Release Characteristics of Ruthenium from Highly Active Liquid Waste in Drying Step

Author:

TASHIRO Shinsuke1,AMANO Yuki1,YOSHIDA Kazuo1,YAMANE Yuichi1,UCHIYAMA Gunzo1,ABE Hitoshi1

Affiliation:

1. Nuclear Safety Research Center, Japan Atomic Energy Agency

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference12 articles.

1. 1) K. Yoshida, Thermal-Hydraulic Analysis of Boiling Event of Reprocessed Liquid Wastes with MELCOR Code, JAEA-Research 2012-026 (2012), [in Japanese].

2. 2) H. Igarashi, K. Kato, T. Takahashi, “Effect of calcining temperature on volatilization of ruthenium in batch calcination of simulated high-level liquid waste,” Radiochim. Acta, 60, 143-148 (1993).

3. 3) M. Philippe, J. P. Mercier, J. P. Gue, “Behavior of ruthenium in the case of shutdown of the cooling system of HLLW storage tanks,” Proc. 21st DOE/NRC Nuclear Air Cleaning Conference, San Diego, CA (USA), 13-16 Aug., 1990, NUREG/CP-0116-Vol. 2, p. 831-843; CEA-CONF-10424 (1991).

4. 4) J. Ishikawa, K. Kido, K. Yoshida, “Development of simulation tool for boiling event of reprocessed radioactive liquid waste,” Tran. At. Energy Soc. Jpn., 12[2], 165-174 (2013), [in Japanese].

5. 5) R. O. Gauntt, R. K. Cole, C. M. Erickson et al., MELCOR Computer Code Manuals, Vol. 2: Reference Manuals, Version 1.8.5 May 2000, NUREG/CR-6119, Vol. 2, Rev. 2, SAND2000-2417/2 (2000).

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