Evaluation of covariance data for chromium, iron and nickel contained in JENDL-3.2

S.Oh*; Shibata, Keiichi

Journal of Nuclear Science and Technology, 35(1), p.66 - 75, 1998/01

https://doi.org/10.3327/jnst.35.66

no abstracts in English

Thermo-Hydraulic Dynamics by Release of Molten Fuel in a Fuel Assembly

M.Tezuk*; S.Ohta*; H.Kajiw*

PNC TN251 74-17, 89 Pages, 1974/07

PNC-TN251-74-17.pdf:2.08MB

For the purpose of evaluating the safety and studying the safety measures against accidents in a nuclear reactor core which present serious problems in designing a fast breeder reactor today, analytical evaluation was conducted on the monitoring system as to its feasible conditions and the extent for the monitoring of in-pile irregularities which may be a possible cause for accidents in a fuel assembly. For the target accident for the evaluation of the monitoring system, local release of molten fuel which is assumed to be a cause for channel blockage in a fuel assembly was taken up. The respondency of the flow meter at the outlet to the coolant flow fluctuations by the fuel-sodium interaction, and the respondency of the thermometer at the outlet to the heat trans-mission behavior in a fuel assembly by a heat release from fuel to sodium were studied respectively from the standpoint of safety analysis.