反应堆工程部代表性论文
目
录
I CLAM 钢代表性论文目录
一、核心论文
[1]
Status and Strategy of Fusion Materials Development in China. Q. Huang, Y. Wu, J. Li,
et al. Journal of Nuclear Materials, 386-388 (2009) 400-404.
[2]
Progress in development of CLAM steel and fabrication of small TBM in China. Q.
Huang, C. Li, Q. Wu, et al. Journal of Nuclear Materials, 417 (2011) 85-88.
[3]
Latest progress on R&D of ITER DFLL-TBM in China. Q. Huang, Q. Wu, S. Liu, et al.
Fusion Engineering and Design, 86 (2011) 2611-2615.
[4]
Progress in development of fabrication of small TBMs for EAST and ITER. Q. Huang,
Q. Wu, C. Li, et al. Fusion Engineering and Design, 85 (2010) 2192-2195.
[5]
Progress in Development of China Low Activation Martensitic Steel for Fusion
Application. Q. Huang, C. Li, Y. Li, et al. Journal of Nuclear Materials, 367-370 (2007)
142-146.
[6]
Welding Techniques Development of CLAM Steel for Test Blanket Module. C. Li, Q.
Huang, Q. Wu, et al. Fusion Engineering and Design, 84 (2009) 1184-1187.
[7]
Mechanical Properties and Microstructures of China Low Activation Martensitic Steel
Compared with JLF-1. Y. Li, Q. Huang, Y. Wu, et al. Journal of Nuclear Materials,
367-370 (2007) 117-121.
[8]
Preliminary analysis of irradiation effects on CLAM after low dose neutron irradiation.
L. Peng, Q. Huang, C. Li, S. Liu. Journal of Nuclear Materials, 386-388 (2009) 312-314.
二．代表性论文
[1]
Microstructure and its influence on mechanical properties of CLAM steel. S. Liu, Q.
Huang, L. Peng, Y. Li, C. Li. Fusion Engineering and Design, 87 (2012) 1628-1632.
[2]
Swelling of CLAM steel irradiated by electron/helium to 17.5 dpa with 10 appm He/dpa.
L. Peng, Q. Huang, Y. Wu, et al. Fusion Engineering and Design, 86 (2011) 2624-2626.
[3]
Influence of different cooling rates on the microstructure of the HAZ and welding CCT
diagram of CLAM steel. S. Zheng, Q. Huang, Q. Wu, et al. Fusion Engineering and
Design, 86 (2011) 2616-2619.
反应堆工程部代表性论文
[4]
Effects of tube rolling and heat treatment on microstructure and mechanical properties
of CLAM rectangular tube. B. Huang, Q. Huang, C. Li, et al. Fusion Engineering and
Design, 86 (2011) 2602-2606.
[5]
Effect of Surface Preparation on CLAM/CLAM Hot Isostatic Pressing diffusion
bonding joints. C. Li, Q. Huang, P. Zhang. Journal of Nuclear Materials, 386-388 (2009)
550-552.
[6]
Vacuum plasma sprayed FeAl/Al2O3 functionally graded coatings for fusion reactor
applications. Z Yan, Q Huang, Z Guo, et al. Fusion Engineering and Design, 85 (2010)
1542-1545.
[7]
Influence of Non-metal Inclusions on Mechanical Properties of CLAM Steel. S. Liu, Q.
Huang, C. Li, B. Huang. Fusion Engineering and Design, 84 (2009) 1214-1218.
[8]
Design Status and Development Strategy of China Liquid Lithium-Lead Blankets and
Related Material Technology. Y. Wu, the FDS Team. Journal of Nuclear Materials,
367-370 (2007) 1410-1415.
[9]
Effects of Addition of Yttrium on Properties and Microstructure for China Low
Activation Martensitic Steel (CLAM). Y. Li, Q. Huang, Y. Wu, et al. Fusion Engineering
and Design, 82 (2007) 2683-2688.
[10] Preliminary Experimental Study on Hot Isostatic Pressing Diffusion Bonding for
CLAM- CLAM. C. Li, Q. Huang, P. Zhang, FDS Team. Fusion Engineering and Design,
82 (2007) 2627-2633.
