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Journal Articles

Feasibility study of BWR-type reduced-moderation water reactor core design in thermal-hydraulic view point

Araya, Fumimasa; Kureta, Masatoshi; Akimoto, Hajime

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.309 - 314, 2000/00

no abstracts in English