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Journal Articles

Demonstration of remote fabrication for FBR MOX fuel at the PFPF

Takahashi, Saburo; Kikuno, Hiroshi; Shiromo, Hideo; Kuba, Meiji; Abe, Tomoyuki; Takeda, Seiichiro

Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10

Japan Atomic Energy Agency (JAEA) has been accumulating various experience and knowledge on development of MOX fuel technologies for more than 40 years since 1966. Plutonium Fuel Production Facility (PFPF) has introduced a fully automated and remote operation in 1988 as a pioneer in the world, based on the operational and technical experience obtained in the existing facilities. The PFPF has fabricated MOX fuel assemblies for a fast reactor "JOYO" and a fast breeder reactor "MONJU" so far. Through MOX fuel fabrication for JOYO and MONJU, many operational experiences such as a hold-up material problem have been gained. Based on the experiences, process equipments have been newly developed and a process technology has been improved. As the results, fully automated and remote fabrication technologies including easy contact maintenance of process equipments for FBR MOX fuel have been demonstrated in the PFPF on a large scale.

Journal Articles

The Prospective role of JAEA Nuclear Fuel Cycle Engineering Laboratories

Ojima, Hisao; Dojiri, Shigeru; Tanaka, Kazuhiko; Takeda, Seiichiro; Nomura, Shigeo

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.273 - 282, 2007/09

The Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency (JAEA) was established to take over activities of the Tokai Works of Japan Nuclear Cycle Development Institute (JNC). From 1959, several kinds of technologies (such as uranium refining, centrifuge for uranium enrichment, LWR spent fuel reprocessing and MOX fuel fabrication) have been accomplished. And also, R&Ds on the treatment and disposal of high level waste and the FBR fuel reprocessing have been carried out. Through such activities, control of environmental release of radioactive material and radiation exposure and management of nuclear materials have been done appropriately. The Laboratories will contribute to establish the closed cycle with R&Ds of the reprocessing technology during the transition period from LWR era to FBR era, improved MOX fuel fabrication technology, advanced FBR fuel reprocessing technology and high level waste disposal technology.

Journal Articles

None

; Takeda, Seiichiro; Suto, O.;

Saikuru Kiko Giho, (15), p.176 - 178, 2002/06

None

Journal Articles

None

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

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

None

JAEA Reports

Corrosion performance of metal materials in reprocessing solution of spent nuclear fuel

Takeda, Seiichiro; ; ; ; Kato, Toshihiro*; *; Fujisaku, Kazuhiko*

JNC TN8400 2002-007, 135 Pages, 2001/12

JNC-TN8400-2002-007.pdf:9.39MB

Corrosion performance of materials used for nuclear fuel reprocessing plant was studied for the extension of their lifetime during in-service period. Research was performed focusing on characteristics of reprocessing solution which is very important corrosion factor on environmental side. In the first stage, fundamental corrosion behavior of several kinds of candidate materials such as 304ULC, 310Nb, Ti, Ti-5Ta and Zr was investigated in pure nitric acid solution. Then corrosion performance of such materials in reprocessing environment was made cleared by means of so-called hot test which is used actual reprocessing solution under radioactive conditions. The results are summarized as follows. (1) With regards to the effects of uranium and plutonium on corrosion, high valence plutonium (Pu(Ⅵ)) accelerated the corrosion of stainless steels in nitric acid, but uranium did not affect on them. It is caused by trans-passive dissolution based on the shift of corrosion potential to the noble position. It is thought that the potential shift is caused by increase of the cathodic current on the stainless steel surface due to the reduction of Pu(Ⅵ) to Pu(IV). (2) In fission product (FP) elements, ruthenium accelerated the corrosion of stainless steel in nitric acid when its concentration was comparatively high. Other FP's did not affect on them. The corrosion potential of stainless steel shifts toward noble region by adding ruthenium in nitric acid where high corrosion rates are exhibited. It is thought that the potential shift is caused by the enhancement of cathodic reactions on metal surface due to co-existence of ruthenium in nitric acid. (3) Ti, Ti-5Ta and Zr showed excellent corrosion resistance in nitric acid with and without Plutonium and ruthenium. Especially, Ti and Ti-5Ta showed the improvement of corrosion resistance by co-existing Plutonium or ruthenium. It was explained by chemical stability of surface oxide film due to plutonium or ruthenium oxidant.

