Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
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.