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Journal Articles

A Review of separation processes proposed for advanced fuel cycles based on technology readiness level assessments

Baron, P.*; Cornet, S. M.*; Collins, E. D.*; DeAngelis, G.*; Del Cul, G.*; Fedorov, Y.*; Glatz, J. P.*; Ignatiev, V.*; Inoue, Tadashi*; Khaperskaya, A.*; et al.

Progress in Nuclear Energy, 117, p.103091_1 - 103091_24, 2019/11

 Times Cited Count:4 Percentile:28.97(Nuclear Science & Technology)

The results of an international review of separation processes for spent nuclear fuel (SNF) recycling in future closed fuel cycles with the evaluation of Technology Readiness Level are reported. This study was made by the Expert Group on Fuel Recycling Chemistry (EGFRC) organised by the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development (OECD). A unique feature of this study was that processes were classified according to a hierarchy of separations aimed at different elements within spent fuel (uranium; uranium-plutonium co-recovery; minor actinides; high heat generating radionuclides) and also the Head-end processes, used to prepare the SNF for chemical separation, were included. Separation processes covered both wet (hydrometallurgical) and dry (pyro-chemical) processes.

Journal Articles

Present state of partitioning and transmutation of long-lived nuclides, 4; Transmutation system using accelerator driven system and technology maturity of partitioning and transmutation

Tsujimoto, Kazufumi; Arai, Yasuo; Minato, Kazuo

Nippon Genshiryoku Gakkai-Shi, 59(11), p.644 - 648, 2017/11

no abstracts in English

Journal Articles

Establishment of technical basis to implement accident tolerant fuels and components to existing LWRs

Yamashita, Shinichiro; Nagase, Fumihisa; Kurata, Masaki; Kaji, Yoshiyuki

Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), p.21 - 30, 2016/09

Fuel rod, channel box, and control rod designed with new materials and concepts have been developed in Japan for increasing accident tolerance of LWRs. In order to efficiently and properly implement the accident tolerant fuels (ATFs) and the other components, it is necessary not only to accumulate fundamental and practical data but also to consider technology readiness, recognize knowledge gaps, and establish strategy for design and fabrication. The Japan Atomic Energy Agency (JAEA) has established the above "technical basis" and drafted a research plan towards implementation of the ATFs and components as a program sponsored and organized by the Ministry of Economy, Trade and Industry (METI). It is useful to take advantage of the experiences in commercial uses of zirconium-base alloys in LWRs and, therefore, JAEA has conducted this METI project in cooperation with power plant providers, fuel venders, research institutes and universities who have been involved in the development of the ATF materials. The present paper describes the main results of the project conducted to establish the technical basis of the ATFs and components.

Oral presentation

Issues toward implementation of accident tolerant fuels and components to existing LWRs

Yamashita, Shinichiro

no journal, , 

In this oral presentation, the result of "Development of Technical Basis for Introducing Advanced Fuels Contributing to Safety Improvement of Current Light Water Reactors" carried out under the Project on Development of Technical Basis for Safety Improvement at Nuclear Power Plants by Ministry of Economy, Trade and Industry (METI) of Japan will be partially introduced. The gap between the present R&D status and the achievement of practical use in order to progress the R&D properly and efficiently will be talked together with related information of oversea research activities.

Oral presentation

Establishment of technical basis to implement accident tolerant fuels and components to existing LWRs; R&D program for design and fabrication towards implementation of ATFs and components to the existing LWRs

Yamashita, Shinichiro; Nagase, Fumihisa; Kurata, Masaki; Kaji, Yoshiyuki

no journal, , 

In TEPCO's Fukushima Daiichi Nuclear Power Station (1F), the cooling capability was lost due to tsunami caused by the Great East Japan Earthquake. It is considered that the Zirconium (Zr) alloy fuel cladding was oxidized in the heated core and the subsequent temperature escalation due to the oxidation caused core melting. As lessons learned from the 1F accident, development of advanced fuel and core components with enhanced accident tolerance becomes the greater concern. We have started R&D to establish the technical basis to implement the advanced fuel components to existing LWRs. The R&D is conducted in cooperation with power plant providers, fuel venders, research institutes and universities who have been involved in the development of the advanced fuel components. In this presentation, we will introduce the R&D program which are carried out under the Project on Development of Technical Basis for Safety Improvement at Nuclear Power Plants by Ministry of Economy, Trade and Industry (METI) of Japan.

Oral presentation

"Issues" and "Challenges" for introducing new fuels and the other components with enhanced accident tolerance to light water reactor

Yamashita, Shinichiro

no journal, , 

In order to increase accident tolerance of light water reactors (LWRs), fuel rod, channel box and control rod with new materials and concepts have been considered and developed in Japan. Since 2015, the Japan Atomic Energy Agency (JAEA) has conducted and coordinated the Japanese R&D program of accident tolerant fuel (ATF) for establishing technical basis of ATF under a program sponsored and organized by the Ministry of Economy, Trade and Industry (METI). This program has been carried out in cooperation with power plant providers, fuel venders and universities because it is efficient and proper to take advantage of the experiences in R&D, practical design, and evaluations of fuels and cores of commercial LWRs.

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