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Sugino, Kazuteru; Iwai, Takehiko*
Proceedings of American Nuclear Society Topical Meeting on Physics of Reactors (PHYSOR 2006) (CD-ROM), 10 Pages, 2006/09
MONJU experimental data analysis was performed by using the detailed calculation scheme for fast reactor cores in Japan. Subsequently, feasibility of MONJU integral data was evaluated by cross-section adjustment technique for the use of FBR nuclear core design. It is concluded that MONJU integral data is quite valuable for building up the standard data base for large FBR nuclear core design. In addition, it is found that the application of the updated data base has a possibility to remarkably improve the prediction accuracy of neutronic parameters for MONJU.
Hazama, Taira; Shono, Akira*; Yokoyama, Kenji
Proceedings of American Nuclear Society Topical Meeting on Physics of Reactors (PHYSOR 2006) (CD-ROM), 10 Pages, 2006/09
Benchmark data have been created on reactor physics experiments performed in two reactors: the experimental fast reactor JOYO MK-I and Deuterium Critical Assembly (DCA). The data were prepared for the International Reactor Physics Experiment Evaluation Project (IRPhEP). In JOYO data, five kinds of reactivity data were evaluated: (1)criticality, (2)control rod worth, (3)sodium void reactivity, (4)fuel replacement reactivity, and (5)isothermal temperature coefficient. In particular, the control rod worth, a key quantity in all the reactivity evaluations, were evaluated in detail, considering interaction effects. In DCA data, three kinds of parameters were evaluated: (1)critical moderator level, (2)epithermal capture ratio of 
U, (3)dysprosium thermal reaction rate distribution in a fuel assembly. Data are systematically arranged in eight kinds of core configurations, varying the assembly pitch and void fraction. Each of evaluated data has a unique feature and will be useful to validate reactor physics calculation schemes.
Roque, B.*; Gregg, R.*; Kilger, R.*; Laugier, F.*; Marimbeau, P.*; Ranta-Aho, A.*; Riffard, C.*; Suyama, Kenya; Thro, J. F.*; Yudkevich, M.*; et al.
Proceedings of American Nuclear Society Topical Meeting on Physics of Reactors (PHYSOR 2006) (CD-ROM), 10 Pages, 2006/09
This paper presents the results from the first phase of an international depletion calculations comparison devoted to UOx fuel cycle issues. This "benchmark" has been defined within the NEA/OECD Working Party on Scientific Issues in Reactors Systems (WPRS). The aim is to investigate a large range of isotopes, physics quantities applied to fuel and back-end cycle configurations. The results analyses have shown that there is a good agreement between participants for the mass calculation of many isotopes. In this benchmark, the poorest agreement is obtained in calculating activation products originating from fuel impurities. Some discrepancies on neutron emission rates were also observed, mainly due to the discrepancies on masses calculations. Good agreement was obtained for the total decay heat calculation.
Yoshikawa, Takamichi*; Iwasaki, Tomohiko*; Wada, Kotaro*; Suyama, Kenya
Proceedings of American Nuclear Society Topical Meeting on Physics of Reactors (PHYSOR 2006) (CD-ROM), 8 Pages, 2006/09
To examine the procedures of the reprocessing, the vitrification and the geologic disposal, precise burn-up calculation for high burn-up and MOX fuels has been performed for not only PWR but also BWR by using SWAT and SWAT2 codes which are the integrated burn-up calculation code systems combined with the burn-up calculation code, ORIGEN2, and the transport calculation code, SRAC (the collision probability method) or MVP (the continuous energy Monte Carlo method), respectively. The calculation results shows that all of the evaluated items (heat generation and concentrations of Mo and Pt) largely increase and those significantly effect to the current procedures of the vitrification and the geologic disposal. The calculation result by SWAT2 confirms that the bundle calculation is required for BWR to be discussed about those effects in details, especially for the MOX fuel.
Shibata, Keiichi; Nakagawa, Tsuneo; Iwamoto, Osamu; Ichihara, Akira; Iwamoto, Nobuyuki; Kunieda, Satoshi; Fukahori, Tokio; Otsuka, Naohiko; Katakura, Junichi
Proceedings of American Nuclear Society Topical Meeting on Physics of Reactors (PHYSOR 2006) (CD-ROM), 10 Pages, 2006/09
no abstracts in English
Sekine, Takashi; David, W.*; Aoyama, Takafumi
no journal, ,
This study describes methods for performing whole-core detailed energy deposition calculations for the "JOYO" MK-III core using MCNP and compares MCNP results with core management method results for deposited power, total flux, and fast flux by subassembly. Methods include heterogeneous geometry modeling with prescriptions to account for the generation, transport, and eventual deposition of the prompt and delayed neutron, 
ray, and charged particle energy contributions. Sensitivity of the calculated values to the nuclear data was evaluated by comparing results with cross section libraries based on the nuclear data sets ENDF/B-VI, JENDL-3.3, and JENDL-3.2.