[11] Interaction of CLAM Steel with Plasma in HT-7 Tokamak during High Parameter
Operation. C. Li, Q. Huang, Y. Feng, et al. Plasma Science and Technology, 9 (2007)
484-487.
[12] Study of Irradiation Effects in China Low Activation Martensitic Steel CLAM. Q.
Huang, J. Li, Y. Chen. Journal of Nuclear Materials, 329-333 (2004) 268-272.
[13] Progress in Compatibility Experiments on Lithium-Lead with Candidate Structural
Materials for Fusion in China. Q. Huang, S. Gao, Z. Zhu, et al. Fusion Engineering and
Design, 84 (2009) 242-246.
[14] Corrosion behavior of CLAM steel in static and flowing LiPb at 480°C and 550°C. S.
Gao, Q. Huang, Z. Zhu, et al. Fusion Engineering and Design, 86 (2011) 2627-2631.
[15] Corrosion analysis of CLAM steel in flowing liquid LiPb at 480°C. Y Chen, Q. Huang, S.
Gao, et al. Fusion Engineering and Design, 85 (2010) 1909-1912.
[16] Compatibility of atmospheric plasma sprayed Al2O3 coatings on CLAM with liquid
LiPb. Z. Guo, Q. Huang, Z. Yan, et al. Fusion Engineering and Design, 85 (2010)
1469-1473.
[17] Corrosion Experiment in the First Liquid Metal LiPb Loop of China. Q. Huang, M.
Zhang, Z. Zhu, et al. Fusion Engineering and Design, 82 (2007) 2655-2659.
反应堆工程部代表性论文
II 精确放射治疗代表性论文目录
一．核心论文
[1] Development of Accurate/Advanced Radiotherapy Treatment Planning and Quality
Assurance System (ARTS), Y. Wu, G. Song, R. Cao, et al. Chinese Physics C (HEP &
NP), 2008, 32(Suppl. II): 177-182.
[2] Realization and Comparison of Several Regression Algorithms for Electron Energy
Spectrum Reconstruction. G. Li, H. Lin, A. Wu, et al. Chinese Physics Letter, 2008, 25(7):
2710-2713.
[3] Photon Energy Spectrum Reconstruction Based on Monte Carlo and Measured
Percentage Depth Dose in Accurate Radiotherapy, Gui LI, Huaqing ZHENG, Guangyao
Sun and Yican WU, Progress in NUCLEAR SCIENCE and TECHNOLOGY,
2011,2:160-164.
[4] Multi-objective Optimization of Inverse Planning for Accurate Radiotherapy. CAO
Ruifen, WU Yican, PEI Xi, JING Jia, LI Guoli, CHENG Mengyun, LI Gui, HU Liqin.
Chinese Physics C. 2011, 35(3):313-317.
[5] Construction of a Voxel Model from CT Images with Density Derived from CT
Numbers, Mengyun CHEN, Qin ZENG, Ruifen CAO, Gui LI, Huaqing ZHENG,
Shanqing HUANG, Gang SONG, and Yican WU, Progress in NUCLEAR SCIENCE and
TECHNOLOGY, 2011,2:237-241
[6] Patient Set-up in Radiotherapy with Video-based Positioning System. S. Tao, A. Wu, Y.
Wu. Clincal Oncology, 2006, 18 (4): 363-366.
[7] Repeated Positioning in Accurate Radiotherapy Based on Virtual Net Technique and
Contrary Reconstruction Scheme. S. Tao, Y. Wu, Y. Chen, et al. Computerized Medical
Imaging and Graphics, 2006, 30 (5): 273-278.
[8] ‘A Finite Size Pencil Beam for IMRT Dose Optimization’- a Simpler Analytical Function
for the Finite Size Pencil Beam Kernel. H. Lin, Y. Wu, Y. Chen. Physics in Medicine and
Biology, 2006, 51: 13-15.
二、代表性论文
[1] 精确放射治疗计划系统 ARTS 的研究与发展. 吴宜灿，李国丽，陶声祥，等. 中国医学
物理学杂志，2005, 22(6): 683-690.
