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International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A

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1.Control of tritium in FFHR-2 self-cooled Flibe blanket

机译：控制FFHR-2自冷覆盖毛毯氚的控制
- 作者：Satoshi Fukada;Akio Morisaki;Akio Sagara;Takayuki Terai
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- flibe;
- tritium;
- blanket;
- redox control;
- permeation;
- beryllium;
2.Review of the activity in Russia in the area of fusion nuclear technology

机译：融合核技术领域俄罗斯活动述评
- 作者：Y. Strebkov;V. Belyakov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion;
- blanket;
- in-vessel components;
- test blanket module;
3.Analysis on fuel cycle schemes in the dual-cooled waste transmutation blanket for the FDS-I

机译：FDS-I双冷废嬗变毯中燃料循环方案分析
- 作者：X.Zhu;S.Zheng;J.Li
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- subcritical;
- blanket;
- fuel cycle;
- transmutation;
4.Japanese activities in ITER transitional arrangements

机译：日本活动在ITER过渡安排
- 作者：M. Mori
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion;
- ITER;
- tokamak;
- magnet;
- vacuum vessel;
- blanket;
5.Dynamic erosion and deposition on carbon and tungsten due to simultaneous bombardment with deuterium and beryllium ions in plasmas

机译：由于氘和铍离子在等离子体中的同时轰击导致碳和钨对碳和钨的动态腐蚀和沉积
- 作者：Shinji Ebisu;Kaoru Ohya;Tetsuo Tanabe
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- erosion;
- deposition;
- carbon;
- tungsten;
- beryllium;
- computer simulation;
6.Notch toughness evaluation of diffusion-bonded joint of alumina dispersion-strengthened copper to stainless steel

机译：氧化铝分散铜扩散接头的Notch韧性评价 - 加强铜与不锈钢
- 作者：H. Nishi
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- diffusion-bonded joint;
- notched specimen;
- instrumented charpy test;
- charpy absorbed energy;
- elasto-plastic analysis;
7.Study of surface and bulk instabilities in MHD duct flow with imitation of insulator coating imperfections

机译：模仿绝缘子涂层缺陷的MHD管道流量的表面和散装稳定性
- 作者：Zengyu Xu;Chuanjie Pan;Wenhao Wei;Weishan Kang
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- liquid metal;
- MHD instability;
- insulator coating imperfections;
8.The RF concept of experimental breeding module for testing in ITER

机译：实验育种模块的RF概念，用于磨练测试
- 作者：A.Yu. Leshukov;V.G. Kovalenko;V.V. Poliksha;M.N. Sviridenko;A.V. Strizhov;Yu.S. Strebkov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- sub-module;
- breeding element;
- helium-cooling system;
9.Determination of hydrogen solubility in lead lithium using sole device

机译：唯一装置测定铅锂中氢溶解度
- 作者：A. Aiello;A. Ciampichetti;G. Benamati
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- lead lithium;
- solubility;
10.Lithium compatibility of insulator coatings fabricated by RF sputtering method

机译：由RF溅射法制造绝缘体涂层的锂兼容性
- 作者：Akihiko Sawada;Akihiro Suzuki;TakayukiTerai
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- lithium;
- MHD;
- coating;
- corrosion;
- insulator;
- ceramic;
11.Characterization of JT-60U exhaust gas during experimental operation

机译：实验操作期间JT-60U废气的表征
- 作者：K. Isobe;H. Nakamura;A. Kaminaga;K. Tsuzuki;S. Higashijima;M. Nishi;Y. Kobayashi;S. Konishi
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- JT-60U;
- fuel cycle;
- carbon compounds;
- exhaust gas;
- tokamak exhaust processing (TEP);
12.RF TBMs for ITER tests

机译：RF TBMS for Iter测试
- 作者：I.R. Kirillov;G.E. Shatalov;YU.S. Strebkov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion;
- blanket;
- ITER test module;
- helium;
- ceramics;
- lithium;
13.Control of nitrogen concentration in liquid lithium by iron-titanium alloy

机译：铁 - 钛合金控制液体锂中氮浓度的控制
- 作者：Shinji Hirakane;Toshiaki Yoneoka;Satoru Tanaka
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- liquid lithium;
- nitrogen;
- Fe-Ti alloy;
- hot trap method;
14.Joining technologies of reduced activation ferritic/martensitic steel for blanket fabrication

机译：橡皮布制造减少激活铁素体/马氏体钢技术
- 作者：T. Hirose;K. Shiba;M. Ando;M. Enoeda;M. Akiba
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- TBM fabrication;
- Joining;
- HIP;
- SPS;
- Ferritic steel;
15.Preparations for ITER construction in the European Union

