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Journal Articles

Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool

Mascari, F.*; Nakamura, Hideo; Umminger, K.*; De Rosa, F.*; D'Auria, F.*

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.4921 - 4934, 2015/08

JAEA Reports

Analysis of energy deposition and evaluation of maximum load of irradiation capsule for NSRR experiment with uranium-zirconium hydride fuel

Fuketa, Toyoshi; Ishijima, Kiyomi; Tanzawa, Sadamitsu; Nakamura, Takehiko; Sasajima, Hideo; Kashima, Yoichi; ;

JAERI-Research 95-005, 53 Pages, 1995/01

JAERI-Research-95-005.pdf:1.96MB

no abstracts in English

JAEA Reports

Implementation of reactor safety analysis code RELAP5/MOD3 and its vectorization on supercomputer FACOM VP2600

; *; *

JAERI-M 91-051, 70 Pages, 1991/03

JAERI-M-91-051.pdf:1.48MB

no abstracts in English

Journal Articles

Ions in carbon dioxide at atmospheric pressure, 5; Reactions in CO$$_{2}$$-CO-CH$$_{4}$$-H$$_{2}$$O mixtures and coolant chemistry

Ikezoe, Yasumasa; Onuki, Kaoru; Shimizu, Saburo; *; Tagawa, S.*; Tabata, Yoneho*

Radiation Physics and Chemistry, 36(3), p.279 - 284, 1990/00

https://doi.org/10.1016/1359-0197(90)90005-3

no abstracts in English

Journal Articles

Present status of future scope of fusion reactor tech; V.2 Blanket enirronments and material ampatibility

; ; ; *; ; ; Sanokawa, Konomo; ; ; ; et al.

Nihon Genshiryoku Gakkai-Shi, 15(11), p.712 - 758, 1973/11

https://doi.org/10.3327/jaesj.15.712

no abstracts in English

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