Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy最新文献_第10页

A comparison of the key features of tandem mirror technology test facilities 串列反射镜技术试验装置的主要特点比较

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90012-6

P. Komarek, G. Kulcinski

引用次数: 5

High temperature thermal creep of materials under non-stationary stress and/or temperature loading conditions 材料在非稳态应力和/或温度加载条件下的高温热蠕变

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90004-7

M. Boček, M. Hoffmann

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引用次数: 1

Subject index to volume 2 第二卷的主题索引

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90030-8

引用次数: 0

Radiation hazards due to activated corrosion and neutron sputtering products in fusion reactor coolant and tritium breeding fluids 核聚变反应堆冷却剂和氚增殖液中活化腐蚀和中子溅射产物的辐射危害

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90023-0

A.C. Klein , W.F. Vogelsang

{"title":"Radiation hazards due to activated corrosion and neutron sputtering products in fusion reactor coolant and tritium breeding fluids","authors":"A.C. Klein , W.F. Vogelsang","doi":"10.1016/0167-899X(85)90023-0","DOIUrl":"10.1016/0167-899X(85)90023-0","url":null,"abstract":"<div><p>The accumulation of radioactive corrosion and neutron sputtering products on the surfaces of components in fusion reactor coolant and tritium breeding systems can cause significant personnel access problems. Remote maintenance techniques or special treatment may be required to limit the amount of radiation exposure to plant operational and maintenance personnel. A computer code, RAPTOR, has been developed to estimate the transport of this activated material throughout a fusion heat transfer and/or tritium breeding material loop. A method is devised which treats the components of the loop individually and determines the source rates, deposition and erosion rates, decay rates, and purification rates of these radioactive materials. RAPTOR has been applied to the MARS and Starfire conceptual reactor designs to determine the degree of the possible radiation hazard due to these products. Due to the very high corrosion release rate by HT-9 when exposed to LiPb in the MARS reactor design, the radiation fields surrounding the primary system will preclude direct contact maintenance even after shutdown. Even the removal of the radioactive LiPb from the system will not decrease the radiation fields to reasonable levels. The Starfire primary system will exhibit radiation fields similar to those found in present pressurized water reactors.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"2 3","pages":"Pages 355-363"},"PeriodicalIF":0.0,"publicationDate":"1985-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(85)90023-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73675478","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 4

Description of breeding blanket test modules for TASKA-M TASKA-M的育种毯测试模块描述

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90016-3

I. Sviatoslavsky, M. Sawan, L. Wittenberg, D. Sze, S. Malang, D. Weinberg

引用次数: 1

TASKA-M — a low cost technology test tandem mirror TASKA-M -低成本技术测试串联反射镜

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90015-1

G.A. Emmert

引用次数: 3

A fusion technology demonstration facility (TDF) 聚变技术示范设施(TDF)

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90014-X

J.N. Doggett, B.G. Logan, J.E. Osher, K.I. Thomassen, W.D. Nelson

引用次数: 6

Finite element analysis of friction joints 摩擦节理有限元分析

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90032-1

Gregory Listvinsky , John A. Dalessandro

引用次数: 0

Materials testing in TASKA-M TASKA-M中的材料测试

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90017-5

Mohamed E. Sawan, Gerald L. Kulcinski, Eric K. Opperman, Max A. Vogel, Jeffrey M. Grover

引用次数: 1

The potential net energy gain from DT fusion power plants DT聚变发电厂的潜在净能量增益

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90031-X

R. Bünde

引用次数: 10