Completion of solidification and stabilization for Pu nitrate solution to reduce potential risks at Tokai Reprocessing Plant

Mukai, Yasunobu; Nakamichi, Hideo; Kobayashi, Daisuke; Nishimura, Kazuaki; Fujisaku, Sakae; Tanaka, Hideki; Isomae, Hidemi; Nakamura, Hironobu; Kurita, Tsutomu; Iida, Masayoshi*; et al.

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8 Pages, 2017/04

TRP has stored the plutonium in solution state for long-term since the last PCDF operation in 2007 was finished. After the great east Japan earthquake in 2011, JAEA had investigated the risk against potential hazard of these solutions which might lead to make hydrogen explosion and/or boiling of the solution accidents with the release of radioactive materials to the public when blackout. To reduce the risk for storing Pu solution (about 640 kg Pu), JAEA planned to perform the process operation for the solidification and stabilization of the solution by converted into MOX powder at PCDF in 2013. In order to perform PCDF operation without adaption of new safety regulation, JAEA conducted several safety measures such as emergency safety countermeasures, necessary security and safeguards (3S) measures with understanding of NRA. As a result, the PCDF operation had stared on 28th April, 2014, and successfully completed to convert MOX powder on 3rd August, 2016 for about 2 years as planned.

Electron-beam treatment of PCDD/Fs in the flue gas from a municipal solid waste incinerator

Hirota, Koichi; Hakoda, Teruyuki; Taguchi, Mitsumasa; Takigami, Machiko*; Kojima, Takuji

Proceedings of 9th International Conference on Radiation Curing (RadTech Asia '03) (CD-ROM), 4 Pages, 2003/00

The flue gas from a municipal solid waste incinerator (MSWI) was irradiated with electron beams to destroy polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs). A flue gas of 1,000 m/h N for the irradiation was obtained at 200C from a main gas stream of the MSWI. The decomposition efficiencies of PCDD/Fs were increased with absorbed dose and reached 90% at a dose of 14 kGy. The reaction mechanisim for PCDD/Fs was also considered.

Visualization system on the earth simulator user's guide

Muramatsu, Kazuhiro; Sai, Kazunori*

JAERI-Data/Code 2002-017, 101 Pages, 2002/08

JAERI-Data-Code-2002-017.pdf:5.65MB

A visualization system on the Earth Simulator is developped. The system enables users to see a graphic representation of simulation results on a client terminal simultaneously with them being computed on the Earth Simulator. Moreover, the system makes it possible to change parameters of the calculation and its visualization in the middle of calculation. The graphical user interface of the system is constructed on a Java applet. Consequently, the client only needs a web browser, so it is independent of operating systems. The system consists of a server function, post-processing function and client function. This report describes mainly the usage of the server and post-processing functions.

lrradiation behavior and performance model of nitride fuel

; ;

JNC TN9400 2000-041, 29 Pages, 2000/03

JNC-TN9400-2000-041.pdf:1.18MB

Irradiation behavior and performance models were investigated in order to apply for nitride fuel options in feasibility study on fast breeder reactor and related recycle systems. (1)MechanicaI design of nitride fuel pin: The behaviors of fission gas release (increase of internal Pressure) and fuel-to-cladding chemical interaction (decrease of cladding thickness) are needed to evaluate cumulative damage fraction in case of fuel pin mechanical design. The behaviors of fission gas release and fuel-to-cladding chemical interaction were investigated from the past studies up to high burnuP, since the lower fission gas release in nitride fuel than in oxide fuel could contribute to reduce the plenum volume and result in the shortening of fuel Pin length. (2)Fuel pin smear density: The higher fuel smear density is preferred for the higher fissile density to improve the core characteristic. The behaviors of fuel pellet swelling were investigated from the past studies up to higher burnup, since the larger fuel pellet swelling in nitride fuel than in oxide fuel would restrict high burunp capability due to fuel-cladding mechanical interaction. (3)Compatibility of nitride fuel with high Temperature water: Compatibility of nitride fuel with high temperature water were investigated from the past studies to contribute water cooled fast breeder reactor options.

None

*

PNC TN142 82-01, 45 Pages, 1981/07

PNC-TN142-82-01.pdf:1.0MB
PNC-TN142-82-01REV.pdf:1.3MB

None

R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition, 3-5; Evaluation on tolerance to failure of existing ODS ferritic steel claddings at the accident conditions of fast reactors

Uwaba, Tomoyuki; Yano, Yasuhide; Otsuka, Satoshi; Naganuma, Masayuki; Tanno, Takashi; Oka, Hiroshi; Kato, Shoichi; Kaito, Takeji; Ukai, Shigeharu*; Kimura, Akihiko*; et al.

no journal, , 

no abstracts in English