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Suzuki, Asuka; Hotoku, Shinobu; Ban, Yasutoshi; Tsutsui, Nao; Tsubata, Yasuhiro; Matsumura, Tatsuro
Proceedings of 5th International Conference on Asian Nuclear Prospects 2016 (ANUP 2016) (CD-ROM), 2 Pages, 2016/10
The Japan Atomic Energy Agency (JAEA) conducts extensive research and development (R&D) activities toward the development of aqueous separation processes for spent nuclear fuel at the Nuclear Fuel Cycle Safety Engineering Research Facility-Back-end Fuel Cycle Key Element Research Facility (NUCEF-BECKY). BECKY is equipped with three hot cells, several glove boxes, and fume hoods. One of the hot cells, called the process cell, contains bench scale spent fuel test equipment used for U, Pu, and other spent fuel material. In this study, we describe an equipment used for aqueous separation processes in the process cell.
*; *; *; *
JNC TJ8400 2000-061, 92 Pages, 2000/03
JNC-TJ8400-2000-061.pdf:8.79MB
Crystallization procedure is considered to have an advantage in recovering rather pure uranium from contaminated uranium solution and to be applicable for a new reprocessing process. It was confirmed until last year that the reprocessing process with crystallization procedure has a sufficient advantage. But the data for Pu crystallization is very rare. although it is necessary for design of the process with crystallization procedure. In this study, a beaker scale plutonium test was performed in AEA Technology Harwell Laboratory to confirm a behavior of Pu (IV) nitrate under crystallization condition. The results were examined by Mitsubishi Materials Corporation. Test item was a measurement of temperature in case of Pu (IV) nitrate crystallization or freezing of the solution in the following six parameters. (Pu(g/L):200, 100, 50, HNO
(m):6, Pu valence:4). (Pu(g/L):200, 100, 50, HNO(m):4, Pu valence:4). Test results were as follows. (1)Pu(IV) nitrate crystallization was not observed even in the case 200g Pu/L and HNO 6M and 4M which were considered to the best condition but crystal of H
O and HNO 
3HO were observed. (2)Similar results were obtained for the other parameter with lower Pu concentration. (3)We can estimate that Pu(IV) nitrate crystallization will not occurred in the reprocessing process with crystallization procedure. (4)The solubility data of Pu(NO)
- HNO-HO system was obtained.
*; Arai, Tsuyoshi*; Kumagai, Mikio*
JNC TJ9400 2000-002, 80 Pages, 2000/02
JNC-TJ9400-2000-002.pdf:4.67MB
In order to develop an economically efficient wet separation process other than solvent extraction for reprocessing spent FBR-fuel (MOX fuel), we have investigated the possibility of an advanced ion exchange process. Based on the fundamental research results, we proposed an advanced ion exchange process considering the characteristics of FBR-fuel cycle. The separation system consists of a main separation process using a novel anion exchanger which has a rapid kinetics and two extraction chromatography processes for minor actinides isolation using novel impregnation adsorbents with high selectivity. The chemical flow sheet, mass balance chart, list of main equipment and installation layout of each equipment were estimated and designed for the process in a reprocessing plant with the capacity of 200 tHM/y FBR-fuel. The process was pfeliminarny evalualed from the aspects of economy performance, recovery of potentially useable resources, minimization of environmental risk and proliferation-resistance by comparing with the advanced PUREX process. Furthermore, the subjects which are important for the practical application of the process are also listed.
*; *; Fumoto, Hiromichi*; *; *
JNC TJ9400 2000-001, 112 Pages, 2000/02
JNC-TJ9400-2000-001.pdf:6.67MB
The purpose of this study is to investigate the possibility of new reprocessing process for the purpose of introducing pipeless plant concept, where aqueous separation methods other than solvent extraction method are adopted in order to develop more economical FBR fuel (MOX fuel) reprocessing process. At it's first stage, literature survey on precipitation method, crystallization method and ion-exchange method was performed. Based on the results, following processes were candidated for pipeless reprocessing plant. (1)The process adopting crystallization method and peroxide precipitation method (2)The process adopting oxalate precipitation method (3)The process under mild aqueous conditions (crystallization method and precipitation method) (4)The process adopting crystallization method and ion-exchange method (5)The process adopting crystallization method and solvent extraction method The processes (1)
(5) were compared with each others in terms of competitiveness to the conventional reference process, and merits and demerits were evaluated from the viewpoint of applicability to pipeless reprocessing plant, safety, economy, Efficiencies in consumption of Resources, non-proliferation, and, Operation and Maintenance. As a result, (1)The process adopting crystallization method and peroxide precipitation method was selected as the most reasonable process to pipeless plant. Preliminary criticality safety analyses, main process chemical flowsheet, main equipment list and layout of mobile vessels and stations were reported for the (1) process.
cell including dissolver off-gas treatmentMineo, Hideaki; Kihara, Takehiro; *; Kimura, Shigeru; *; ; Uchiyama, Gunzo; Hotoku, Shinobu; Watanabe, Makio; ; et al.
