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Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

Journal Articles

Feasibility study of direct plutonium mass measurement in high-concentrated plutonium solution by a new NDA; Advanced Solution Measurement and Monitoring System (ASMS)

Nakamura, Hironobu; Takaya, Akikazu; Mukai, Yasunobu; Hosoma, Takashi; Yoshimoto, Katsunobu; Tamura, Takayuki*; Iwamoto, Tomonori*

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-30-Kai Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2009/11

JNFL and JAEA have collaboratively started to develop an ASMS for RRP since 2007. The purpose of the development is to establish direct plutonium mass measurement technique by NDA of high concentrated pure plutonium nitrate solution in a strategic process tank. If it is established, ASMS provides direct Pu mass measurement and monitoring capability, substitutes for sampling and destructive analysis at IIV, and extends process monitoring to safety purposes. The target of the measurement uncertainty is set less than 6% which is equivalent to the detection level of partial defect at IIV by NDA. The principle is similar to the one of NDA for MOX powder, but extended such as introducing variable alpha depends on solution properties. As a first trial, a simple prototype system was constructed and calibrated at PCDF (Plutonium Conversion Development Facility) using plutonium nitrate solution. Consequently, good consistency between MCNP (Monte Carlo Neutron and Photon Transport Code) calculation and measured singles/doubles count rate were obtained. As a feasibility study, it was necessary to find out subjects to be solved. We would like to present benefits of ASMS, review installation and detector setup and summarize preliminary calibration results.

Journal Articles

First trial to study the feasibility of direct plutonium mass measurement in a process tank by a new NDA; Advanced solution measurement and monitoring system

Nakamura, Hironobu; Takaya, Akikazu; Mukai, Yasunobu; Hosoma, Takashi; Yoshimoto, Katsunobu; Tamura, Takayuki*; Iwamoto, Tomonori*

Proceedings of INMM 50th Annual Meeting (CD-ROM), 9 Pages, 2009/00

JNFL and JAEA have collaboratively started to develop an ASMS for RRP since 2007 as a trial base. The purpose of the development is to establish quantitative plutonium mass measurement technique directly by NDA of high concentrated pure plutonium nitrate solution in a process tank. If it is established, ASMS provides direct Pu mass measurement and monitoring capability, substitutes for sampling and analysis at IIV, and extends process monitoring to safety purposes. The target of the measurement uncertainty is set less than 6% (1 $$sigma$$) which is equivalent to the detection level of partial defect at IIV by NDA. The principle is similar to the one of NDA for MOX powder, but extended such as introducing variable alpha depends on solution properties. As a first trial, a simple prototype system was constructed and tested at Plutonium Conversion Development Facility of JAEA. Prior to the installation, MCNP calculations for entire cell and tank were performed. Two detectors with a gap were installed just center of the annular tank, then we carried out calibration using plutonium nitrate solution in the range up to 52 kgPu. Consequently, good consistency between calculation and measured singles/doubles count rate were obtained. As a feasibility study, it was necessary to find out subjects to be solved. We would like to present benefits of ASMS, review installation and detector setup and summarize preliminary calibration results.

Journal Articles

Investigation of causes of a failed steam jet and devising an improved jet design

Shimizu, Ryo; Takaya, Akikazu; Shirozu, Hidetomo; Uchida, Naoki; Tanaka, Kosuke; Yamaguchi, Akira; Aoto, Kazumi; Watahiki, Masaru

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(3), p.203 - 212, 2005/09

It was occurred that process solution leaked from the steam jet in the acid recovery process of Tokai reprocessing plant. So we retrieved the jet from the cell and observed the inside. As a result, it was revealed that a defect by corrosion, which penetrated the inside of the structure, arose from the steam nozzle root in the suction room of the jet. To ascertain why such failure occurred, we carried out observation of metallurgical structure of the jet, an analysis of temperature distribution of the structure involving verification using mock-ups and evaluation of material by corrosion test. Consequently, the origin of the corrosion defect was pin hole which was occurred on the surface of the end of the material at the steam nozzle root, where nitric acid fluid was contacted, and then the defect progressed along the temperature of about 120 of the structure. Anisotropy of the material, possibly originating in the manufacturing process, was observed from the result of evaluation of material by corrosion test. Finally, we devised a new design of improved corrosion resistance on the result of the whole investigations.

Journal Articles

Investigation of the Factor of Failed Steam Jet in the Acid Recovery Process of Tokai Reprocessing Plant

Shirozu, Hidetomo; Shimizu, Ryo; Takaya, Akikazu; Uchida, Naoki; Tanaka, Kosuke; Yamaguchi, Akira; Aoto, Kazumi

Saikuru Kiko Giho, (21), p.41 - 55, 2003/00

The cause of the failure, which had occurred in the steam jet (273J202) in the acid recovery process of Tokai reprocessing plant, was investigated.

