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

{"title":"Numerical analysis of electromagnetic stress induced in bellows for a magnetic fusion reactor","authors":"Kenzo Miya,&nbsp;Mitsuru Uesaka,&nbsp;Yuichi Ogawa,&nbsp;Taiji Hamada","doi":"10.1016/0167-899X(85)90037-0","DOIUrl":"10.1016/0167-899X(85)90037-0","url":null,"abstract":"<div><p>The use of bellows in a magnetic fusion reactor gives, in many cases, more efficient penetration of the poloidal electric field and very efficient plasma heating in the first phase of operation. This is because bellows sections lead to higher electrical resistance of the vacuum vessel. There are many examples of its application to tokamak type experimental devices such as TFTR, JT-60 and so on. In addition to its higher electrical resistance, the bellows has an ability to absorb large deformation due to thermal expansion and radiation creep, and thus has been applied to the design of a first wall configuration in some conceptual designs of a commercial power reactor. Its application to a vacuum vessel of the Reacting Plasma machine, which was proposed by the Institute of Plasma Physics of Nagoya University, was examined for circular plasmas. When applying the numerical analysis to the bellows, a computational difficulty occurs. Too many unknows appear in a mesh division with a general shell element and these are not easily handled. Therefore in the present paper a finite element code is made to consider an axisymmetric structure loaded by nonsymmetric forces. In the code various types of electromagnetic forces are taken into account. These include the diamagnetic electromagnetic force, the toroidal-current-induced-electromagnetic forces, the electromagnetic forces due to toroidal coil current change and saddle shaped electromagnetic forces. Aluminum is selected as bellows material because of its low activation nature but there are large induced currents because of its higher electrical conductivity. Results of stress analysis show that a leak of the saddle shaped current into the thick aluminum vacuum vessel generates maximum bending stress near a joint between the bellows and the vessel. Stress due to other types of electromagnetic force are significantly smaller.</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":"3 1","pages":"Pages 81-95"},"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)90037-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88928099","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}

{"title":"The effect of cascade and helium on microstructural evolution under fusion irradiations","authors":"S. Ishino,&nbsp;T. Muroga,&nbsp;N. Sekimura","doi":"10.1016/0167-899X(85)90002-3","DOIUrl":"10.1016/0167-899X(85)90002-3","url":null,"abstract":"<div><p>Cascade damage and high helium production rate are major characteristic features of fusion neutron radiation effects. Experimental as well as computational studies of these two factors which have been performed by the authors are presented and discussed from the standpoint of microstructural evolution. The experimental work has been performed using a facility comprising two small ion accelerators and an electron microscope, capable of observing cascade damage during heavy ion bombardment, and of carrying out dual beam irradiations to study the effect of simultaneous injection of helium atoms with displacement cascades. It has been shown that the evolving microstructures depend strongly on the nature of the cascade, type of materials, irradiation temperature, and amount and mode of helium implantation. The implication of these microstructural studies to the radiation effects relevant to fusion reactor design is discussed.</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 3-18"},"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)90002-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79605001","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}

{"title":"An upgrade of MFTF-B for fusion technology","authors":"K. Thomassen, J. Doggett, B. 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":"","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":"17 1","pages":"209-222"},"PeriodicalIF":0.0,"publicationDate":"1985-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72956962","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}

{"title":"The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications","authors":"R.L. Klueh,&nbsp;E.E. Bloom","doi":"10.1016/0167-899X(85)90026-6","DOIUrl":"10.1016/0167-899X(85)90026-6","url":null,"abstract":"<div><p>The CrMo ferritic (martensitic) steels are leading candidates for the structural components for future fusion reactors. However, irradiation of such steels in a fusion environment produces long-lived radioactive isotopes that lead to difficult waste disposal problems once the structure is removed from service. One method proposed to alleviate such problems is the development of steels that contain only elements that produce radioactive isotopes that decay to low levels in a reasonable time (tens of years instead of hundreds or thousands of years). For such a solution for the CrMo steels, molybdenum must be eliminated. In addition, niobium must be maintained at extremely low levels. Tungsten is proposed as an appropriate substitution for molybdenum, and the procedures for developing CrW steels analogous to the CrMo steels are discussed.</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 383-389"},"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)90026-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72889205","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}

