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Kitada, Takanori*; Okumura, Keisuke; Unesaki, Hironobu*; Saji, Etsuro*
Proceedings of International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004) (CD-ROM), 8 Pages, 2004/04
Burnup calculation benchmark has been carried out for the LWR next generation fuels aiming at high burnup up to 70 GWd/t with UO
and MOX. Based on the submitted results by many benchmark participants, the present status of calculation accuracy has been confirmed for reactor physics parameters of the LWR next generation fuels, and the factors causing the calculation differences were analyzed in detail. Moreover, the future experiments and research subjects necessary to reduce the calculation differences were discussed and proposed.
Suyama, Kenya; Mochizuki, Hiroki*; Okuno, Hiroshi; Miyoshi, Yoshinori
Proceedings of International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004) (CD-ROM), 10 Pages, 2004/04
This paper provides validation results of SWAT2, the revised version of SWAT, which is a code system combining point burnup code ORIGEN2 and continuous energy Monte Carlo code MVP, by the analysis of post irradiation examinations (PIEs). Some isotopes show differences of calculation results between SWAT and SWAT2. However, generally, the differences are smaller than the error of PIE analysis that was reported in previous SWAT validation activity, and improved results are obtained for several important fission product nuclides. This study also includes comparison between an assembly and a single pin cell geometry models.
Tsujimoto, Kazufumi; Sasa, Toshinobu; Nishihara, Kenji; Oigawa, Hiroyuki; Takano, Hideki*
Proceedings of International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004) (CD-ROM), 8 Pages, 2004/04
The Japan Atomic Energy Research Institute (JAERI) is developing an Accelerator Driven System (ADS) for transmutation of nuclear waste such as minor actinide (MA) and long-lived fission product (LLFP). To study and evaluate the feasibility of ADS by physical and engineering viewpoints, the Transmutation Experimental Facility (TEF) is proposed under a framework of J-PARC (Japan Proton Accelerator Research Complex) project. The TEF consists of two facilities named as Transmutation Physics Experimental Facility (TEF-P) and ADS Target Test Facility (TEF-T). The TEF-P consists of a zero-power critical assembly which is operated with a low power proton beam to research the reactor physics and the controllability of ADS. The TEF-T is a facility for material irradiation and partial mockup of beam window which can accept a maximum 600MeV-200kW proton beam into the Pb-Bi eutectic target. The purposes, experimental items and the specifications of the facilities are described.
Chiba, Go; Yokoyama, Kenji; Sekine, Takashi; Maeda, Shigetaka
Proceedings of International Conference on the Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004), 0 Pages, 2004/04
Performance test at low power had been carriod out in the experimental fast reactor JOYO. In the test, several neutronics characteristics had been measured. For the analysis, a deterministic standard calculation route of JNC was adopted and good agreements with the measured values were obtained. We also evaluated a sensitivity of the evaluation method of the self-shielding effect in the reflector subassemblies to the neutronics characteristics and the calculation uncertainty indeced by the uncertainty of cross sections.
Hazama, Taira; Tommasi, J.*
Proceedings of International Conference on the Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004), 95348 Pages, 2004/04
SEFOR (South-West Experimental Fast Oxide Reactor) Doppler reactivity experiment was re-evaluated. The re-evaluation was carried out on the static tests performed at power levels up to 20MW, starting from raw data of the Doppler reactivity and fuel temperature. Investigations are made on various parameters, such as the fuel thermal conductivity and weighting function to obtain core averaged fuel temperature. Experimental uncertainty is also re-evaluated. The re-evaluated Doppler constant is about 10% larger than the original GE evaluation. The increase is brought by the use of the exact weight to consider temperature distribution in the core and the update of fuel thermal conductivity. The new values are more reasonable than the currently recommended values in that C/E values do not depend on the core types.
Shono, Akira; Hazama, Taira; Ishikawa, Makoto; Manturov, G.*
Proceedings of International Conference on the Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004), 95315 Pages, 2004/00
The present paper provides evaluation results of predicted uncertainty on nuclear parameters on the BN-600 hybrid core, a feasible option for Russian surplus weapons plutonium disposition. Covariance of nuclear group constant, analysis error, and experimental error are considered to predict uncertainties of the hybrid core nuclear parameters by applying the nuclear group constant adjustment method. Analysis results of BFS mockup and other fast reactor core experiments were reflected in the evaluation.