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JAEA Reports

Corroborative tests for Oarai Waste Reduction Treatment Facility using the in-can type high frequency induction heating method

Sakauchi, Hitoshi; Sato, Isamu*; Donomae, Yasushi; Kitamura, Ryoichi

JAEA-Technology 2015-059, 352 Pages, 2016/03

JAEA-Technology-2015-059.pdf:51.53MB

OWTF (Oarai Waste Reduction Treatment Facility) is constructed for volume reduction processing and stabilization treatment of $$alpha$$ solid waste, which was generated from hot facilities in Oarai Research and Develop Center of Japan Atomic Energy Agency, using in-can type high frequency induction heating by remote control. This report describes corroborative tests, in which incinerating and melting performance for OWTF is confirmed with a full-scale testing furnace. We have been carrying out the tests of incinerating and melting treatment with some kinds of simulated wastes, such as enclosure form of radioactive wastes, material and articles.

Journal Articles

Characterization of 50L-scale solidified products yielded by melting treatment of miscellaneous solid wastes and evaluation of radioisotope tracer distribution

Nakashio, Nobuyuki; Nakashima, Mikio; Hirabayashi, Takakuni*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(3), p.279 - 287, 2004/09

Large-scale melting tests of simulated miscellaneous solid wastes were conducted to characterize solidified products (50L-drum size). Two heating modes were adopted in the tests: hybrid heating and induction heating modes. In the former, wastes were heated with both an induction furnace and a plasma torch, and in the latter, an electrically-conductive crucible was used with the induction furnace. Visual observation, chemical analysis and radioactivity measurements were conducted to the solidified products. It was found that the radioisotope distribution of solidified products was almost homogeneous. There was no remarkable deterioration in the solidified products subsequent to the leaching test.

JAEA Reports

Operatioin and maintenance manuals for VEGA apparatus on radionuclide release from irradiated fuel

Hayashida, Retsu*; Hidaka, Akihide; Nakamura, Takehiko; Kudo, Tamotsu; Otomo, Takashi; Uetsuka, Hiroshi

JAERI-Tech 2001-029, 161 Pages, 2001/03

JAERI-Tech-2001-029.pdf:9.33MB

no abstracts in English

Journal Articles

Current status of VEGA program

Hidaka, Akihide; Nakamura, Takehiko; Nishino, Yasuharu; Kanazawa, Hiroyuki; Hashimoto, Kazuichiro; Harada, Yuhei; Kudo, Tamotsu; Uetsuka, Hiroshi; Sugimoto, Jun

JAERI-Conf 99-005, p.211 - 218, 1999/07

no abstracts in English

JAEA Reports

None

Ouchi, Jin; ; Kawamura, Kazuhiro

PNC TN8440 95-044, 148 Pages, 1995/10

PNC-TN8440-95-044.pdf:6.06MB

None

Journal Articles

Experimental and analytical study on thermal fracture stress of carbon-based materials

Proc. of the First Int. Symp. on Thermal Stresses and Related Topics (Thermal Stresses 95), 0, p.99 - 102, 1995/00

no abstracts in English

Journal Articles

Research and development of toroidal field coils in th JAERI lorge tokamak JT-60

Okubo, Minoru; ; ; ; ; ; *; *; *

Nihon Genshiryoku Gakkai-Shi, 20(3), p.195 - 206, 1978/03

 Times Cited Count:3

no abstracts in English

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 5; Technical development of fuel heating under a multiple of atmosphere

Hirosawa, Takashi; Sato, Isamu; Tanaka, Kosuke; Osaka, Masahiko; Koyama, Shinichi; Tokoro, Daishiro*; Ishigamori, Toshio*; Seki, Takayuki*

no journal, , 

In order to demonstrate severe accident condition on BWR, FP gas release test device was alternated to be used under oxidizing atmosphere. As a result, it is confirmed that the oxidation reaction of tungsten part was inhibited under high temperature.

Oral presentation

Fundamental experiment on the U-Zr-Gd-O molten corium solidification behavior

Sudo, Ayako; Poznyak, I.*; Nagae, Yuji; Nakagiri, Toshio; Kurata, Masaki

no journal, , 

no abstracts in English

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