{"title":"Time independent tensile behaviour of a high manganese steel selected as a candidate material in conceptual tokamak fusion reactor designs","authors":"G. Piatti,&nbsp;S. Matteazzi,&nbsp;G. Petrone","doi":"10.1016/0167-899X(85)90027-8","DOIUrl":"10.1016/0167-899X(85)90027-8","url":null,"abstract":"<div><p>A study is reported of uniaxial tensile properties over a wide temperature range (293–1173 K) and at different strain rates between 4 × 10⁻⁵ to 4 × 10⁻²s⁻¹ for a high manganese content austenitic steel (Fe-17Mn-10Cr-0.1C) which is an alternative to AISI 316 stainless steel in the material selection for the conceptual tokamak fusion reactor designs. The behaviour of this alloy is similar to that of other high manganese steels, including a strain induced γ(fcc) → ϵ(hcp) martensitic transformation which considerably increases the strain hardening rate and leads to a maximum in ductility near 470 K. Moreover, non-linear statistical analysis of the true stress—true strain data, fitted to several constitutive equations, shows that the best description of plastic flow is given, for the present material, by the <span>Ludwigson law (1971)</span>: <span><span><span><math><mtext>σ = A</mtext><msub><mi></mi><mn><mtext>LU</mtext></mn></msub><mtext>exp</mtext><mtext>(C</mtext><msub><mi></mi><mn><mtext>LU</mtext></mn></msub><mtext>ϵ) + B</mtext><msub><mi></mi><mn><mtext>LU</mtext></mn></msub><mtext>ϵ</mtext><msup><mi></mi><mn>n</mn></msup><msub><mi></mi><mn><mtext>p</mtext></mn></msub><mtext>LU</mtext></math></span></span></span> or by the <span>Matteazzi—Petrone—Piatti law (1982)</span> if the strain rate effect is also considered: <span><span><span><math><mtext>σ = K</mtext><msub><mi></mi><mn>M</mn></msub><mtext>[1 + m</mtext><msub><mi></mi><mn>M</mn></msub><mtext>ln</mtext><mtext>ϵ</mtext><mtext>̇</mtext><mtext>ϵ</mtext><mtext>̇</mtext><msub><mi></mi><mn>0</mn></msub><mtext>)] ϵ</mtext><msup><mi></mi><mn>n</mn></msup><msub><mi></mi><mn><mtext>p</mtext></mn></msub><mtext>M</mtext><msup><mi></mi><mn><mtext>[1 + C</mtext><msub><mi></mi><mn>M</mn></msub><mtext>ln</mtext><mtext>ϵ</mtext><mtext>ϵ</mtext><msub><mi></mi><mn>0</mn></msub><mtext>)]</mtext></mn></msup><mtext>.</mtext></math></span></span></span> where σ = true stress, ϵ_p = true plastic strain, ϵ_p = true strain rate, ϵ_p = reference strain rate and the other parameters are material constants.</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 391-406"},"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)90027-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80704367","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}

{"title":"A comparison of pulsed and steady-state tokamak reactor burn cycles. Part I: Thermal effects and lifetime limitations","authors":"D.A. Ehst,&nbsp;Y. Cha,&nbsp;A.M. Hassanein,&nbsp;S. Majumdar,&nbsp;B. Misra,&nbsp;H.C. Stevens","doi":"10.1016/0167-899X(85)90020-5","DOIUrl":"10.1016/0167-899X(85)90020-5","url":null,"abstract":"<div><p>Four distinct operating modes have been proposed for tokamaks, and consequently a variety of thermal environments can be postulated for future reactor subsystems. Our study concentrates on lifetime limitations associated with fluctuating thermal loads on the first wall, limiter or divertor plates, and in the breeding blanket. Simultaneous failure from thermal fatigue, radiation damage, and disruption-induced erosion is considered, and burn length goals are calculated in order to help achieve high availability for a commercial reactor. In addition, the cost of thermal storage is found as a function of the dwell period between burns of a pulsed cycle; thermal storage is shown to be an expensive requirement for pulsed 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 305-318"},"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)90020-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87672415","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}

