Status of water cooled ceramic breeder blanket development-Reference-Cited by-同舟云学术

Status of water cooled ceramic breeder blanket development

Published:2018-11 Issue: Volume:136 Page:1550-1556
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Kawamura Yoshinori,Tanigawa Hisashi,Hirose Takanori,Gwon Hyoseong,Nakajima Motoki,Takemura Makoto,Nakata Misato,Ishioka Minoru,Yoshino Seiji,Murakami Hideo^ORCID,Wakasa Atsushi,Sato Satoshi,Ochiai Kentaro,Nakamura Hirofumi,Hoshino Tsuyoshi,Nakamichi Masaru,Tanigawa Hiroyasu,Hayashi Takumi,Yamanishi Toshihiko

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference14 articles.

1. Guidance for EEE in Tokamak Complex [ITER_D_7NPFMA],2018

2. Experimental evaluation of tritium permeation through stainless steel tubes of heat exchanger from primary to secondary water in ITER;Nakamura;J. Nucl. Mater.,2004

3. Allowable Leak Rate of the CCWS-1 Clients [ITER_D_ RWGKT9],2018

4. Development of a two-dimensional nuclear-thermal-coupled analysis code for conceptual blanket design of fusion reactors;Uto;Fusion Eng. Des.,2011

5. Design improvement of blanket box structure with fillet against water ingress;Gwon;Fusion Eng. Des.,2016

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1. Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development;Nuclear Fusion;2024-08-27

2. Development of a tritium release system for ceramic tritium breeder pebbles irradiated by high intensity DT fusion neutron Generator at INEST;Nuclear Materials and Energy;2024-06

3. Conceptual design of poloidal horseshoe limiter layout for JA DEMO;Fusion Engineering and Design;2024-02

4. Effect of Magnetic Field on High-Temperature and High-Pressure Water Corrosion Property of F82H;Plasma and Fusion Research;2024-01-26

5. Study on the Li Mass Loss From LTZO in the Blanket;IEEE Transactions on Plasma Science;2024