The Development status of Generation IV reactor systems, 1; Overview

Sagayama, Yutaka; Ando, Masato

Nihon Genshiryoku Gakkai-Shi ATOMO, 60(3), p.162 - 167, 2018/03

https://doi.org/10.3327/jaesjb.60.3_162

The Generation IV international Forum (GIF) has led international collaborative efforts to develop six next generation nuclear energy systems, such as Sodium-cooled Fast Reactor (SFR), Lead-cooled Fast Reactor (LFR), Gas-cooled Fast Reactor (GFR), Molten Salt Reactor (MSR), Supercritical Water-cooled Reactor (SCWR), and Very High Temperature Reactor (VHTR), which have superior characteristics for the Safety and Reliability, Economics, Sustainability, Proliferation Resistance and Physical Protection. Some systems are already in the Demonstration Phase and the commercialization of the system in 2030s, which is the target of GIF, comes into sight.

International conference on future nuclear systems (Global '97)

Takizuka, Takakazu

Nihon Kikai Gakkai Doryoku Enerugi Shisutemu Bumon Nyusu Reta, (16), P. 7, 1998/05

no abstracts in English

Proceedings of the 6th Seminar on Software Development in Nuclear Energy Research

; Research Committee on Reactor Physics

JAERI-M 91-015, 188 Pages, 1991/02

JAERI-M-91-015.pdf:5.82MB

no abstracts in English

Current status and perspectives of thorium nuclear energy systems, 1; Global trend of the developments for thorium nuclear energy systems

Sasa, Toshinobu

no journal, , 

As a part of the activities of the "Research Committee for Thorium Nuclear System" in the Japan Atomic Energy Society, the characteristics, performance and feasibility of the proposed thorium nuclear systems from recently published open documents were surveyed in order to understand the research and development status of the thorium nuclear system around the world. Research has been conducted in the countries using nuclear power in the world such as India, Asia, Europe, and the United States. Pebble fuel or molten salts (thermal and fast neutron systems) are selected as fuel material. Regarding the core thermal output, proposals were selected from several 100 MW for demo reactors and modular reactor to 5 GW for power reactors. For the feasibility point of view, many proposals are still in the concept study phase, but there are a few concepts which aimed at licensing of already approved the domestic environmental impact assessment.

Study on advanced nuclear energy system based on the environmental impact of radioactive waste disposal, 4; Simplification of MA separation process based on environmental load in waste disposal

Matsumura, Tatsuro; Tsubata, Yasuhiro; Asano, Hidekazu*

no journal, , 

no abstracts in English

Study on nuclear energy system considering environmental load reduction of waste disposal in diversification of nuclear fuel cycle conditions, 3; Simplification of MA separation process based on reasonable MA recovery rate by environmental impact assessment of radioactive waste disposal

Matsumura, Tatsuro; Asano, Hidekazu*; Sakuragi, Tomofumi*; Hamada, Ryo*; Han, C. Y.*; Nakase, Masahiko*; Chiba, Go*; Sagara, Hiroshi*; Takeshita, Kenji*

no journal, , 

The issue of high-level waste disposal is important for the sustainable use of nuclear energy. P&T technology of long-lived and highly radiotoxic MA is a key technology. The MA separation process, which separates MA from the high-level waste, is one of the essential technology for realizing the P&T technology. JAEA has been developing the SELECT process using the solvent extraction technique for the MA separation process. Target values for separation performance were 99% recovery rate based on radiotoxicity evaluation and 95% MA product purity from evaluation of the performance of transmutation system. The separation process was demonstrated by the test using genuine HLW. SELECT process consists of two steps. The second step for MA/RE separation requires 40 extraction stages for the target value, and there was a issue of introduction and operation costs. Therefore, we set a reasonable recovery rate based on the evaluation of the environmental impact of the disposal site. Based on the target value, quantitative evaluation was carried out using the PARC-MA code, and the number of extraction stages in the MA/RE separation process and the purity of the MA product were obtained. We believe that the configuration of a realistic simplified MA separation process has been clarified.

Study on advanced nuclear energy system based on the environmental impact of radioactive waste disposal, 12; Simplification of the MA separation process

Matsumura, Tatsuro; Asano, Hidekazu*; Sakuragi, Tomofumi*; Hamada, Ryo*

no journal, , 

no abstracts in English

Material corrosion and development in nuclear energy systems

Kato, Chiaki

no journal, , 

The Nuclear Science Research Institute where the author belongs has large hot facilities for handling radioactive materials, including research reactors. Using these facilities, the author has been investigating the mechanisms of material corrosion in nuclear systems. This paper describes the corrosion phenomena and mechanisms of nuclear fuel reprocessing facilities, which mainly have been the subject of research and development by the author. It also discusses the effects of high irradiation specific to nuclear systems.