机译：欧洲联盟的ITER建设准备
- 作者：E. Di Pietro;R. Andreani;D. Maisonnier
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER construction;
- cadarache;
- EISS project;
- safety;
- licensing;
- codes;
- fusion;
- ITER site;
16.Model calculation of tritium release behavior from lithium titanate

机译：钛酸锂氚释放行为的模型计算
- 作者：Daiju Yamaki;Shiro Jitsukawa
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- blanket materials;
- breeding materials;
- ceramics;
- hydrogen;
- neutron irradiation;
- tritium;
17.Russian Federation contribution to the ITER project

机译：俄罗斯联邦对ITER项目的贡献
- 作者：V.A. Belyakov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- fusion reactor;
- tokamak;
- fusion technology;
18.Material probe analysis of boronized wall in LHD

机译：LHD硼化墙体的材料探测分析
- 作者：Y. Nobuta;N. Ashikawa;T. Hino;Y. Yamauchi;Y. Hirohata;K. Nishimura;A. Sagara;S. Masuzaki;N. Noda;N. Ohyabu;A. Komori;O. Motojima
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- boronization;
- LHD;
- material probe;
- hydrogen retention;
- helium retention;
19.Improvement of the CFC structure to withstand high heat flux

机译：改进CFC结构以承受高热通量
- 作者：S. Pestchanyi;I. Landman
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- CFC;
- erosion;
- ITER;
- divertor armour;
- high heat flux;
20.Interactions between molten Flibe and metallic Be

机译：熔融素和金属之间的相互作用
- 作者：M. Hara;Y. Hatano;M.F. Simpson;G.R. Smolik;J.P. Sharp;Y. Oya;K. Okuno;M. Nishikawa;T. Terai;S. Tanaka;R.A. Anderl;D.A. Petti;D.-K. Sze
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- 2LiF-BeF_2;
- Be dissolution;
- fluorine potential;
- reductant;
- JUPITER-II;
21.Structural concept of Japanese solid breeder test blanket modules for ITER

机译：日本固体育种者测试毯子模块的结构概念
- 作者：Yasunobu Nomoto;Satoshi Suzuki;Koichiro Ezato;Takanori Hirose;Daigo Tsuru;Hisashi Tanigawa;Toshihisa Hatano;Mikio Enoeda;Masato Akiba
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- solid breeder TBM;
- structural concept;
- coolant flow route;
- purge gas flow route;
22.Development of a tritium separation process using SDGC

机译：使用SDGC开发三氚分离过程
- 作者：Y. Morimoto;S. Kojima;T. Sasaki;M. Matsuyama;M. Hara;S. Akamaru;M. Numata;T. Kato;K. Watanabe
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- self-developing gas chromatography;
- Pd-Pt alloy;
- tritium;
- isotope separation;
23.Helium thermal desorption and retention properties of V-4Cr-4Ti alloy used for first wall of breeding blanket

机译：V-4CR-4TI合金的氦热解吸和保留性能，用于养殖毯子的第一墙
- 作者：Yuko Hirohata;T. Yamada;Y. Yamauchi;T. Hino;T. Nagasaka;T. Muroga
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- vanadium alloy;
- ion irradiation;
- helium;
- thermal desorption;
24.Low cycle fatigue behavior of JLF-1 steel at elevated temperatures

机译：高温下JLF-1钢的低循环疲劳行为
- 作者：Huailin Li;Arata Nishimura;Zaixin Li;Takuya Nagasaka;Takeo Muroga
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- reduced activation ferritic/martensitic steels;
- low cycle fatigue;
- elevated temperature;
- serration;
- dynamic strain ageing;
25.RF test blanket sub-module with ceramic breeder and helium cooling for test in ITER

机译：RF测试毯子子模块，陶瓷饲养员和氦气冷却用于测试
- 作者：V. Kovalenko;V. Kapyshev;A. Leshukov;V. Poliksha;G. Shatalov;Yu. Strebkov;A. Strizhov;M. Sviridenko
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion;
- blanket;
- test blanket sub-module;
- helium;
- ceramic;
26.Breeder foam: an innovative low porosity solid breeder material

机译：繁殖者泡沫：一种创新的低孔隙率固体饲养剂材料
- 作者：S. Sharafat;N. Ghoniem;M. Sawan;A. Ying;B. Williams
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- solid breeder;
- ceramic foam;
- cellular ceramic;
- foam properties;
- foam processing;
- foam applications;
27.Study of tritium migration in liquid Li_2BeF_4 with ab initio molecular dynamics

机译：AB Initio分子动力学液体Li_2Bef_4氚迁移的研究
- 作者：A. Klix;A. Suzuki;T. Terai
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- flibe (Li_2BeF_4);
- liquid breeder;
- breeding blanket;
- tritium;
- molecular dynamics;
28.Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr_2O_3-SiO_2 including CrPO_4 (out-of-pile tests)

