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Journal Articles

Development of the residual sodium quantification method for a fuel pin bundle of SFRs before and after dry cleaning

Kudo, Hideyuki*; Otani, Yuichi*; Hara, Masahide*; Kato, Atsushi; Otaka, Masahiko; Ide, Akihiro*

Journal of Nuclear Science and Technology, 57(4), p.408 - 420, 2020/04

 Times Cited Count:1 Percentile:11.41(Nuclear Science & Technology)

In a fuel handling system of sodium-cooled fast reactors (SFRs), it is necessary to remove the sodium remaining on spent fuel assemblies (FAs) before storing them in a spent fuel water pool (SFP) in order to minimize plant operating loads. A next-generation SFR in Japan has adopted an advanced dry cleaning process which consists of the following steps, argon gas blowing to remove the metallic residual sodium on the FA, moist argon gas blowing to deactivate the residual sodium, and direct storage in the SFP. This three-step process increases economic competitiveness and reduces waste products thanks to a waterless process. In this R&D work, performance of the dry cleaning process has been investigated.

Journal Articles

Dry cleaning process test for fuel assembly of fast reactor plant system, 1; Pilot scale test for fuel pin bundle

Kudo, Hideyuki*; Otani, Yuichi*; Hara, Masahide*; Kato, Atsushi; Ishikawa, Nobuyuki; Otaka, Masahiko; Nagai, Keiichi; Saito, Junichi; Ara, Kuniaki; Ide, Akihiro*

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05

A next generation SFR in Japan has adopted an advanced dry cleaning system which consists of the argon gas blowing process to reduce the amount of metallic residual sodium remaining on spent fuel assemblies. This paper describes experimental and analytical work focusing on the amount of residual sodium remaining on a fuel pin bundle before and after the argon gas blowing process. The experiments were conducted using a sodium test loop and a short specimen consisting of a 7 pin bundle. The effects of the blowing gas velocity and the blowing time were quantitatively analyzed in the experiments. On the basis of these experimental results, evaluation models predicting the amount of the residual sodium were constructed.

Journal Articles

Dry cleaning process test for fuel assembly of fast reactor plant system, 2; Laboratory scale test for fuel assembly and evaluation of the amount of residual sodium

Ide, Akihiro*; Kudo, Hideyuki*; Inuzuka, Taisuke*; Hara, Masahide*; Kato, Atsushi; Ishikawa, Nobuyuki; Otaka, Masahiko; Nagai, Keiichi; Saito, Junichi; Ara, Kuniaki

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05

A next generation SFR in Japan has adopted an advanced dry cleaning system which consists of the following process of argon gas blowing to reduce the amount of metallic sodium, moist argon gas blowing to deactivate the residual sodium, and direct storage in the SFP without using storage containers. This three-step process increases economic competitiveness and reduces waste products. In this Research and Development work, the amount of residual sodium and performance of the dry cleaning process were investigated. This paper describes experimental and analytical work for all parts of a fuel assembly except for a fuel pin bundle.

Journal Articles

Dry cleaning process test for fuel assembly of fast reactor plant system

Kato, Atsushi; Nagai, Keiichi; Ara, Kuniaki; Otaka, Masahiko; Oka, Nobuki*; Tanaka, Masako*; Otani, Yuichi*; Ide, Akihiro*

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

In a fuel handling system (FHS) of a sodium-cooled fast reactor, it is necessary to reduce residual sodium on a spent fuel subassembly before storing at a spent fuel water-pool (SFP) in order to minimize design loads. Although the wet cleaning process adopted on MONJU could eliminate almost all of residual sodium, a large amount of radioactive liquid waste occurs and it needs long duration of cleaning treatment and large plant commodities. On the other hand, Japan sodium-cooled fast reactor adopted an advanced dry cleaning system which consists of roughly blowing massive sodium on the fuel subassembly out by 300$$^{circ}$$C argon gas, inactivation of residual sodium to NaOH by moist argon gas and directly immersion into the SFP to achieve economic competitiveness and waste reduction. This paper reports current status of recent R&D activities to demonstrate a performance of the dry cleaning process in Japan which are for improvement of the cleaning performance and optimizing the FHS design.

Journal Articles

Progress of design study on fuel handling system in JSFR against design extension conditions

Otaka, Masahiko; Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*; Ide, Akihiro*; Kaneko, Fumiaki*; Hara, Hiroyuki*

Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.607 - 615, 2014/04

Responding to the TEPCO's Fukushima Dai-ichi Nuclear Power Station accident, the design study was carried out to enhance cooling function of fuel handling system for Japan sodium-cooled fast reactor (JSFR). Design measures to maintain an FHS cooling function even in case of Design Extension Conditions are studied; such as alternative cooling systems which are independent and diversified from design basis cooling systems. Based on effectiveness evaluations, it was confirmed that these measures have adequate availability against the postulated design extension conditions.

