第30卷 2010年

第1期

一體化壓水堆雙恒定運(yùn)行方案控制策略研究 … ………………………… 徐 文奇,彭敏俊,劉建閣,等

穩(wěn)壓器壓力水位控制系統(tǒng)建模與仿真 ……………………………………… 馬 進(jìn),劉長良,李淑娜

EPR緩解SGTR事故的設(shè)計特點 … …………………………………………………………… 鄭 華

中國實驗快堆汽輪機(jī)的首次沖轉(zhuǎn)… …………………………………………………… 張亞勃,張東輝

GO法在CEFR核級循環(huán)冷卻水系統(tǒng)的動態(tài)可靠性分析 … ………………………… 楊麗芳,楊紅義

超冷中子源的發(fā)展現(xiàn)狀 ……………………………………………………… 余小玲,封啟璽,馮全科

圓柱形帶反射層反應(yīng)堆的數(shù)值傳熱計算 …………………………………… 劉會娟,張 敏,彭文杰

豎直矩形窄流道內(nèi)過冷沸騰汽泡生長特性及對換熱的影響 … ………… 陳 德奇,潘良明,袁德文,等

先進(jìn)核能系統(tǒng)設(shè)計分析軟件與數(shù)據(jù)庫研發(fā)進(jìn)展… ……………………… 吳 宜燦,胡麗琴,龍鵬程,等

聚變裂變混合發(fā)電堆水冷包層中子學(xué)設(shè)計分析… ……………………… 蔣 潔瓊,王明煌,陳 忠,等

聚變裂變混合發(fā)電堆水冷包層熱工水力學(xué)設(shè)計分析… ………………… 金 鳴,蔣潔瓊,劉松林,等

天然鈾資源的有效利用 ………………………………………………………………………… 溫鴻鈞

核電廠廠址選擇中飛機(jī)墜毀事件的評價程序及概率確定方法… ……… 鄭 啟燕,張力軍,黃偉奇,等

第2期

快中子堆啟堆試驗 ……………………………………………………………………………… 王 洲

基于虛擬儀器技術(shù)的池式熱堆Rossi-α測量裝置設(shè)計 … ……………… 曾 和榮,馮琦杰,谷振軍,等

聚變堆用CLAM鋼管件冷推彎成形數(shù)值模擬及試驗研究 …………… 郭 訓(xùn)忠,陶 杰,劉紅兵,等

中國實驗快堆C31系統(tǒng)HPGeγ譜儀效率刻度的點源模擬 … ………… 熊 文彬,段天英,仇春華,等

概率安全分析平臺NFRisk設(shè)計與驗證 … ……………………………… 胡 文軍,宋 維,任麗霞,等

模塊式高溫氣冷堆三維中子動力學(xué)計算分析 ……………………………… 宋英明,周志偉,馬遠(yuǎn)樂

CANDU堆中鈾-釷自持循環(huán)的研究 ………………………………………………… 王天磊,李金鴻

靜載荷與地震載荷作用下ITER重力支撐系統(tǒng)有限元靜力分析 … …… 梁 尚明,閆喜江,莫春華,等

整體針翅管混合管束滑油冷卻器強(qiáng)化換熱試驗研究… ………………… 牛 廣林,閻昌琪,孫中寧,等

軟化熱處理與預(yù)變形對CLAM鋼塑性的影響分析 …………………… 黃 波,黃群英,李春京,等

液態(tài)金屬回路DRAGON-Ⅱ鋰鉛合金流動與傳熱三維數(shù)值模擬 … …… 汪 衛(wèi)華,朱志強(qiáng),李晉嶺,等

EAST鎢雜質(zhì)輸運(yùn)特性分析 … …………………………………………… 王君一,陳一平,FDS 團(tuán)隊

秦山二期擴(kuò)建工程低溫超壓事故PSA分析 ………………………………………… 李 琳,趙 博

安全殼在事故情況下的完整性分析 ………………………………………… 林誠格,趙瑞昌,劉志弢

第3期

TP2008核數(shù)據(jù)庫研制………………………………………………………………… 劉 萍,王耀清

熱處理對690合金腐蝕性能影響… ……………………………………… 喬 培鵬,張樂福,徐雪蓮,等

傳統(tǒng)共振計算方法改進(jìn)措施的初步可行性研究 … ………………………… 張正習(xí),蔣校豐,張少泓

高溫氣冷堆包覆燃料顆粒破損機(jī)制及失效模型… ……………………… 楊 林,劉 兵,邵友林,等

基于CFD的反應(yīng)堆局部三維流動模型與時空中子動力學(xué)模型耦合研究………………………………………………………………………………………………………… 桂學(xué)文,蔡 琦,陳玉清