机译：CR_2O_3-SiO_2陶瓷涂层包括CRPO_4的陶瓷涂层，包括CRPO_4的氢异形渗透的研究（桩型试验）
- 作者：T.V. Kulsartov;K. Hayashi;M. Nakamichi;S.E. Afanasyev;V.P. Shestakov;Y.V. Chikhray;E.A. Kenzhin;A.N. Kolbaenkov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- hydrogen;
- deuterium;
- permeability;
- permeation reduction factor;
- F82H;
- ceramic coating;
29.Feasibility study on the blanket tritium recovery system using the palladium membrane diffuser

机译：使用钯膜扩散器的毯子氚蒸馏系统的可行性研究
- 作者：Yoshinori Kawamura;Mikio Enoeda;Toshihiko Yamanishi;Masataka Nishi
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- solid breeder blanket;
- blanket tritium recovery;
- sweep gas;
- palladium membrane diffuser;
- tritium;
30.Vapor species evolved from Li_2TiO_3 heated at high temperature under various conditions

机译：在各种条件下在高温下加热Li_2tio_3的蒸气种类
- 作者：T. Hoshino;M. Yasumoto;K. Tsuchiya;K. Hayashi;H. Nishimura;A. Suzuki;T. Terai
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- solid breeder materials;
- Li_2TiO_3;
- vaporization;
- sweep gas;
- atmosphere-controlled high-temperature mass spectrometer;
31.Tritium control modelling for a helium cooled lithium-lead blanket of a fusion power reactor

机译：龙骨冷却锂铅橡皮布氚控制模型的氚控制模型
- 作者：W. Farabolini;A. Ciampichetti;F. Dabbene;M.A. Fuetterer;L. Giancarli;G. Laffont;A. Li Puma;S. Raboin;Y. Poitevin;I. Ricapito;P. Sardain
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium;
- permeation;
- fusion blanket;
- lithium-lead;
32.An overview of US ITER test blanket module program

机译：美国拍摄测试毯模块程序的概述
- 作者：A. Ying;M. Abdou;C. Wong;S. Malang;N. Morley;M. Sawan;B. Merrill;D.K. Sze;R. Kurtz;S. Willms;M. Ulrickson;S. Zinkle
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
33.Hydrogen permeability and erosion behavior of W-Pd bimetallic systems

机译：W-PD双金属系统的氢渗透性和侵蚀行为
- 作者：G.P. Glazunov;A.A. Andreev;D.I. Baron;R.A. Causey;A. Hassanein;K.M. Kitayevskiy;A.L. Konotopskiy;V.I. Lapshin;I.M. Neklyudov;A.P. Patokin;A.E. Surkov;E.D. Volkov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- plasma-material interaction;
- tungsten;
- erosion;
- hydrogen;
- permeation;
34.Tensile property of low activation vanadium alloy after liquid lithium exposure

机译：液体锂曝光后低活化钒合金的拉伸性能
- 作者：Takuya Nagasaka;Takeo Muroga;Meimei Li;David T. Hoelzer;Steven J. Zinkle;Martin L. Grossbeck;Hideki Matsui
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- first wall/blanket materials;
- impurity effect;
- mechanical property;
35.Integration of the EU HCPB Test Blanket Module system in ITER

机译：EU HCPB测试毯模块系统的集成在ITER中
- 作者：H. Neuberger;L.V. Boccaccini;R. Meyder
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- TBM-integration;
- port plug;
- interfaces;
- pipe integration cask;
- welding tools;
36.Recent progress of ITER FW/blanket design and preparations for fabrication

机译：艾尔FW /毯子设计和制备的最新进展
- 作者：K. Ioki;F. Elio;M.Nakahira;J.Ohmori;M. Shimada;M. Sugihara;X. Wang
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- blanket;
- first wall;
- attachments;
- supports;
- dynamic effect;
37.A design study for tritium recovery system from cooling water of a fusion power plant

机译：融合电厂冷却水的氚回收系统设计研究
- 作者：Toshihiko Yamanishi;Yasunori Iwai;Yoshinori Kawamura;Masataka Nishi
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium;
- water detritiation;
- blanket;
- water distillation;
- chemical exchange;
- electrolysis cell;
38.Monitoring of tritium in diluted gases by detecting bremsstrahlung X-rays

机译：通过检测Bremsstrahlung X射线监测稀释气体的氚
- 作者：W.M. Shu;M. Matsuyama;T. Suzuki;M.F. Nishi
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium;
- monitoring;
- bremsstrahlung X-rays;
- absorption coefficient;
39.Tritium release from neutron-irradiated Transport in porous sintered pellets

