for the large core numerical benchmarks. These results have been obtained using different calculation methods and analysis tools to estimate the core reactivity and isotopic composition evolution, neutronic feedbacks and power distribution. For the different core concepts analyzed, a satisfactory agreement was obtained between participants despite the different calculation schemes used. A good agreement was generally obtained when comparing compositions after burnup, the delayed neutron fraction, the Doppler coefficient, and the sodium void worth. However, some noticeable discrepancies between the k-effective values were observed and are explained in this paper. These are mostly due to the different neutronic libraries employed (JEFF3.1, ENDFB7.0 or JENDL-4.0) and to a lesser extent the calculations methods.

JAEA Reports

Fuel and core design studies on metal fuel sodium-cooled fast reactor (4), (5) and (6); Joint research report for JFY2009 - 2012

Uematsu, Mari Mariannu; Sugino, Kazuteru; Kawashima, Katsuyuki; Okano, Yasushi; Yamaji, Akifumi; Naganuma, Masayuki; Oki, Shigeo; Okubo, Tsutomu; Ota, Hirokazu*; Ogata, Takanari*; et al.

JAEA-Research 2012-041, 126 Pages, 2013/02

JAEA-Research-2012-041.pdf:16.49MB

The characteristics of sodium-cooled metal fuel core compared to MOX fuel core are given by its higher heavy metal density and superior neutron economy. By taking advantage of these characteristics and allowing flexibility in metal fuel specification and core design conditions as sodium void reactivity and bundle pressure drop, core design with high burnup, high breeding ratio and low fuel inventory features will be achievable. On ground of the major achievements in metal fuels utilization as driver fuels in sodium fast reactors in U.S., the metal fuel core concept is selected as a possible alternative of MOX fuel core concept in FaCT project. This report describes the following items as a result of the joint study on "Reactor core and fuel design of metal fuel core of sodium-cooled fast reactor" conducted by JAEA and CRIEPI during 4 years from fiscal year 2009 to 2012.

Journal Articles

Comparison of JSFR design with EDF requirements for future SFR

Uematsu, Mari Mariannu; Pr$`e$le, G.*; Mariteau, P.*; Sauvage, J.-F.*; Hayafune, Hiroki; Chikazawa, Yoshitaka

Proceedings of 2012 International Congress on Advances in Nuclear Power Plants (ICAPP '12) (CD-ROM), p.836 - 849, 2012/06

EDF and JAEA have signed a bilateral agreement for research and development cooperation and information exchange on future sodium-cooled fast reactors (SFR) since 2008. Within the bilateral framework, a comparison of Japan Sodium-cooled Fast Reactor (JSFR) design with future French SFR concept has been done based on the requirement of EDF, the investor-operator of future French SFR, and the French safety baseline, under the framework of EDF-JAEA bilateral agreement of research and development cooperation on future SFR. The specific designs of JSFR were evaluated as interesting from EDF point of view. The comparison work pointed out the differences in safety baselines between two countries as well.

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