池式鈉冷快堆二回路鈉比活度研究 … …………………………………… 王 勇,周培德,楊 勇,等

快堆三維節(jié)塊法程序燃耗模塊的開發(fā)… ………………………………… 楊 曉燕,徐 銤,王 侃,等

中國實驗快堆三廢控制系統(tǒng)… ………………………………………………………… 李 禾,李曉薇

液態(tài)鉛鉍回路設(shè)計研制與材料腐蝕實驗初步研究 … …………………… 吳 宜燦,黃群英,柏云清,等

IPWRs非能動余熱排出系統(tǒng)運(yùn)行特性分析 ………………………………………… 代守寶,彭敏俊

EPR與CPR1000嚴(yán)重事故緩解措施比較 …………………………………………………… 鄭 華

大型壓水堆核電站換料機(jī)的強(qiáng)度分析… ………………………………… 賈 曉峰,周國豐,畢祥軍,等

基于模糊神經(jīng)網(wǎng)絡(luò)的直流蒸汽發(fā)生器壓力協(xié)調(diào)控制 … …………………… 夏國清,艾 明,張 偉

蒙特卡羅程序TRIPOLI自動建模方法研究 … ………………………… 張 俊軍,曾 勤,王國忠,等

中子學(xué)計算多目標(biāo)優(yōu)化程序開發(fā)及其初步應(yīng)用… ……………………… 胡 楊林,劉金超,王明煌,等

結(jié)合幾何的MCNP計算結(jié)果可視化分析系統(tǒng)的研究與實現(xiàn) ………… 范 言昌,龍鵬程,曾 勤,等

第4期

MA以IMF燃料靶組件形式在大型鈉冷快堆中的非均勻嬗變研究 … …… 胡 赟,徐 銤,王 侃

核工程建造過程中不符合項的糾正管理 … ……………………………… 吳 顯明,劉漢剛,劉耀光,等

秦山核電站二期反應(yīng)堆堆芯流量分配數(shù)值分析… ……………………… 張 曙明,李華奇,趙民富,等

基于CSA算法的快堆堆芯燃料管理研究 ……………………………… 楊 曉燕,徐 銤,王 侃,等

中國實驗快堆380 V應(yīng)急交流電力系統(tǒng)的可靠性分析 … ………………… 楊麗芳,楊紅義,胡文軍

電感式單點鈉液位計的研制 ………………………………………………… 陳道龍,康瑞清,李新穎

核動力裝置運(yùn)行支持系統(tǒng)的設(shè)計與開發(fā) … ……………………………… 成 守宇,王 賀,彭敏俊,等

液態(tài)鉛鉍實驗平臺無窗靶水力學(xué)原理驗證實驗段設(shè)計研究 … ………… 祝 玲琳,柏云清,陳 釗,等

屏蔽設(shè)計組合優(yōu)化研究… ……………………………………………………………… 賈小波,石秀安

反應(yīng)堆控制保護(hù)系統(tǒng)監(jiān)測參數(shù)校準(zhǔn) … …………………………………… 王 學(xué)杰,朱世雷,黃 文,等

秦山二期核電廠安全緩解系統(tǒng)的性能指標(biāo)分析 … ………………………… 黃志超,趙 博,祁 軍

基于SSH架構(gòu)的風(fēng)險監(jiān)測系統(tǒng)的設(shè)計與實現(xiàn) ………………………… 王 芳,汪 進(jìn),王家群,等

適于風(fēng)險監(jiān)測系統(tǒng)的零壓縮二元決策圖基本事件排序方法 … ………… 汪 進(jìn),王 芳,王家群,等

數(shù)字化人機(jī)界面設(shè)計的人因工程問題分析 … ……………………………… 王志方,谷鵬飛,張建波

基于A rcGIS Engine開發(fā)的砂巖型鈾礦區(qū)域物化探數(shù)據(jù)處理系統(tǒng) … 韓紹陽,柯 丹,侯惠群,等

松散破碎射氣介質(zhì)氡析出能力的測量與計算 … ………………………… 李 廣悅,丁德馨,陳 翔,等

CHINESE JOURNALOF NUCLEAR SCIENCE AND ENGINEERING

Volume 30 2010

Number 1

Research on ideal steady-state programming control strategy of integrated PWR ………………………………………XU Wen-qi,PENG Min-jun,LIU Jian-ge,et al.