机译：中子辐照颗粒中的中子辐照传输的氚释放
- 作者：Takaaki Tanifuji;Daiju Yamaki;Shiro Jitsukawa
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium;
- Li_2O;
- square-root law;
- micro-pore diffusion;
40.Optimal configuration of neutron reflector in He-cooled molten Li blanket

机译：HE-COODED MOLTTTOL LI毯子中子反射器的最佳配置
- 作者：Beomseok Han;Yonghee Kim;Chang Hyo Kim
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- He-cooled molten Li blanket;
- TBR;
- Neutron reflector;
- Neutronics;
- MCCARD;
41.Behavior of actively cooled mock-ups with plasma sprayed tungsten coating under high heat flux conditions

机译：在高热通量条件下激动地用血浆喷涂钨涂层的行为
- 作者：K. Tokunaga;Y. Kubota;N. Noda;Y. Imamura;A. Kurumada;N. Yoshida;T. Sogabe;T. Kato;B. Schedler
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tungsten;
- coating;
- high heat flux;
- divertor;
- fusion device;
42.Overview of design and RD of test blankets in Japan

机译：日本试卷设计与研发概述
- 作者：Mikio Enoeda;Masato Akiba;Satoru Tanaka;Akihiko Shimizu;Akira Hasegawa;Satoshi Konishi;Akihiko Kimura;Akira Kohyama;Akio Sagara;Takeo Muroga
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- test blanket module;
- water-cooled solid breeder blanket;
- helium-cooled solid breeder blanket;
- liquid breeder;
43.Breeding Blanket Modules testing in ITER: An international program on the way to DEMO

机译：繁殖毯子模块测试中的测试：演示途中的国际计划
- 作者：L. Giancarli;V. Chuyanov;M. Abdou;M. Akiba;B.G. Hong;R. Lasser;C. Pan;Y. Strebkov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- TBWG;
- test blanket module;
- TBM;
- breeding blanket;
44.Topology of compressed pebble beds

机译：压缩鹅卵石床的拓扑
- 作者：J. Reimann;R.A. Pieritz;R. Rolli
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- pebble bed;
- thermal-mechanical behaviour;
- microtomography;
- co-ordination number;
- contact surfaces;
45.Ablation of hydrogen-implanted graphite target using pulsed laser beam

机译：利用脉冲激光束消融氢气注入石墨靶
- 作者：Youichi Sakawa;Kouji Sato;Takahiro Shibahara;Tetsuo Tanabe
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- laser ablation;
- graphite target;
- tritium retention;
- tritium removal;
- Nd:YAG laser;
46.Critical heat flux loading experiments on CVD-W coating in the TEXTOR tokamak

机译：临界热通量在Tokamak中CVD-W涂层加载实验
- 作者：T. Hirai;A. Kreter;J. Linke;J. Malzbender;T. Ohgo;V. Philipps;G. Pintsuk;A. Pospieszczyk;Y. Sakawa;G. Sergienko;T. Tanabe;Y. Ueda;M. Wada
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- CVD;
- tungsten;
- coating;
- high heat load;
- tokamak;
- TEXTOR;
47.He-cooled divertor for DEMO: Experimental verification of the conceptual modular design

机译：用于演示的He-Cooled Devertor：实验验证概念模块化设计
- 作者：P. Norajitra;A. Gervash;R. Giniyatulin;T. Ihli;W. Krauss;R. Kruessmann;V. Kuznetsov;A. Makhankov;I. Mazul;I. Ovchinnikov
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- helium-cooled divertor;
- tungsten components;
- high-temperature brazing;
- gas puffing experiment;
- high-heat-flux experiment;
48.Hydrogen retention and depth profile in divertor tiles of Jt-60 exposed to hydrogen discharges

机译：JT-60的vertiver瓦片的氢保持和深度曲线暴露于氢气排放
- 作者：A. Yoshikawa;Y. Hirohata;Y. Oya;T. Shibahara;M. Oyaidzu;T. Arai;Y. Gotoh;K. Masaki;N. Miya;K. Okuno;T. Tanabe
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- hydrogen retention;
- Re-deposited layer;
- SIMS;
- TDS;
- SEM;
- JT-60;
49.Helium irradiation effects for deuterium retention in boron coating films

机译：硼涂膜中氘保留的氦辐照效应
- 作者：T. Takeda;A. Yoshikawa;M. Oyaidzu;T. Nakahata;Y. Nishikawa;H. Kimura;Y. Onishi;H. Miyauchi;Y. Oya;A. Sagara;N. Noda;K. Okuno
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- helium irradiation prior to deuterium;
- deuterium retention;
- boron coating film;
- PACVD;
- TDS;
50.Experimental study of lithium free-surface flow for IFMIF target design

