Radwaste reduction technology for spent resins

Aizawa, Hideyuki*; Katagiri, Genichi*; Sano, Kazuya; Higashiura, Norikazu

Fuji Denki Homu Peji and Fuji Denki America Sha Homu Peji (Internet), 11 Pages, 2012/04

http://www.americas.fujielectric.com/engineers-room/white-papers

In a nuclear power plant, spent IXR (hereafter called SR), low-level radioactive waste, is produced from water purification systems in association with the operation of the plant. These SR are different in a radioactive concentration depending on purification systems, and SR which is relatively higher in the radioactivity concentration is stored in the nuclear power plant. Stored amounts continue to increase year after year. In Japan, it is planned that SR will be buried in the ground in the future as a "waste solid" which is solidified in a specific metal container. In terms of securing long-term soundness of the waste solids, it is said the solidification of the SR is required after stabilization treatment is performed. Moreover, SR with high radioactivity concentration requires higher disposal expenses; therefore, the reduction of the disposal volume is required in terms of cost-cutting. To realize these requirements, processing technologies are required which satisfy both the volume reduction and stabilization of the SR at once. Fuji Electric is continuing to develop LPOP technology and the equipment (FRR: Fuji Resin Reducer) as technologies to respond to these requirements. LPOP treatment is a technology enabling realization of both volume reduction and stabilization of SR which is low-level radioactive waste. Fuji Electric post the overview of LPOP technology and the results of mineralization of ion exchange resin and solidification tests executed for the purpose of evaluating the effect of LPOP treatment aiming the burial disposal on our website.

Document collection of the 24th Technical Special Committee on Fugen Decommissioning

Otani, Hiroshi; Matsushima, Akira; Mori, Naoto; Kutsuna, Hideki; Higashiura, Norikazu

JAEA-Review 2011-041, 55 Pages, 2012/01

JAEA-Review-2011-041.pdf:6.08MB

In planning and carrying out decommissioning technical development of Fugen, "Technical special committee on Fugen decommissioning", which consists of the members well-informed, is established, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials "Current Situation of Fugen Decommissioning", "Radioactive Corrosion Products Decontamination Experiment with using Heavy Water System Equipment", "Laser Cutting Test on Dust Behavior in Cutting Work in Air", "Preparatory Situation for Operation of Clearance System" of this committee.

Study of LPOP residue on resin mineralization and solidification

Katagiri, Genichi*; Fujisawa, Morio*; Sano, Kazuya; Higashiura, Norikazu

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.125 - 130, 2010/10

https://doi.org/10.1115/ICEM2010-40112

Fuji Electric had developed the low pressure oxygen plasma technology for mild decomposition and mineralization of an organic material such as ion exchange resin. This method is suitable for radioactive spent resin volume/weight reduction and stabilization for final disposal. On this process, the ion-exchange resins are vaporized and decomposed into gas-phase with pyrolysis, and then, they are decomposed and oxidized with low-pressure plasma activity based on oxygen. And this process is achieved under moderate condition for radio active waste. (1) incinerate temperature: 400-700 C (2) low-pressure (low-temperature) plasma condition: 10-50 Pa. From the result of this process, named of LPOP(low pressure oxidation process) by the inductively coupled plasma, we have confirmed that the process is applicable for organic fireproof waste including ion-exchange resin, and found that the used resin treatment performance is the same as cold test.

Radiation activity evaluation for decommissioning of Fugen Nuclear Power Station

Shiratori, Yoshitake; ; Higashiura, Norikazu

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 0 Pages, 2003/00

None

None

Higashiura, Norikazu; ; ;

Donen Giho, (91), p.96 - 99, 1994/09

https://jopss.jaea.go.jp/pdfdata/PNC-TN1340-94-003.pdf

None

Verification tests for clearance monitor at Fugen Decommissioning Engineering Center

Kawagoe, Shinji; Higashiura, Norikazu; Goto, Tetsuo*

no journal, , 

no abstracts in English

Measurement procedure and evaluation on clearance at FUGEN, 3; Evaluation of performance on the clearance monitor

Kawagoe, Shinji; Higashiura, Norikazu; Goto, Tetsuo*

no journal, , 

Measurement procedure and evaluation on clearance at FUGEN. Evaluation of performance on the clearance monitor.

Basic test for making waste package for spent resin disposal, 1; Volume reduction and stabilization process by low pressure oxygen plasma process for spent resin

Mizui, Hiroyuki; Otani, Hiroshi; Higashiura, Norikazu; Onozaki, Kimihiro*; Katagiri, Genichi*; Endo, Nobuyuki*; Ogawa, Hideo*; Kaneda, Yoshihisa*

no journal, , 

The applicable prospect for spent resin disposal including inhibitor was acquired by basic test of using low pressure oxygen plasma method.

放射能評価方法、放射能評価プログラム及び放射能評価装置

山本 耕輔; 川越 慎司; 東浦 則和; 水井 宏之

not registered

JP, 2020-055379  Patent licensing information  Patent publication (In Japanese)

【課題】評価の保守性の観点から放射能濃度を適切に評価することができる放射能評価方法を提供する。 【解決手段】放射能評価方法は、測定対象物の放射能濃度を算定する放射能濃度算定工程(S4)と、放射能濃度の相対誤差σ'Dを算定する誤差算定工程(S5)と、放射能濃度の相対誤差σ'Dに基づく不確定性を考慮して放射能濃度を評価する評価工程(S6)とを含み、誤差算定工程(S5)は、グロス計数率の測定プロセスに起因する複数のグロス誤差を重畳してグロス計数率の誤差σCGを算定するグロス誤差算定工程(S51)と、測定BG計数率の測定プロセス及び推定BG計数率の推定プロセスに起因する複数のBG誤差を重畳して推定BG計数率の誤差σCBGを算定するBG誤差算定工程(S52)と、グロス計数率の誤差σCGと、推定BG計数率の誤差σCBGとに基づいて、正味計数率の相対誤差σ'CNを算定する正味計数率誤差工程(S53)とを含む。