Modeling and simu lation o f p ressurizer dynam ic process in PWR nuclear power plant ……………………………………………………MA Jin,LIU Chang-liang,LIShu-na

Design features formitigating SGTR of EPR … ………………………………………ZHENG Hua

The first rushing of CEFR turbine …………………………ZHANG Ya-bo,ZHANG Dong-hui

The dynamic reliability analysis for the CEFR nuclear-cycle cooling water based on GO methodology ………………………………………………YANG Li-Fang,YANG Hong-Yi

Present statusof ultra-cold neutron source constructions ……………………………………YU Xiao-ling,FENG Qi-xi,FENG Quan-ke

Num erical heat transfer in cylindrical nuclear reactor w ith reflected layer ……………………………………………LIU Hui-juan,ZHANGM in,PENG Wen-jie

An experimental investigation of bubb le grow th and effects on heat transfer in water subcooled flow boiling in a verticalnarrow rectangular channel ……………………………CHEN De-qi,PAN Liang-ming,YUAN De-wen,et al.

Developm ent o f design and analysis software for advanced nuclear system s …………………………………WU Yi-can,HU Li-qin,LONG Peng-cheng,et al.

Neutronics design and analysis of w ater-cooled energy p roduction blanket for a fusion-fission hybrid reactor ………………JIANG Jie-qiong,WANG Ming-huang,CHEN Zhong,et al.

Thermal-hydraulics design and analysisof water-cooled energy production blanket for a fusion-fission hybrid reactor …………………………JIN Ming,JIANG Jie-qiong,LIU Song-lin,et al.

The effective utilization of natural uranium resources ……………………………WEN Hong-jun

Assessment p rocedure and p robability determination m ethods of aircraft crash events in siting for nuclear power p lants ……ZHENG Qi-yan,ZHANG Li-jun,H UANG Wei-qi,et al.

Number 2

Startup operational tests of fast reactors ………………………………………………WANG Zhou

Research and manufacture of Rossi-αm easurement device for pool therm al reactor based on virtual instrum ent technology ……ZENG He-rong,FENG Qi-jie,GU Zhen-jun,et al.

Finite element simulation and experimental study of push-bending processes for CLAM steel elbow ……………………………GUO Xun-zhong,TAO Jie,LIU H ong-bing,et al.

The peak efficiency calibration for the cover gasmonitoring system of CEFR's HPGeγ detector ………………………XIONG Wen-bin,DUAN Tian-ying,QIU Chun-hua,et al.

The design and verification of probabilistic safety analysis platform NFRisk ………………………………………H UWen-jun,SONG Wei,REN Li-xia,et al.

Analysis of the 3D neutron kinetics for MH TGR … …………………………………SONG Ying-ming,ZHOU Zhi-wei,MA Yuan-le

Research on U-Th self-sustaining cycle in CANDU ………………WANG Tian-lei,LI Jin-hong

FEM static analysis for the ITER gravity support system under the combined action of the dead weightand seism ic loads ………LIANG Shang-m ing,YAN Xi-jiang,MOChun-hua,et al.

Experim ental Research on heat transfer enhancementof lubricating-oil coo ler with mixing integral pin-fin tubesand plain tubes …NIU Guang-lin,YAN Chang-qi,SUN Zhong-ning,et al.

Influence of pre-elongation and softening heat treatment on p lasticity of China low activation martensitic steel ……………………HUANG Bo,HUANG Qun-ying,LIChun-jing,et al

Three dimension numerical analysisof flow and heat transfer for Chinese liquid metal LiPb experimental loop Dragon-Ⅱ …………WANGWei-hua,ZH U Zhi-qiang,LIJin-ling,et al

Analysis of tungsten im purity transport property in EAST ……………………………………………WANG Jun-yi,CHEN Yi-ping,FDS Team

PSA analysis of low temperature over pressure event in nuclear power plant ……………………………………………………………………………LI Lin,ZHAO Bo

Containment integrity analysis under acciden ts ……………………………………LIN Cheng-ge,ZHAO Rui-chang,LIU Zhi-tao

Number 3

The development ofm ulti-group constants library TP2008 ………LIU Ping,WANG Yao-qing

Effect of heat treatmentson corrosion resistance of alloy 690 ………………………………QIAO Pei-peng,ZHANG Le-fu,XU Xue-lian,et al.