{"title":"Effect of first wall flaws on reactor performance","authors":"R.H. Jones,&nbsp;R.W. Conn,&nbsp;R.F. Schafer","doi":"10.1016/0167-899X(85)90010-2","DOIUrl":"10.1016/0167-899X(85)90010-2","url":null,"abstract":"<div><p>The influence of primary blanket coolant leaks through flaws in the first wall on Tokamak fusion plasma performance is investigated. A one-dimensional, three region radial diffusion model of impurity transport in the plasma is developed. The model includes plasma removal and recycling in the boundary layer and is used to correlate plasma performance with coolant leakage rates. In turn, coolant leak rates are estimated via molecular or viscous flow, as appropriate through both elastically loaded cracks and cracks opened by creep. Fatigue and environmentally induced subcritical crack growth and unstable crack growth flaw sizes are estimated for austenitic and ferritic stainless steels and compared to the coolant leak rate flaw sizes. The materials and plasma analyses are combined to yield estimates of the critical leak rate for three coolant candidates: helium, water, and lithium. The results indicate that the maximum-leak-rate (MLR) flaw sizes for helium, water and lithium are 5 to 8 mm, 6 to 8 mm and 1.5 to 3 × 10⁴ mm, respectively, for elastically loaded cracks and 0.1 to 0.3 mm, 0.2 to 0.3 mm, and 700 to 1500 mm, respectively, for cracks opened by creep. The threshold flaw sizes for fatigue and corrosion fatigue subcritical crack growth of Type 316 stainless steel and HT-9 range from 0.2 to 2 mm and the flaw sizes for unstable crack growth of irradiated 316 stainless steel and HT-9 are 4 mm and 50 mm, respectively. These results suggest that the MLR sizes for helium and water are among the smallest flaws that may affect reactor performance and that the threshold for subcritical crack growth in fatigue is a critical material property. Also, creep processes are shown to have a significant effect on the MLR flaw size.</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 175-188"},"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)90010-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79273735","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}

{"title":"Protective interior wall for the doublet III vacuum vessel","authors":"R.D. Phelps,&nbsp;P.M. Anderson","doi":"10.1016/0167-899X(85)90025-4","DOIUrl":"10.1016/0167-899X(85)90025-4","url":null,"abstract":"<div><p>The design and installation of a protective inner wall for a tokamak vacuum vessel is described. This wall is a series of small rectangular plates attached to the existing walls with threaded fasteners. The design effectively conceals and protects all mounting hardware beneath the plate array, while providing a substantial surface area that will absorb plasma energy.</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 375-381"},"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)90025-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83387156","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}

{"title":"Inelastic structural analysis of the mars tandem mirror reactor","authors":"J.P. Blanchard,&nbsp;N.M. Ghoniem","doi":"10.1016/0167-899X(85)90003-5","DOIUrl":"10.1016/0167-899X(85)90003-5","url":null,"abstract":"<div><p>The effects of radiation on the structural performance of fusion reactor structures is recognized as a major issue for the development of fusion reactor technology. Neutron irradiation changes the mechanical properties of structural components resulting in a general degradation of these properties. In addition to the mechanical loads (pressure and weight) and the thermal strains, non-uniform inelastic strain fields are induced by radiation swelling and creep in fusion structures. In this paper, we describe a new computer code, STAIRE, for <span><math><mtext>ST</mtext></math></span>ress <span><math><mtext>A</mtext></math></span>nalysis <span><math><mtext>I</mtext></math></span>ncluding <span><math><mtext>R</mtext></math></span>adiation <span><math><mtext>E</mtext></math></span>ffects. This code is based on standard beam theory for pipe-bends. The theory is modified in two areas: (1) consideration of the pipes' cross-section deformation as the radius of curvature changes; and (2) inclusion of inelastic radiation and thermal strains (swelling and creep). An efficient analytical/numerical approach is developed for the solution of indeterminate beam problems. As an application of the method, the stress distribution and deflections of toroidal blanket pipes in the Mirror Advanced Reactor Study (MARS) are evaluated. Swelling strains are identified as a major source of stress and deformation in the proposed blanket design, and possible solutions to the problem are outlined.</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 19-27"},"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)90003-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80248013","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}

{"title":"Effect of plasma motion in disruption on the electromagnetic behavior of a vacuum vessel","authors":"Kimihiro Ioki,&nbsp;Setsuo Niikura,&nbsp;Katsuo Namiki,&nbsp;Fushiki Matsuoka","doi":"10.1016/0167-899X(85)90035-7","DOIUrl":"10.1016/0167-899X(85)90035-7","url":null,"abstract":"<div><p>Eddy current and magnetic force analysis during disruption of single-null divertor plasma has been carried out for a vacuum vessel of a tokamak device by using a code system, MATEX, which was developed for this purpose. The electromagnetic behavior during a disruption with plasma motion is emphasized in this study. The large upward or downward force induced on the vacuum vessel is due to midplane-asymmetric poloidal field configuration, and is intensified by vertical plasma motion in disruption. On the other hand, the saddle-like force at the inboard section of the flange is increased by the horizontal plasma motion during disruption. The results indicate that the analysis of the effect of plasma motion is very important to the design of a vacuum vessel and its support structure.</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":"3 1","pages":"Pages 63-71"},"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)90035-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86446935","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}