Oral presentation

Development of a sub-criticality monitoring system for a reprocessing plant, 1

Totsuka, Masayoshi; Shirai, Nobutoshi; Takaya, Akikazu; Inano, Masatoshi

no journal, , 

no abstracts in English

Oral presentation

Study of organic wastes treatment process applying microwave induced plasma

Takaya, Akikazu; Mizuniwa, Naoki; Tanabe, Yoji; Sato, Soichi; Inano, Masatoshi

no journal, , 

no abstracts in English

Oral presentation

MOX reprocessing at TRP, 5; Evaluation for temperature of plutonium product in storage

Kurabayashi, Kazuaki; Kawaguchi, Yoshihito; Takaya, Akikazu; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

Plutonium product recovered from Fugen MOX type B spent fuel is measured temperature at Tokai Reprocessing Plant. And we studied difference between estimated by ORIGEN and analytical value of relative promotion on Pu, moreover, we studied calculation model because of the difference between initial evaluation and temperature of Pu product.

Oral presentation

MOX conversion test for Fugen MOX spent fuel, 1; Temperature evaluation for plutonium nitrate storage tank

Nakamura, Hironobu; Nakamichi, Hideo; Takaya, Akikazu; Shoji, Kaoru*; Matsumoto, Masaki; Fujisaku, Sakae; Yoshimoto, Katsunobu

no journal, , 

For the MOX conversion test by using plutonium nitrate solution that is recycled by Fugen MOX spent fuel, JAEA had performed temperature evaluation for plutonium solution receiving tank (annular shape), and had established the guideline of thermal effect by comparing the measured temperature with designed temperature.

Oral presentation

MOX conversion test for fugen MOX spent fuel, 2; Temperature evaluation for MOX powder

Fujisaku, Sakae; Nakamura, Hironobu; Takaya, Akikazu; Nakamichi, Hideo; Matsumoto, Masaki; Shoji, Kaoru*; Yoshimoto, Katsunobu

no journal, , 

For the MOX conversion test by using plutonium nitrate solution that is recovered by Fugen MOX spent fuel, JAEA had perform the temperature evaluation for MOX powder and had established the guideline for thermal effect by comparing measured temperature with designed temperature.

Oral presentation

Modification of sol-gel vitrification process of high-level radioactive waste

Takaya, Akikazu; Kato, Junya; Fujiwara, Koji; Ueno, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Feasibility study of direct plutonium mass measurement in high-concentrated plutonium solution by a new NDA; Advanced Solution Measurement and Monitoring System (ASMS)

Nakamura, Hironobu; Takaya, Akikazu; Mukai, Yasunobu; Hosoma, Takashi; Yoshimoto, Katsunobu; Tamura, Takayuki*; Iwamoto, Tomonori*

no journal, , 

JNFL and JAEA have collaboratively started to develop an ASMS for RRP since 2007. The purpose of the development is to establish direct plutonium mass measurement technique by NDA of high concentrated pure plutonium nitrate solution in a strategic process tank. If it is established, ASMS provides direct Pu mass measurement and monitoring capability, substitutes for sampling and destructive analysis at IIV, and extends process monitoring to safety purposes. The target of the measurement uncertainty is set less than 6%(1$$sigma$$) which is equivalent to the detection level of partial defect at IIV by NDA. The principle is similar to the one of NDA for MOX powder, but extended such as introducing variable alpha depends on solution properties. As a first trial, a simple prototype system was constructed and tested at PCDF. Two detectors with a gap were installed just center of the annular tank, then we carried out calibration using plutonium nitrate solution (-52kgPu). Consequently, good consistency between MCNP calculation and measured singles/doubles count rate were obtained. As a feasibility study, it was necessary to find out subjects to be solved. We would like to present benefits of ASMS, review installation and detector setup and summarize preliminary calibration results.

Oral presentation

Modification of vitrification process and characteristics evaluation of Sol-Gel glass

Kato, Junya; Takaya, Akikazu; Fujiwara, Koji; Isozaki, Koei

no journal, , 

no abstracts in English

Oral presentation

Development of the measurement technology of inside melter, 2

Nakazaki, Katsutoshi; Takaya, Akikazu; Kato, Junya; Kobayashi, Masahiro; Matsumura, Tadayuki; Niitsuma, Koichi; Fujiwara, Koji

no journal, , 

no abstracts in English

Oral presentation

Development on the measurement system of inside the melter

Kato, Junya; Nakazaki, Katsutoshi; Takaya, Akikazu; Matsumura, Tadayuki; Niitsuma, Koichi; Kodaka, Akira; Fujiwara, Koji

no journal, , 

no abstracts in English

Oral presentation

Repair of the crane in the vitrification cell in Tokai Vitrification Facility (TVF)

Matsumura, Tadayuki; Takaya, Akikazu; Sumi, Hirotaka; Ishii, Kiyonori; Niitsuma, Koichi; Kodaka, Akira; Fujiwara, Koji

no journal, , 

no abstracts in English

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