[2] CT 图像的体元大小对 EGSnrc 蒙特卡罗剂量计算的影响. 吴爱东，吴宜灿. 核技术，
反应堆工程部代表性论文
2007, 30(2): 143-146.
[3] Monte Carlo 模拟对放疗中电子反散射谱的研究. 林辉，宋钢，吴宜灿. 核技术，2007,
30(1): 17-20.
[4] 蒙特卡罗方法在放疗计划中的应用. 陈朝斌，黄群英，吴宜灿. 核技术，2006, 29(1):
22-28.
[5] 基于 MCNP 的医学仿真计算建模方法研究. 陈卓，刘晓平，施灿辉，等. 系统仿真学报，
2004, 16(10): 2153-2156.
[6] BNCT 中载能粒子对肿瘤细胞损伤效应的 Monte Carlo 模拟及分析. 江海燕，吴宜灿，
ARTS 课题组. 核技术，2004, 27(9): 687-692.
[7]Beam orientation optimization using ant colony optimization in intensity modulated
radiation therapy. Pei Xi, Cao Ruifen, Liu Hui, Proceedings of World Academy of Science,
Engineering and Technology, v 80, p 661-664, August 2011.
[8]A Multi-objective Hybrid Genetic Based Optimization for External Beam Radiation. G. Li,
Y. Wu, J. Zhang. Plasma Science and Technology, 2006, 8 (2): 234-236.
[9]基于放射治疗计划系统的二重癌风险预测分析. 金雏凤，刘慧，郑华庆，等. 核技术，
2011,34(10): 757-761.
[10]基于共轭梯度法的调强放疗射束强度分布优化. 曹瑞芬，裴曦，郑华庆，等. 原子核物
理评论， 2010, 27(2): 212-217.
[11]Patient Positioning Error Measurement Based on Dynamic Template Matching
Techniques. S. Tao, J. Zhang. Presented at the 27th Annual International Conference of the
IEEE Engineering in Medicine and Biology Society, 2005, Shanghai, China.
[12]基于双目视觉测量的放疗位置验证方法研究. 陶声祥，吴宜灿. 核技术，2007, 30 (3):
219-221.
[13]基于视频的精确放疗摆位系统研究. 陶声祥，吴宜灿. 原子核物理评论，2006, 23 (2):
250-253.
[14]Automatic 2D/2D Registration using Multiresolution Pyramid based Mutual
Information in Image Guided Radiation Therapy. Jing JIA, Shanqing HUANG, Fang LIU,
Qiang REN, Gui LI, Mengyun CHENG, Chufeng JIN and Yican WU, Proceedings of World
Academy of Science, Engineering and Technology, v 80, p 964-968, August 2011.
反应堆工程部代表性论文
III 中子学代表性论文目录
一、核心论文
[1]
A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Numerical
Calculation in Curvilinear Geometries. Yican Wu, Zhongsheng Xie, Ulrich Fischer.
Nuclear Science and Engineering, 1999, 133: 350-357.
[2]
Update of ITER 3D Basic Neutronics Model with MCAM. Q. Zeng, L. Lu, A. Ding, Y. Li,
H. Hu, S. Zheng, Q. Huang, Y. Chen, Y. Wu, H. Iida. Fusion Engineering and Design,
2006, 81(23-24): 2773-2778.
[3]
Conceptual Design Activities of FDS Series Fusion Power Plants in China. Y. Wu, FDS
Team. Fusion Engineering and Design, 2006, 81(23-24): 2713-2718.
[4]
The Fusion-Driven Hybrid System and Its Material Selection. Y.C. Wu, J.P. Qian, J.
N.Yu. Journal of Nuclear Materials, 2002, 307-311:1629-1636. Also invited presentation
at the 10th International Conference on Fusion Reactor Materials (ICFRM-10), Oct. 14,
2001, Baden-Baden, Germany.
[5]
Conceptual Design and Testing Strategy of a Dual Functional Lithium-Lead Test
Blanket Module in ITER and EAST. Y. Wu and the FDS Team. Nuclear Fusion, 2007,
47(11): 1533-1539.