机译：IFMIF靶设计锂自由表面流动的实验研究
- 作者：H. Kondo;A. Fujisato;N. Yamaoka;S. Inoue;S. Miyamoto;T. Iida;H. Nakamura;M. Ida;I. Matushita;T. Muroga;H. Horiike
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- IFMIF target;
- liquid metal;
- free surface flow;
51.Hydrogen inventories in the vacuum pumping systems of ITER

机译：磨料的真空泵系统中的氢库存
- 作者：Christian Day;A. Antipenkov;I.-R. Cristescu;M. Dremel;G. Federici;H. Haas;V. Hauer;A. Mack;D.K. Murdoch;M. Wykes
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- vacuum;
- tritium;
- cryosorption;
- safety;
- hydrogen;
52.Long term performances assessment of a water detritiation system components

机译：长期性能评估水脱裂系统组件
- 作者：I. Cristescu;I.-R. Cristescu;L. Doerr;M. Glugla;D. Murdoch;S. Welte
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium;
- water detritiation;
- isotopic catalytic exchange;
- solid polymer electrolyte;
53.Numerical analysis of MHD flow and heat transfer in a poloidal channel of the DCLL blanket with a SiCf/SiC flow channel insert

机译：具有SICF / SIC流动通道插入件DCLL橡皮布块的MHD流量和传热传热的数值分析
- 作者：S. Smolentsev;M. Abdou;N.B. Morley;M. Sawan;S. Malang;C. Wong
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- DCLL blanket;
- magnetohydrodynamics;
- heat transfer;
54.Breeding blanket design and systems integration for a helium-cooled lithium-lead fusion power plant

机译：氦气冷却锂引线融合电厂的繁殖毯设计与系统集成
- 作者：A. Li Puma;J.L. Berton;B. Branas;L. Buehler;J. Doncel;U. Fischer;W. Farabolini;L. Giancarli;D. Maisonnier;P. Pereslavtsev;S. Raboin;J.-F. Salavy;P. Sardain;J. Szczepanski;D. Ward
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- power plant;
- HCLL blanket;
- integration;
- efficiency;
55.ITER fuel cycle RD: Consequences for the design

机译：ITER燃油循环研发：设计的后果
- 作者：M. Glugla;D.K. Murdoch;A. Antipenkov;S. Beloglazov;I. Cristescu;I.-R. Cristescu;C. Day;R. Laesser;A. Mack
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- tritium plant;
- fuel cycle design;
- vacuum pumping;
56.Deuterium retention of low activation ferritic steel and boronized wall in JFT-2M

机译：氘保留低激活铁素体钢和JFT-2M的硼化壁
- 作者：Y. Yamauchi;K. Yamaguchi;Y. Hirohata;M. Hashiba;T. Hino;K. Tsuzuki;Y. Kusama
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- JFT-2M;
- material probe;
- ferritic steel;
- deuterium retention;
- boronization;
57.A neutronic feasibility study on Be-free He-cooled solid breeder blanket

机译：无可无甲固体种植毯的中性可行性研究
- 作者：Beomseok Han;Yonghee Kim;Bong Guen Hong;Chang Hyo Kim
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- Be-free;
- He-cooled solid breeder blanket;
- Lead neutron multiplier;
- TBR;
- Graphite reflector;
58.Design and development of EC HCD antenna mirrors for ITER

机译：EC H＆CD天线镜的设计与开发ITER
- 作者：K. Takahashi;N. Kobayashi;A. Kasugai;K. Sakamoto
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER EC Hamp;
- CD antenna;
- steering mirror;
- spiral tube;
- miter bend mirror;
59.The European test blanket module systems: Design and integration in ITER

机译：欧洲测试毯模块系统：ITER中的设计和集成
- 作者：L.V. Boccaccini;J.-F. Salavy;R. Laesser;A. Li Puma;R. Meyder;H. Neuberger;Y. Poitevin;G. Rampal
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- test blanket;
- ITER;
- liquid breeder;
- solid breeder;
- helium cooling;
60.Carbon impurity behavior on plasma facing surface of tungsten

机译：钨血浆表面上的碳杂质行为
- 作者：Y. Ueda;M. Fukumoto;I. Sawamura;D. Sakizono;T. Shimada;M. Nishikawa
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tungsten;
- carbon;
- plasma facing materials;
- material mixing;
61.Preparation of ITER construction and operation

机译：准备迭代建设与运作
- 作者：Y. Shimomura
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion reactor;
- tokamak;
- ITER;
- plasma;
- remote handling;
- tritium;
62.Moderate tritium properties in lithium-tin alloy as a liquid breeder/coolant

