Numerical analysis of core disruptive accident in a metal-fueled sodium-cooled fast reactor

Yamano, Hidemasa; Tobita, Yoshiharu

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 3 Pages, 2018/11

Based on the event tree analysis, the present numerical analyses investigated the capability of fuel discharge through the one-dimensional single fuel assembly geometry and the two-dimensional geometry of a CRGT channel with neighboring fuel assemblies. The single fuel assembly analyses showed that the fuel blockage formed in the lower shielding region because fuel solidified by contacting with cold sodium in case of no fission gas release. On the assumption that fission gas was released, the molten fuel successfully relocated below the core. The next analyses using the CRGT channel indicated a significant fuel discharge through the CRGT channel. This is because the fuel temperature was still high just after the CRGT wall failure and sodium in the CRGT channel was quickly voided just after the ingress of a small amount of molten fuel.

Experiments and analyses on fuel expansion and bowing reactivity worth in mock-up cores of metallic fueled fast reactors at FCA

Oigawa, Hiroyuki; Iijima, Susumu; *

Journal of Nuclear Science and Technology, 36(10), p.902 - 913, 1999/10

https://doi.org/10.3327/jnst.36.902

no abstracts in English

Measurement and analysis of breeding indices of U capture to Pu fission rate ratios and U capture to U fission rate ratios at fast critical assembly

Sakurai, Takeshi;

JAERI-Research 95-054, 36 Pages, 1995/08

JAERI-Research-95-054.pdf:1.41MB

no abstracts in English

Contribution of higher energy neutrons to Doppler effect of U in metal fueled fast reactor

Oigawa, Hiroyuki

Journal of Nuclear Science and Technology, 28(11), p.1058 - 1060, 1991/11

https://doi.org/10.3327/jnst.28.1058

no abstracts in English