[6]
A High Temperature Blanket Concept for Hydrogen Production. H. Chen, Y. Wu, S.
Konishi, J. Hayward. Fusion Engineering and Design, 2008, 83(7-9).
[7]
Design Status and Development Strategy of China Liquid Lithium-lead Blankets and
Related Material Technology. Y. Wu, the FDS Team. Journal of Nuclear Materials, 2007,
367-370: 1410-1415.
二、代表性论文
[1]
Benchmarking of MCAM 4.0 with the ITER 3D model. Y. Li, L. Lu, A. Ding, H. Hu, Q.
Zeng, S. Zheng, Y. Wu. Fusion Engineering and Design, 2007, 82: 2861-2866.
[2]
Development and application of SN Auto-Modeling Tool SNAM 2.1. Pengcheng Long,
Jun Zou, Shanqing Huang, Yuefeng Qiu. Fusion Engineering and Design, 2010, 85(7-9):
1113-1116.
[3]
Development and testing of multigroup library with correction of self-shielding effects
in fusion–fission hybrid reactor. Jun Zou, Zhaozhong He, Qin Zeng, Yuefeng Qiu,
Minghuang Wang. Fusion Engineering and Design, 2010,85 :1587–1590.
反应堆工程部代表性论文
[4]
Neutronics Analysis for a Compact Reversed Shear Tokamak CREST. Q. Huang, S.
Zheng, L. Lu, R. Hiwatari, Y. Asaoka, K. Okano, Y. Ogawa. Fuison Eegineering and
Design, 2006, 81: 1239-1244.
[5]
Neutronics Analysis of Dual-cooled Waste Transmutation Blanket for the FDS. Y.C. Wu,
X.X. Zhu, S.L. Zheng, Y. Ke, Q.Y. Huang, X.P. Liu, S. Wu, D. Xu, H.Liu. Fusion
Engineering and Design, 2002, 63-64: 133-138.
[6]
Neutronics Analysis for the Test Blanket Modules Proposed for EAST and ITER. S.
Zheng, M. Chen, J. Li, Q. Zeng, L. Lu, Y. Li, A. Ding,and H. Hu. Nuclear Fusion, 2007,
47(8): 1053-1056.
[7]
蒙特卡罗粒子输运计算自动建模程序系统的研究与发展. 吴宜灿，李莹，卢磊，丁爱平，
胡海敏，曾勤，罗月童，郑善良，黄群英，陈义学. 核科学与工程, 2006, 26(1): 20-27.
[8]
大型集成多功能中子学计算与分析系统 VisualBUS 的研究与发展. 吴宜灿，李静惊，陈
明亮，郑善良，许德政，蒋洁琼，李莹，卢磊，丁爱平，胡海敏，龙鹏程，罗月童, 曹
瑞芬，邹俊，何兆忠，曾勤，FDS 团队. 核科学与工程, 2007, 27(4): 365-373.
[9]
Progress in Fusion-driven Hybrid System Studies in China. Yican Wu. Fusion
Engineering and Design, 2002, 63-64: 73-80.
[10] Conceptual Design of the Fusion-driven Subcritical System FDS-I. Y. Wu, S. Zheng, X.
Zhu, W. Wang, H. Wang, S. Liu, Y. Bai, H. Chen, L. Hu, M. Chen, Q. Huang, D. Huang,
S. Zhang, J. Li, D. Chu, J. Jiang, Y. Song, FDS Team. Fusion Engineering and Design,
2006, 81, PartB: 1305-1311.
[11] Conceptual Design of the China Fusion Power Plant FDS-II. Y. Wu, FDS Team. Fusion
Engineering and Design, 2008, 83(10-12): 1683–1689.
[12] Fusion-Based Hydrogen Production Reactor and Its Material Selection, Y. Wu, FDS
Team,Journal of Nuclear Materials, 2009, 386-388:122-126.
[13] Overview of liquid lithium lead breeder blanket program in China. Yican Wu, FDS
Team. Fusion Engineering and Design, 2011, 86(9-11): 2343–2346.