机译：锂 - 锡合金中适度的氚特性作为液体种植/冷却剂
- 作者：Yi Kang;Takayuki Terai
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- lithium-tin;
- tritium;
- liquid blanket;
63.Thermal conductivity of compressed beryllium pebble beds

机译：压缩铍鹅卵石床的导热系数
- 作者：J. Reimann;G. Piazza;H. Harsch
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- beryllium pebbles;
- fusion reactor blanket;
- pebble beds;
- thermal conductivity;
64.Integration of an advanced He-cooled divertor in a DEMO-relevant tokamak geometry

机译：在演示相关的与托卡马克几何中集成先进的He-Cooled Devertor
- 作者：T. Ihli;S. Hermsmeyer;C. Koehly;P. Norajitra
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- helium-cooled divertor;
- DEMO;
- reactor integration;
- multiple jet impingement;
- tungsten;
- layout;
65.Ion and neutron beam analyses of hydrogen isotopes

机译：氢同位素的离子和中子束分析
- 作者：N. Kubota;K. Ochiai;C. Kutsukake;K. Kondo;W.M. Shu;M. Nishi;T. Nishitani
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- hydrogen isotope profile;
- plasma facing material;
- TFTR;
- NRA;
- neutron ERDA;
66.First wall and divertor engineering research for power plant in JAERI

机译：贾里电厂的第一墙和转型工程研究
- 作者：S. Suzuki;K. Ezato;T. Hirose;K. Sato;H. Yoshida;M. Enoeda M. Akiba
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion power plant;
- PFC;
- F82H;
- screw tube;
- HIP bonding;
- thermal fatigue;
67.Overview of the European Union fusion nuclear technologies development and essential elements on the way to DEMO

机译：欧洲联盟融合核技术的概述在演示途中的发展和基本要素
- 作者：R. Andreani;E. Diegele;W. Gulden;R. Laesser;D. Maisonnier;D. Murdoch;M. Pick;Y. Poitevin
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- europe;
- technology;
- materials;
- DEMO;
- blanket;
- IFMIf;
68.Three-dimensional neutronics assessment of dual coolant molten salt blankets with comparison to one-dimensional results

机译：三维中型评估双冷却液熔盐橡皮布与一维效果相比
- 作者：M.E. Sawan;M.Z. Youssef
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- molten salt;
- 3-D neutronics;
- dual coolant;
- tritium breeding;
- nuclear heating;
- radiation damage;
69.EU RD on the ITER First Wall

机译：欧盟R＆D在磨练第一墙上
- 作者：P. Lorenzetto;A. Peacock;I. Bobin-Vastra;L. Briottet;P. Bucci;G. DellOrco;K. Ioki;M. Roedig;P. Sherlock
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER first wall;
- Be/Cu alloy joining;
- Cu alloy/316L SS joining;
70.Study of poisoning effects with the ITER model pump during relevant operation cycles

机译：相关操作周期中浸泡模型泵的中毒效应研究
- 作者：H. Haas;C. Caldwell-Nichols;C. Day;A. Mack;D. Murdoch
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- vacuum;
- hydrogen isotopes;
- cryosorption;
- hydrocarbons;
- water-like impurities;
71.Experimental and numerical analysis on pebble beds used in an ITER Test Module Blanket

机译：射床床上铺面床的实验和数值分析
- 作者：Donato Aquaro;Nicola Zaccari
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- pebble bed;
- alumina;
- breeder blanket;
- conductivity;
- stiffness;
- oedometric;
72.Experimental study of tritium recovery from liquid lithium by yttrium

机译：钇液锂氚回收的实验研究
- 作者：Mika Kinoshita;Satoshi Fukada;Naoya Yamashita;Takeo Muroga;Masabumi Nishikawa
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- lithium;
- tritium;
- yttrium;
- recovery;
- IFMIf;
73.U.S. contributions to ITER

机译：美国对Iter的贡献
- 作者：Ned R. Sauthoff
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- tokamak;
- burning plasmas;
- magnets;
- project management;
- international collaboration;
74.Study on tritium accountancy in fusion DEMO plant at JAERI

机译：Jaeri融合演示工厂氚计算的研究
- 作者：Masataka Nishi;Toshihiko Yamanishi;Takumi Hayashi
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium;
- accountancy;
- control;
- fusion DEMO plant;
75.Overview of research and development activities on fusion nuclear technologies in Japan

机译：日本融合核技术研究与发展活动概述
- 作者：Satoru Tanaka
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fgusion nuclear technology (FNT);
- fusion program;
- blanket engineering;
- fuel processing system;
- fusion safety;
- reactor system design;
76.Overview of comprehensive characterisation of erosion zones on plasma facing components