Journal Articles

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

Nakamura, Kazuyuki; Furukawa, Tomohiro; Hirakawa, Yasushi; Kanemura, Takuji; Kondo, Hiroo; Ida, Mizuho; Niitsuma, Shigeto; Otaka, Masahiko; Watanabe, Kazuyoshi; Horiike, Hiroshi*; et al.

Fusion Engineering and Design, 86(9-11), p.2491 - 2494, 2011/10

 Times Cited Count:10 Percentile:61.04(Nuclear Science & Technology)

In IFMIF/EVEDA, tasks for lithium target system are shared to 5 validation tasks (LF1-5) and a design task (LF6). The purpose of LF1 task is to construct and operate the EVEDA lithium test loop, and JAEA has a main responsibility to the performance of the Li test loop. LF2 is a task for the diagnostics of the Li test loop and IFMIF design. Basic research for the diagnostics equipment has been completed, and the construction for the Li test loop will be finished before March in 2011. LF4 is a task for the purification systems with nitrogen and hydrogen. Basic research for the purification equipment has been completed, and the construction of the nitrogen system for the Li test loop will be finished before March in 2011. LF5 is a task for the remote handling system with the target assembly. JAEA has an idea to use the laser beam for cutting and welding of the lip part of the flanges. LF6 is a task for the design of the IFMIF based on the validation experiments of LF1-5.

JAEA Reports

None

Todokoro, Akio; Watahiki, Masatoshi; Kihara, Yoshiyuki; Ishii, Yasuhiko*; Ogasawara, Masahiro*; Otaka, Akihiro*

PNC TN8410 96-238, 86 Pages, 1996/08

PNC-TN8410-96-238.pdf:2.3MB

None

JAEA Reports

None

Todokoro, Akio; Kihara, Yoshiyuki; Watahiki, Masatoshi; Ogasawara, Masahiro*; Otaka, Akihiro*

PNC TN8410 94-403, 30 Pages, 1994/11

PNC-TN8410-94-403.pdf:1.71MB

None

Oral presentation

Results of basic examinations on the simplified MOX fuel fabrication process (short process), 1; Experimental concept and the examination on Pu/U ratio control by liquid mixing

Mukai, Yasunobu; Kato, Yoshiyuki; Yoshimoto, Katsunobu; Sawa, Hideshi*; Otaka, Akihiro*

no journal, , 

no abstracts in English

Oral presentation

Effect on heating efficiency by support table height in microwave oven

Tanigawa, Masafumi; Kato, Yoshiyuki; Kurita, Tsutomu; Kusano, keiichi*; Otaka, Akihiro*; Nakamichi, Hideo*

no journal, , 

no abstracts in English

Oral presentation

Study on countermeasure against design extension conditions for spent fuel storage facilities of JSFR

Otaka, Masahiko; Kato, Atsushi; Chikazawa, Yoshitaka; Ide, Akihiro*; Kaneko, Fumiaki*; Hara, Hiroyuki*; Uzawa, Masayuki*

no journal, , 

Design study was carried out for enhancement of cooling function of fuel storage facilities in Japan Sodium-cooled Fast Reactor (JSFR). Design measures to maintain cooling function even in case of postulated design extension conditions are studied; such as an alternative cooling system for design basis components, multiplying cooling lines, concerning diversity of a cooling ways, etc.

Oral presentation

Examination that improves solubility of plutonium dioxide in MOX powder

Tanigawa, Masafumi; Kato, Yoshiyuki; Kurita, Tsutomu; Komatsuzaki, Mai*; Otaka, Akihiro*; Nakamichi, Hideo*

no journal, , 

no abstracts in English

Oral presentation

Dry cleaning process test for fuel assembly of fast reactor plant system, 3; Sodium loop test

Kudo, Hideyuki*; Otani, Yuichi*; Hara, Masahide*; Otaka, Masahiko; Nagai, Keiichi; Saito, Junichi; Ishikawa, Nobuyuki; Ara, Kuniaki; Ide, Akihiro*

no journal, , 

no abstracts in English

Oral presentation

Dry cleaning process test for fuel assembly of fast reactor plant system, 4; Laboratory scale test and evaluation results of the amount of residual sodium on a fuel assembly

Ide, Akihiro*; Otaka, Masahiko; Nagai, Keiichi; Saito, Junichi; Ishikawa, Nobuyuki; Ara, Kuniaki; Kudo, Hideyuki*; Inuzuka, Taisuke*; Hara, Masahide*

no journal, , 

no abstracts in English

14 (Records 1-14 displayed on this page)
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