Preliminary study on the im provement on the conventional resonance calculation method …………………………ZHANG Zheng-xi,JIANG Xiao-feng,ZHANG Shao-hong

The failurem echanism s of HTR coated particle fuel and com puter code ……………………………………………YANG Lin,LIU Bing,SHAO You-lin,et al

Study on coup ling of local three-dimension flow model based on CFD method and space-time neutron kineticsmodel ……………………………GUIXue-wen,CA IQi,CHEN Yu-qing

Study on the sodium specific radioactivity in the second loop of pool-type sodium-cooled fast reactor ……………………………………WANG Yong,ZHOU Pei-de,YANG Yong,et al

Development of burn-up module to three-dimension hexagonal nodalmethod for fast reactor …………………………………………YANG Xiao-yan,XU Mi,WANG Kan,et al

The three wastes control system of CEFRLI ……………………………………He,LIXiao-wei

Preliminary experimental study on the corrosion of structural steels in liquid lead bismuth loop ……………………………………WU Yi-can,HUANG Qun-ying,BA IYun-qing,et al

Analysis on the thermal-hydraulic characteristics for passive residualheat removal system of IPWRs ………………………………………………………DA IShou-bao,PENG Min-jun

Comparison of severe accidentmitigation measures between EPR and CPR1000……………………………………………………………………………ZHENG Hua

Strength analysis of refueling machine for large PWR in nuclear pow er plant …………………………………JIA Xiao-feng,ZHOU Guo-feng,BIXiang-jun,et al.

Pressure coordinated controlbased on fuzzy neural network of once-through steam generator … ……………………………………………XIA Guo-qing,AIM ing,ZHANGWei

Autom aticmodeling for them onte carlo transport TRIPOLI code ………………………………ZHANG Jun-jun,ZENG Qin,WANG Guo-zhong,et al.

Developm ent and app lication of amu lti-objective op timization code for neutronics calculation …………………………HU Yang-lin,LIU Jin-chao,WANG Ming-huang,et al

Research and Imp lementation o f a geometry coup led visual analysis system for MCNP ………………………………FAN Yan-chang,LONG Peng-cheng,ZENG Qin,et al

MA heterogeneous transmutation in large sodium cooled fast reactor as IMF fueled target subassembly ……………………………………………………HU Yun,XU Mi,WANG Kan

Correction administration of inconsistent item during the nuclear engineering construction ………………………WU Xian-ming,LIU Han-gang,LIU Yao-guang,et al.

Num erical analysis of flow distribution at the reator core in let of Qinshan phase-Ⅱreactor …………………………………ZHANG Shu-m ing,LIHua-qi,ZHAO Min-fu,et al.

Optimization of fast reactor in-core fuelmanagementwith CSA ……………………………………………YANG Xiao-yan,XU Mi,WANG Kan,et al.

Reliability analysis of the 380 V emergency AC power supp ly system of the China experimentalfast reactor ………………………………………YANG Li-fang,YANG Hong-yi,HU Wen-jun

Development of induction type single point sodium level gauge …………………………………………CHEN Dao-long,KANG Rui-qing,LIXin-ying

Design o f operator support system for nuclear power plants ………………………………CHENG Shou-yu,WANG He,PENGM in-jun,et al.

Design studies of hydraulic verification test section of w indow less target of liquid lead-bism uth eutectic experimental platform ………ZHU Ling-lin,BAIYun-qing,CHEN Zhao,et al.

Combinatorialoptimization study on shielding design …………………JIA Xiao-bo,SH IXiu-an

Monitoring parameters calibration of nuclear reactor contro l and p rotection system ……………………………………WANG Xue-jie,ZHU Shi-lei,HUANGWen,et al.

MSPIanalysis for QinshanⅡ … ……………………………HUANG Zhi-chao,ZHAO Bo,QIJun

Design and imp lementation o f a risk monitor based on SSH architecture ………………………………WANG Fang,WANG Jin,WANG Jia-qun,et al.

A variable ordering heuristic for risk monitorsbased on zero-suppressed binary decision diagram ……………………………………WANG Jin,WANG Fang,WANG Jia-qun,et al.

Hum an factor engineering analysis for computerized hum anm achine interface design issues ………………………………WANG Zhi-fang,GU Peng-fei,ZHANG Jian-bo

Development of data processing system for regional geophysical and geochemicalexp loration of sandstone-hosted uranium deposits based on A rcGIS Engine ……………………………………HAN Shao-yang,KE Dan,HOU H ui-qun,et al.

Measurement and calculation for radon emanation capability of loose fragmented radon-emitting medium ………………LIGuang-yue,DING De-xin,CHEN Xiang,et al.