机译：等离子体面向组件侵蚀区综合表征概述
- 作者：M. J. Rubel;E. Fortuna;A. Kreter;E. Wessel;V. Philipps;K.J. Kurzydlowski
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- graphite;
- erosion;
- plasma facing components;
- fuel inventory;
- TEXTOR;
77.On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER

机译：支持框架对磨机氦冷却锂铅试卷模块核响应的影响
- 作者：P. Chiovaro;P.A. Di Maio;E. Oliveri;G. Vella
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- HCLL test blanket module;
- neutronics;
- nuclear response;
78.Aging effects in uranium tritide

机译：铀氚化的老化作用
- 作者：Rong Li;Ying Sun;Yongjun Wei;Wensheng Guo
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium;
- uranium;
- aging;
- ~3He;
79.Study of heat transfer enhancement/suppression for molten salt flows in a large diameter circular pipe Part Ⅰ: Benchmarking

机译：大直径圆管部熔盐流动的传热增强/抑制的研究Ⅰ：基准
- 作者：J. Takeuchi;S. Satake;R. Miraghaie;K. Yuki;T. Yokomine;T. Kunugi;N.B. Morley;M.A. Abdou
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- FLiBe;
- MHD;
- PIV;
- turbulence;
80.Experimental study of the interaction of ceramic breeder pebble beds with structural materials under thermo-mechanical loads

机译：热机械负荷下结构材料陶瓷饲养卵石床相互作用的实验研究
- 作者：P. Calderoni;A. Ying;T. Sketchley;M.A. Abdou
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion energy;
- gas-cooled blanket;
- lithium meta-titanate;
- silicon carbide;
- creep deformation;
- finite elements;
81.Applicability of β-ray-induced X-ray spectrometry to in situ measurements of tritium retention in plasma-facing materials in ITER

机译：β射线诱导的X射线光谱法在原始物质中氚测量的原位测量的适用性
- 作者：M. Matsuyama;Y. Torikai;N. Bekris;M. Glugla;A. Erbe;W. Naegele;N. Noda;V. Philipps;P. Coad;K. Watanabe
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium retention;
- In situ measurement;
- BIXS;
- plasma-facing materials;
- ITER;
82.Effect of low energy helium irradiation on mechanical properties of 304 stainless steel

机译：低能氦辐射对304不锈钢力学性能的影响
- 作者：T. Kawakami;K. Tokunaga;N. Yoshida
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- helium;
- low energy ion;
- mechanical property;
- surface modification;
- tensile test;
- hardness;
83.Influence of oxygen and carbon on performance of superpermeable membranes

机译：氧气和碳对高度耐膜性能的影响
- 作者：Y. Hatano;A. Livshits;Y. Nakamura;A. Busnyuk;V. Alimov;C. Hiromi;N. Ohyabu;K. Watanabe
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- superpermeation;
- tritium;
- recovery;
- niobium;
- vanadium;
84.Correlation between annihilation of irradiation defects and tritium release in neutron-irradiated lithium zirconate

机译：中子辐照锂锆渗透缺陷与氚释放之间的相关性
- 作者：M. Oyaidzu;H. Kimura;A. Yoshikawa;Y. Nishikawa;K. Munakata;M. Okada;M. Nishikawa;K. Okuno
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ceramic breeder;
- irradiation defects;
- E′-center;
- tritium;
- hot-atom chemistry;
85.The tests of liquid metals (Ga, Li) as plasma facing components in T-3M and T-11M tokamaks

机译：液体金属（GA，Li）作为T-3M和T-11M Tokamak的等离子体面向等离子体
- 作者：S.V. Mirnov;V.A. Evtikhin
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tokamak;
- plasma facing components;
- liquid metal;
- splashing;
- sputtering;
86.The cascading pebble divertor for the spherical tokamak power plant

机译：球形卵石转向器为球形托卡卡马克发电厂
- 作者：G.M. Voss;A. Bond;S. Davis;M. Harte;R. Watson
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- cascading;
- pebble;
- divertor;
- spherical tokamak;
87.Simulation of redeposition patterns of hydrocarbons released from carbon target in divertors

机译：岩体中碳靶烃中烃染色模式的模拟
- 作者：Kaoru Ohya;Tetsuo Tanabe;Jun Kawata
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- redeposition;
- hydrocarbon;
- gap;
- divertor;
- computer simulation;
88.Direct numerical simulation of MHD flow with electrically conducting wall

机译：导电壁的MHD流量的直接数值模拟
- 作者：S. Satake;T. Kunugi;N. Naito;A. Sagara
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- MHD;
- turbulent flow;
- conducting wall;
- insulated wall;
- vortical structures;
89.Erosion of carbon deposition layer by hydrogen RF plasma

