Behaviour of IPG waste forms bearing BaSO as the dominant sludge constituent generated from the treatment of water used for cooling the stricken power reactors

Amamoto, Ippei; Kobayashi, Hidekazu; Yokozawa, Takuma; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*

Proceedings of 15th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2013) (CD-ROM), 8 Pages, 2013/09

The great amount of water used for cooling the stricken power reactors at Fukushima Dai-ichi has resulted in accumulation of "remaining water". As the remaining water is subsequently contaminated by FPs, etc., it is necessary to decontaminate it in order to reduce the volume of liquid radioactive waste and to reuse it again for cooling the reactors. Various techniques are being applied to remove FP, etc. and to make stable waste forms. One of the methods using the iron phosphate glass as a medium is being developed to stabilize the strontium-bearing sludge whose main component is BaSO. From the results hitherto, the iron phosphate glass is regarded as a potential medium for the target sludge.

None

; ; Koakutsu, Masayuki; ; Miyamoto, Yasuaki; Takeda, Seiichiro

Saikuru Kiko Giho, (16), 37- Pages, 2002/00

https://rdreview.jaea.go.jp/gihou/pdf2/n16-04.pdf

None

Development of computer code for calculating radionuclide inventory of vitrified high-level waste; Research report on solidification of high-level liquid waste

; ; Kawamura, Kazuhiro

PNC TN8410 97-265, 65 Pages, 1997/07

PNC-TN8410-97-265.pdf:1.22MB

The computer code for calculating the radionuclide inventory of vitrified high-level waste was designed by using the ORIGEN2 computer code, record of nuclear spent fuel, and process control data of high-level liquid waste, etc. This report describes the designed system and the programmed prototype that calculates radionuclide inventory in the HLLW storage tanks in the Tokai Reprocessing Plant(TRP). The purpose of the code is to calculate radionuclide inventory in vitrified high-level waste, for example Cs, Tc, etc. These are important radionuclides for the performance assessment of radioactive waste disposal system, but it is difficult to analyze these nuclides in TRP. The code calculates radionuclide inventory in the HLLW storage tanks by using calculation results of radionuclide inventory in the nuclear spent fuel and the storage record of high-level liquid waste. And the code calculates the radionuclide inventory in the vitrified high-level waste by using the vitrification process control data in the Tokai Vitrification Facility (TVF).Furthermore the code calculates the radioactive decay at any stage of storage, transportation, and disposal of vitrified high-level waste by using the ORIGEN2 computer code.

None

PNC TN8410 89-064, 90 Pages, 1989/11

PNC-TN8410-89-064.pdf:4.25MB

None

Developments in the treatment and disposal of plutonium-contaminated wastes (Annual report in FY-1986)

; ; Kagawa, Akio; ; ; Ouchi, Jin; ;

PNC TN8410 88-044, 75 Pages, 1988/09

PNC-TN8410-88-044.pdf:4.15MB

None

Development of the long-life vitrification melter, 2; Temperature dependence on corrosion behavior of the refractory materials

Miura, Akihiko; Kato, Junya; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*

no journal, , 

no abstracts in English

Development of simulation system for vitrification melter, 1; Design and models newly applied in the simulation system

Nakajima, Masayoshi; Miura, Akihiko; Yamashita, Teruo; Sakai, Takaaki; Shiotsuki, Masao; Kawahara, Hitoshi*; Sato, Akihiro*

no journal, , 

no abstracts in English

Development of long-life vitrification melter, 13; Evaluation of temperature distribution of the melter

Yamashita, Teruo; Masaki, Toshio; Kojima, Keizo; Shiotsuki, Masao; Ito, Toshiyuki*; Ono, Isamu*; Matsumoto, Shiro*

no journal, , 

no abstracts in English

Development of the long-life vitrification melter, 9; Life estimation of refractory materials installed in vitrification melter

Kato, Junya; Miura, Akihiko; Yamashita, Teruo; Shiotsuki, Masao

no journal, , 

no abstracts in English

Development of long-life vitrification melter, 5; Characterization of vitrified waste

Sasage, Kenichi; Miyauchi, Atsushi; Morikawa, Yo; Yamashita, Teruo; Shiotsuki, Masao

no journal, , 

Viscosity and specific resistivity of simulated waste glass was measured to investigate characterization of waste glass processed by the long-life vitrification melter. The composition of the simulated waste glass was varied based on 8 cases of assumed spent fuel conditions and reprocessing flows including reprocessing of FBR fuel with minor actinides separation. The viscosity of the sample glasses was from 0.5 to 1.8 times that of waste glass with standard composition. The specific resistivity of the sample glasses was from 0.5 to 1.5 times that of standard waste glass.