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pro vyhledávání: '"2 of others"'
Autor:
他2名, 2 of others
Publikováno v:
PNC TN8410 89-054.
(目的)高レベル放射性廃液のガラス固化試験及び処分試験に伴いガラス固化体の成分分析法を確率する。 (方法)ガラス固化体中の成分分析を行うたの前処理法として過酸化ナトリウム(N-2O
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::90480e68212bb7b45670274b938f80cb
https://jopss.jaea.go.jp/search/servlet/search?4023450
https://jopss.jaea.go.jp/search/servlet/search?4023450
Publikováno v:
PNC TJ202 83-04.
高速原型炉の設計に必要な材料デ一タを得る目的で、オーステナイト系ステンレス鋼SUS321及びインコネル718の高温強度試験を実施した。供試材は次の4種である。SUS321鍛造材(350t),SUS321伝
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::115bdba9fc76f7013469431668eb7990
https://jopss.jaea.go.jp/search/servlet/search?4013320
https://jopss.jaea.go.jp/search/servlet/search?4013320
Autor:
他2名, 2 of others
Publikováno v:
PNC TN3410 88-025.
The radiation shielding analysis of pressure tube type heavy water reactors was performed using the discrete ordinate transport code, dot 3.5. The present paper describes the analytical methods developed to calculate the dose rates after shutdown in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::71271056ef6a6cb03743b5e76d40ea0e
https://jopss.jaea.go.jp/search/servlet/search?4013137
https://jopss.jaea.go.jp/search/servlet/search?4013137
Publikováno v:
PNC TN3410 88-010.
A study of chemical decontamination of the reactor cooling system of the Fugen has been made with KURIDECON 203, a dilute decontamination reagent. The heat exchangers of the cleanup water system and of the residual heat removal system were decontamin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::7c1b38107fcc3c717dbdcc1b65d3498b
https://jopss.jaea.go.jp/search/servlet/search?4013123
https://jopss.jaea.go.jp/search/servlet/search?4013123