机译：氢rf等离子体腐蚀碳沉积层
- 作者：K. Katayama;H. Nagase;C. Nishinakamura;T. Takeishi;M. Nishikawa
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- carbon deposition layer;
- erosion yield;
- H/C;
- RF plasma;
90.Water vapor decomposition reaction on ZrNi alloy

机译：ZrnI合金对水蒸气分解反应
- 作者：Takao Kawano
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ZrNi alloy;
- water vapor decomposition;
- hydrogen extraction;
- tritium process;
91.Experimental examination of heat removal limitation of screw cooling tube at high pressure and temperature conditions

机译：高压和温度条件下螺杆冷却管散热限制的实验检查
- 作者：Koichiro Ezato;Satoshi Suzuki;Masayuki Dairaku;Masato Akiba
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- high heat flux removal;
- plasma-facing components;
- PFC;
- fusion;
- divertor;
- screw tube;
- heat transfer;
- critical heat flux;
92.Development of tritium production measurement method for in-pile tests of fusion blanket in the JMTR

机译：JMTR中融合毯桩桩桩桩桩试验的研制
- 作者：Y. Nagao;K. Tsuchiya;T. Ishida;H. Kawamura;M. Niimi
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- tritium-measuring system;
- tritium monitor;
- JMTR;
- fusion blanket in-pile test;
93.Present status of hydrogen isotope separation by CECE process at the NIFS

机译：NIFS中CECE工艺氢同位素分离的现状
- 作者：T. Sugiyama;Y. Asakura;T. Uda;T. Shiozaki;Y. Enokida;I. Yamamoto
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- water detritiation;
- hydrogen isotope separation;
- tritium;
- CECE;
- packed bed;
- hydrophobic Pt catalyst;
94.Numerical research on heat transfer enhancement for high Prandtl-number fluid

机译：高普朗特数流体传热增强的数值研究
- 作者：Shin-Ya Chiba;Kazuhisa Yuki;Hidetoshi Hashizume;Saburo Toda;Akio Sagara
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- fusion;
- blanket;
- flibe;
- high prandtl-number;
- heat transfer enhancement;
95.Numerical analysis of MHD flow structure behind a square rod

机译：方形杆后面MHD流动结构的数值分析
- 作者：M. Satake;K. Yuki;S. Chiba;H. Hashizume
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- MHD;
- k-ε;
- square rod;
- twin vortex;
- karman's vortex street;
96.Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour

机译：基准锻炼的进展分析LITHES育种卵石床热电机制
- 作者：G. DellOrco;P.A. Di Maio;R. Giammusso;A. Malavasi;L. Sansone;A. Tincani;G. Vella
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- thermo-mechanical behaviour;
- lithiated ceramics;
- breeder;
97.Introduction of tritium transfer step at surface layer of breeder grain for modeling of tritium release behavior from solid breeder materials

机译：种植粒子表面层的氚转移步骤介绍纯化剂材料氚释放行为造型
- 作者：T. Kinjyo;M. Nishikawa;T. Tanifuji;M. Enoeda
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- solid breeder materials;
- tritium release;
- surface water;
- mass transfer resistance;
98.Deuterium retention and desorption behavior of boron-titanium as first wall material of fusion experimental device

机译：硼 - 钛作为融合实验装置第一壁材料的氘保留和解吸行为
- 作者：T. Hino;Y. Hashiba;Y. Yamauchi;Y. Hirohata;K. Nishimura;N. Ashikawa;S. Masuzaki;A. Sagara;N. Noda;N. Ohyabu;A. Komori;O. Motojima
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- boron-titanium;
- deuterium retention;
- desorption;
- temperature;
- fuel hydrogen recycling;
99.Progress of plasma surface interaction study on low activation materials

机译：低活化材料等离子体表面相互作用研究进展
- 作者：T. Hino;E. Hayashishita;T. Yamada;X. Liu;A. Kohyama;Y. Yamauchi;Y. Hirohata;Y. Nobuta
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ferritic steel;
- fuel hydrogen retention;
- vanadium alloy;
- helium retention;
- SiC/SiC composite;
- helium permeability;
100.JET contributions to ITER technology issues

机译：喷气机贡献对ITER技术问题
- 作者：C. Grisolia;S. Rosanvallon;P. Coad;N. Bekris;J. Braet;D. Brennan;B. Brichard;G. Counsell;C. Day;J. Likonen;G. Piazza;C. Poletiko;M. Rubel;A. Semerok
- 会议名称：《International Symposium on Fusion Nuclear Technology(ISFNT-7) pt.A》 | 2006年
- ITER;
- JET;
- technology;
- tritium inventory control;
- Ramp;
- D program;