Evaluation of Tritium Permeation in Solid Breeder Blanket Cooled by Supercritical Water
Author:
Affiliation:
1. Naka Fusion Research Establishment, Japan Atomic Energy Research Institute 801-1 mukoyama, Naka-machi Naka-gun, Ibaraki-ken, 311-0193 JAPAN +81-29-270-7488
Publisher
Informa UK Limited
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST02-A22727
Reference10 articles.
1. Blanket and divertor design for the Steady State Tokamak Reactor (SSTR)
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