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JAEA Reports

High radioactive $$alpha$$-$$gamma$$ solid Waste treatment facilities Conceptual design study

; Seki, Sadao*;

PNC TJ9409 91-001, 164 Pages, 1991/02

PNC-TJ9409-91-001.pdf:4.41MB

This report describes the result of conceptual design study concerned with "High Radioactive $$alpha$$-$$gamma$$ Solid Waste Treatment Facilities, "which will be planed for the purpose of volume reduction and stabilization of High Radioactive $$alpha$$-$$gamma$$ solid wastes generated and stocked in the O-arai Engineering Center of PNC. In this conceptual design study the basic process of the facilities, which are sufficient to treat each waste and develop technologies, are clarified. This report consist with: (1)Clarification of waste to be treated. (2)Study on the treatment technology and process. (3)Conceptual design of facilities and equipment. (4)Estimation of construction cost and schedule.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 7; Numerical analysis of temperature rise of solidified waste by radiation applying various container shapes

Hiraki, Yoshihisa; Enomoto, Mayu*; Terasawa, Toshiharu*; Imaizumi, Ken*; Kato, Jun; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Evaluate the maximum temperature of solidified body, when Secondary Waste Produced from Contaminated Water Treatment at Fukushima Daiichi NPP is solidified with cement etc. Simulate various container shapes, and analysis using the radiation transport code and the thermal analysis code was performed. The summary of the test and some of the obtained results are introduced.

Oral presentation

IR cameras detection of corrosion in radioactive waste containers and nuclear fuel material containers assessing; Applicability of non-destructive inspection for internal corrosion

Suzuki, Ryuta; Watanabe, Naoki; Minouchi, Hiroyuki; Fukui, Masahiro

no journal, , 

Feasibility experiments were conducted to develop a novel inspection method for non-destructively detecting corrosion on the inner surfaces of radioactive waste containers (steel drums) and nuclear fuel material containers (stainless steel cans) using active thermography with an infrared camera (IC). The experiments confirmed that a non-cooled IC could detect corrosion with a minimum diameter of approximately 15 mm in steel drums. Regarding stainless steel cans with simulated inner corrosion (10 mm diameter), corrosion was detectable when the outer surface temperature was 5 degrees Celsius and 40 degrees Celsius, but detection became difficult at 70 degrees Celsius.

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