Thermal and hydraulic design of mercury target; Cross flow type

Kaminaga, Masanori; Hino, Ryutaro; *; *; Nakamura, Fumihito*; *

Proc. of 14th Meeting of the Int. Collaboration on Advanced Neutron Sources (ICANS-14), 1, p.269 - 277, 1998/00

no abstracts in English

Advanced thermal reactor "FUGEN"; The Investigation to revise the appendix 10 of the application document for permission of nuclear reactor establishement and amendment

*; *; *

PNC TN3720 88-007, 235 Pages, 1988/03

PNC-TN3720-88-007.pdf:16.69MB

As the irradiation test in developing high-burnup fuels for the ATR, a loading of MOX fuel assembly containing UO-GdO fuel rods to the "FUGEN" is planning. We have analyzed and evaluated the intergrity and the safety of these fuels based on the safety examination guides. The appendix 10 of the application document for permission of nuclear reactor establishment and amendment of the "FUGEN" were revised. The present report describes the results of these investigation refeing to the appendix 10 for LWRs.