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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90012-6

P. Komarek, G.L. 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 Epub Date: 2004-08-26 DOI: 10.1016/0167-899X(85)90004-7

M. Boček, M. Hoffmann

{"title":"High temperature thermal creep of materials under non-stationary stress and/or temperature loading conditions","authors":"M. Boček, M. Hoffmann","doi":"10.1016/0167-899X(85)90004-7","DOIUrl":"10.1016/0167-899X(85)90004-7","url":null,"abstract":"<div><p>The object of this paper is to describe the thermal creep behavior and the lifetime prediction of materials subjected to non-stationary tensile loading conditions. The calculations are based on HART's tensile test equation and on a phenomenological cavitation damage model. From this model the life fraction rule (LFR) is derived. Analytical expressions for the lifetimes are derived, which contain only stationary stress rupture data. The creep behavior of non-cavitating and ideally plastic materials is derived from the solution of the tensile test equation for the particular loading conditions considered. Cavitation damage is known to influence the creep behavior by reducing the load bearing capability. The corresponding constitutive equation containing the loading conditions as well as the damage function is derived.</p><p>The following loading conditions were considered: (i) creep at constant load <em>F</em> and temperature <em>T</em>; (ii) creep at linearly increasing load and <em>T</em> = const.; (iii) creep at constant load amplitude cycling and <em>T</em> = const.; (iv) creep at constant load and linearly increasing <em>T</em>; (v) creep at constant load and temperature cycling and (vi) creep at superimposed load and temperature cycling.</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 1","pages":"Pages 29-52"},"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)90004-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72403123","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: 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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90030-8

引用次数: 0

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

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 Epub Date: 2004-09-07 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

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90015-1

G.A. Emmert

引用次数: 3

Nonlinear and dynamic fracture of cracked structures under electromagnetic force 电磁力作用下裂纹结构的非线性动态断裂

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 Epub Date: 2004-08-26 DOI: 10.1016/0167-899X(85)90005-9

G. Yagawa, S. Yoshimura

{"title":"Nonlinear and dynamic fracture of cracked structures under electromagnetic force","authors":"G. Yagawa, S. Yoshimura","doi":"10.1016/0167-899X(85)90005-9","DOIUrl":"10.1016/0167-899X(85)90005-9","url":null,"abstract":"<div><p>This paper is concerned with both numerical analyses and experiments on dynamic fracture caused by the electromagnetic force taking an edge-cracked structure which carries a transient electric current <em>I</em> and is placed in a uniform and steady magnetic field <em>B</em><sub><em>o</em></sub>. In the numerical analyses, we calculate the electric current distribution, the Joule heating and the extended <em>J</em>-integral with the inertia effect, the electromagnetic force and the thermal force on dynamic fracture caused by the electromagnetic force. Also the dynamic fracture tests under the electromagnetic force are carried out with the edge-cracked specimens made of brittle and ductile materials to compare with the numerical results. Here, using the electric potential method, with which the crack initiation and the dynamic ductile crack growth are detected, we obtain the dynamic fracture toughness and the crack velocity on the dynamic fracture caused by the electromagnetic force.</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 1","pages":"Pages 53-63"},"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)90005-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87234854","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: 5

An upgrade of MFTF-B for fusion technology 用于核聚变技术的MFTF-B升级

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90013-8

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

{"title":"An upgrade of MFTF-B for fusion technology","authors":"K.I. Thomassen, J.N. Doggett, B.G. Logan, W.D. Nelson","doi":"10.1016/0167-899X(85)90013-8","DOIUrl":"https://doi.org/10.1016/0167-899X(85)90013-8","url":null,"abstract":"<div><p>A deuterium-tritium (DT) burning upgrade to the MFTF-B tandem mirror that incorporates a high neutron flux test section in the central cell is described. This test section is a beam-driven simple mirror, where 11 MW of fusion power produces a neutron flux of ∼ 2 MW/m<sup>2</sup>. In this test section one can perform 100 h uninterrupted tests of the power and fuel cycle operation of fusion blankets. The tandem mirror in which this section is embedded is a scale down version of the MARS reactor. It uses 200 kV negative ion beams, an 18 T choke coil, drift pumping for removing α-ash and ions trapped in the barrier/transition, halo pumping, and biased end plates for potential control and direct conversion. There are two modes of operation in the device: one mode achieves the high neutron flux by injecting beams in the test section and reducing the end plug potential to accommodate the high throughput of particles; the other mode reduces the beam input to the minimum required for fueling and raises the end potentials to their highest possible values for good confinement. This two-mode operation is a unique feature of the tandem that allows a dual physics-nuclear technology role for the device.</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 2","pages":"Pages 209-222"},"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)90013-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91773265","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: 3

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90031-X

R. Bünde

引用次数: 10

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90032-1

Gregory Listvinsky , John A. Dalessandro

引用次数: 0