JAERI-Conf 99-004, p.498 - 507, 1999/03
no abstracts in English
; ; Ishibashi, Yuzo; Takeda, Seiichiro; *; Fujisaku, Kazuhiko*; *
PNC TN8410 98-116, 147 Pages, 1998/08
None
Asakura, Toshihide; Uchiyama, Gunzo; Kihara, Takehiro; Hotoku, Shinobu; *; ; *; ; ; Fujine, Sachio; et al.
Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 1, p.746 - 753, 1998/00
no abstracts in English
Usuda, Shigekazu; Yasuda, Kenichiro; Sakurai, Satoshi; Takahashi, Toshiyuki; Gunji, Hideho*
Dai-18-Kai Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Nenji Taikai Hobunshu, p.142 - 148, 1997/11
no abstracts in English
Sakurai, Tsutomu;
JAERI-Review 97-002, 62 Pages, 1997/02
JAERI-Review-97-002.pdf:2.51MB
no abstracts in English
Takeshita, Isao
Enerugi, 28(10), p.63 - 66, 1995/00
no abstracts in English
JAERI-M 94-066, 67 Pages, 1994/03
no abstracts in English
Sakurai, Tsutomu;
Journal of Nuclear Science and Technology, 31(1), p.86 - 87, 1994/01
Times Cited Count：9 Percentile：75.49(Nuclear Science & Technology)no abstracts in English
Segawa, Tomoomi; Hamaba, Taishu*; Yoshida, Hideto*; Fukui, Kunihiro*
no journal, ,
In the field of reprocessing of spent nuclear fuel, the aqueous solution of uranyl nitrate and plutonium nitrate is converted to the mixed oxide powder (MOX raw powder) using the microwave heating method for direct denitration. In order to clarify the reaction mechanism of denitration of a metallic nitrate aqueous solution using microwaves, the novel thermogravimetric analysis unit using microwave heating was developed. The absorbed microwave energy can be measured by 2 power meters set on the both side of the raw material. The change in the temperature and the mass of the raw material can be also measured continuously. The process for synthesizing metallic oxide powders by the microwave denitration method was investigated using trihydrated copper nitrate aqueous solutions with this apparatus. As a result of this study, it was found that the reaction routes for microwave heating are the same as those for conventional external heating.
Hamaba, Taishu*; Segawa, Tomoomi; Fukasawa, Tomonori*; Yoshida, Hideto*; Fukui, Kunihiro*
no journal, ,
no abstracts in English
Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka
no journal, ,
The new reprocessing and minor actinide (MA) separation processes using innovative extractants in accord with CHON principle has been developed in Japan Atomic Energy Agency aimed for reduction of radioactive wastes from nuclear fuel cycle. The new nonorganophosphorus extractants which have appropriate extraction behaviors for each separation steps were developed. Continuous counter-current experiment of each solvent extraction process with uranium, plutonium and tracers of minor actinides were carried out. The experimental results showed that the separation performance of the solvent extraction processes were demonstrated successfully.
Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka; Toigawa, Tomohiro; Kurosawa, Tatsuya*; Shibata, Mitsunobu*; et al.
no journal, ,
PUREX process was established for industrial scale reprocessing plant. TRUEX and the 4 group separation were developed for partitioning of minor actinides from HLW, and demonstrated using genuine HLW. Although the extractants for the processes have excellent performance, the molecules contain phosphorus which could be cause for the secondary waste from the solvent extraction processes. To minimize the radioactive waste, we have conducted research and development of the new reprocessing and MA separation processes using innovative extractants in accord with CHON principle. The extractants for reprocessing process are monoamides as alternative extractants for TBP. For An(III)+RE recovery process, we developed TDdDGA. HONTA and ADAAM were developed for An(III)/RE separation process and Am/Cm separation process respectively. The separation performances of the flowsheets were evaluated by continuous extraction tests using simulated and genuine spent fuel and high level liquid waste.