Journal Articles

None

; Takeda, Seiichiro; Suto, O.; Baba, Tsutomu

Saikuru Kiko Giho, (13), p.111 - 113, 2001/12

None

Journal Articles

None

; Takeda, Seiichiro; Suto, O.; Baba, Tsutomu

Saikuru Kiko Giho, (12), p.175 - 177, 2001/09

None

JAEA Reports

The calculation and estimation of wastes generated by decommissioning of nuclear facilities

; ; ; Takeda, Seiichiro

JNC TN8420 2001-008, 134 Pages, 2001/07

JNC-TN8420-2001-008.pdf:4.4MB

This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decomissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decomissioning of the nuclear facilities are as follows. (1)Tokai works. The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2)Ningyo-toge Environmental Engineering Center. The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton.

Journal Articles

None

; Takeda, Seiichiro; Suto, O.; Baba, Tsutomu

Saikuru Kiko Giho, (11), p.173 - 175, 2001/06

None

Journal Articles

Long-term Durability Test of Acid Recovery Evaporators Made of Ti-5%Ta Alloy and Zirconium

; Nagai, Takayuki; Koizumi, Tsutomu; Takeda, Seiichiro;

Nihon Genshiryoku Gakkai-Shi, 42(12), p.1315 - 1324, 2000/00

 Times Cited Count:1 Percentile:12.43(Nuclear Science & Technology)

None

Journal Articles

PLANNING OF WASTE MANAGEMENT PROGRAM FOR LOW LEVEL RADIOACTIVE WASTES GENERATED FROM JNC SITES

Takahashi, Kuniaki; Takeda, Seiichiro; ; ;

Spectrum2000, 0 Pages, 2000/00

None

JAEA Reports

None

Fujisaku, Kazuhiko*; Ishibashi, Yuzo; Takeda, Seiichiro; ; *

PNC TN8410 98-115, 50 Pages, 1998/09

PNC-TN8410-98-115.pdf:1.45MB

None

JAEA Reports

None

; ; Ishibashi, Yuzo; Takeda, Seiichiro; *; Fujisaku, Kazuhiko*; *

PNC TN8410 98-116, 147 Pages, 1998/08

PNC-TN8410-98-116.pdf:8.6MB

None

JAEA Reports

None

; Ishibashi, Yuzo; ; ; Takeda, Seiichiro

PNC TN8410 98-078, 36 Pages, 1998/07

PNC-TN8410-98-078.pdf:1.11MB

None

Journal Articles

Corrosion Behavior of Stainless Steel in Nitric Acid Solution under Gamma-ray Irradiation

Nagai, Takayuki; Takeuchi, Masayuki; Takeda, Seiichiro; Yamamoto, Takao*; Tsukui, Shigeki*; Okamoto, Shinichi*

Journal of Nuclear Science and Technology, 35(7), p.502 - 507, 1998/07

 Times Cited Count:5 Percentile:44.99(Nuclear Science & Technology)

None

JAEA Reports

None

; ; Fujisaku, Kazuhiko*; Ishibashi, Yuzo; Takeda, Seiichiro

PNC TN8410 98-060, 74 Pages, 1998/03

PNC-TN8410-98-060.pdf:4.43MB

None

JAEA Reports

None

Kato, Toshihiro*; ; ; ; Ishibashi, Yuzo; Takeda, Seiichiro

PNC TN8410 98-070, 31 Pages, 1998/02

PNC-TN8410-98-070.pdf:0.96MB

None

Journal Articles

$$gamma$$-ray irradiation effect on corrosion rates of stsinless steel in boilingnitric acid containi

; Nagai, Takayuki; Takeda, Seiichiro; Tanaka, Yasumasa

Journal of Nuclear Science and Technology, 35(5), p.353 - 356, 1998/00

None

Journal Articles

Gamma-ray Irradiation Effects on Corrosion Rates of Stainless Steel in Boiling Nitric Acid Containing Ionic Additives

; Nagai, Takayuki; Takeda, Seiichiro; Tanaka, Yasumasa

Journal of Nuclear Science and Technology, 35(5), p.353 - 356, 1998/00

 Times Cited Count:11 Percentile:67.36(Nuclear Science & Technology)

None

Journal Articles

Effect of $$gamma$$-ray irradiation on corrosion of austenitic stainless steel in boiling int

; ; Takeda, Seiichiro

Proceedings of 5th International Conference on Recycling, Conditioning and Disposal (RECOD '98), p.845 - 851, 1998/00

None

39 (Records 1-20 displayed on this page)