Refine your search:     
Report No.
 - 
Search Results: Records 1-6 displayed on this page of 6
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Experimental evaluation of release and transport behavior of gaseous ruthenium under boiling accident in reprocessing plant

Yoshida, Naoki; Tashiro, Shinsuke; Amano, Yuki; Yoshida, Kazuo; Yamane, Yuichi; Abe, Hitoshi

NEA/CSNI/R(2017)12/ADD1 (Internet), p.293 - 305, 2018/01

The "Evaporation to Dryness due to the Loss of Cooling Functions" (EDLCF) of highly-active liquid waste (HALW) was newly defined as one of the severe accidents in Japan's nuclear safety standard for the reprocessing plant. Studies on accident scenarios and their source terms have led to an increased need for the development of accident management measures and the assessment of their effectiveness. Previous studies have shown that ruthenium was released at a greater rate than other elements because it formed volatile species such as ruthenium tetroxide (RuO4). In addition, ruthenium isotopes, 106Ru and 103Ru, have radiotoxicity. Accordingly, the accident management measures require the experimental information on the release and transport behavior of the gaseous ruthenium (Ru(g)). This paper summarizes our experimental results on the characteristics of Ru(g) in the EDLCF. This work includes the results of the experiments carried out under the agreement among JAEA, Japan Nuclear Fuel Ltd. and Japan Nuclear Energy Safety Organization.

JAEA Reports

Evaluation of accuracy of Monte Carlo code MVP with VHTRC experiments; Multiplication factor at criticality, burnable poison worth and void worth

Nojiri, Naoki; Yamashita, Kiyonobu; Fujimoto, Nozomu; Nakano, Masaaki*; Yamane, Tsuyoshi; Akino, Fujiyoshi

JAERI-Tech 97-060, 34 Pages, 1997/11

JAERI-Tech-97-060.pdf:1.08MB

no abstracts in English

Journal Articles

Evaluation of the high temperature engineering test reactor's first criticality with Monte Carlo code

Yamashita, Kiyonobu; Ando, Hiroei; Nojiri, Naoki; Fujimoto, Nozomu; Nakata, Tetsuo*; Watanabe, Takashi*; Yamane, Tsuyoshi; Nakano, Masaaki*

Proc. of SARATOGA 1997, 2, p.1557 - 1566, 1997/00

no abstracts in English

Oral presentation

Study of removal technique and confirmation technique of removal condition in heavy water withdraw and tritium removal for decommissioning of FUGEN

Kadowaki, Haruhiko; Matsuo, Hidehiko; Yamane, Naoki; Matsushima, Akira

no journal, , 

no abstracts in English

Oral presentation

A Tritium removal for the decommissioning of FUGEN, 1; Applicability of the tritium removal technique for the actual equipment and pipe

Ando, Koji; Kadowaki, Haruhiko; Matsuo, Hidehiko; Yamane, Naoki; Matsushima, Akira

no journal, , 

no abstracts in English

Oral presentation

Tritium removal of FUGEN using a compact portable dehumidifier system of hollow fiber membrane separation, 2; Verification test of applicability

Kadowaki, Haruhiko; Matsuo, Hidehiko; Yamane, Naoki; Asakura, Yamato*; Matsushima, Akira

no journal, , 

no abstracts in English

6 (Records 1-6 displayed on this page)
  • 1