[14] Design Analysis of the China Dual-functional Lithium Lead (DFLL) Test Blanket
Module in ITER. Y. Wu, the FDS Team. Fusion Engineering and Design, 2007, 82:
1893-1903.
[15] 聚变发电反应堆概念设计研究. 吴宜灿，汪卫华，刘松林，李静惊，王红艳，陈红丽，
陈明亮，张士杰，黄群英，黄德所，郑善良，曾勤，胡丽琴，柏云清，章毛连，李艳芬，
李春京，冯岩，宋勇，龙鹏程，FDS 课题组. 核科学与工程，2005, 25(1): 76-85.
[16] 聚变高温制氢反应堆概念设计研究. 吴宜灿，刘松林，陈红丽，黄群英，宋勇，柏云清，
曾勤，张世杰，陈一平，FDS 团队. 核科学与工程，2008, 28(1): 1-9.
反应堆工程部代表性论文
[17] ITER 中国液态锂铅实验包层模块设计研究与实验策略. 吴宜灿，汪卫华，刘松林，黄
群英，郑善良，王红艳，陈红丽，陈明亮，柏云清，宋勇，章毛连，柯严，李春京，李
艳芬，胡丽琴，刘萍，李静惊，李莹，许德政，曾勤，陈义学. 核科学与工程，2005, 25(4):
347-360.
IV 系统安全代表性论文目录
一、核心代表性论文
[1] 福岛核电站事故的影响与思考. 吴宜灿. 中国科学院院刊, 2011, 26(3):271-277.
[2] 秦山三期重水堆核电站风险监测器研发进展. 吴宜灿, 胡丽琴, 李亚洲, 等. 核科学与
工程, 2011, 31(1): 70-77.
[3] 先进核能系统设计分析软件与数据库研发进展. 吴宜灿, 胡丽琴, 龙鹏程, 等. 核科学
与工程, 2010, 30(1): 55-64.
[4] 大型集成概率安全分析软件系统的研究与发展. 吴宜灿, 刘萍, 胡丽琴, 等. 核科学与
工程, 2007, 27(3): 270-276.
[5]Conceptual Design Activities of FDS Series Fusion Power Plants in China. Y. Wu, FDS
Team. Fusion Engineering and Design, 2006, 81: 2713-2718.
[6]Selection of Bounding Events for ITER DFLL-TBM Safety Analysis. L. Hu, H. Chen, Y.
Bai, et al. Fusion Engineering and Design, 2010, 85: 1577-1580.
[7]Probabilistic Safety Assessment of the Dual-cooled Waste Transmutation Blanket for the
FDS-I. L. Hu, Y. Wu. Fusion Engineering and Design, 2006, 81: 1403-1407.
二、代表性论文
[1]
核电站风险监测系统数据库的设计和实现. 王芳, 王家群, 汪进, 等. 核科学与工程,
2011, 31(3): 252-257.
[2]
风险监测系统中实时风险模型研发及其应用初步研究. 顾晓慧, 王家群, 王芳, 等. 核
科学与工程, 2011, 31(2): 180-192.
[3]
多核并行计算技术在风险监测系统中的应用. 殷园, 汪进, 王芳, 等. 核科学与工程,
2011, 31(2): 175-179.
[4]
RiskA 计算引擎在核电站概率安全评价中的应用. 王家群, 王芳, 汪进, 等. 核科学与
工程, 2011, 31(1): 78-82.
反应堆工程部代表性论文
[5]
概率安全评价软件 RiskA 中的非逻辑处理方法. 李亚洲, 胡丽琴, 袁润, 等. 原子能科
学技术, 2010, 44(8): 969-973.
[6]
基于 SSH 架构的风险监测系统的设计与实现. 王芳, 汪进, 王家群, 等. 核科学与工程,
2010, 30(4): 355-359.
[7]
适于风险监测系统的零压缩二元决策图基本事件排序方法. 汪进, 王芳, 王家群, 等.
核科学与工程, 2010, 30(4): 360-364.
[8]
A Variable Ordering Heuristic based on Zero-suppressed Binary Decision Diagrams. Y.
LI, J. Wang, L. Hu, et al. Proceedings of the 18th International Conference on Nuclear
Engineering, 2010, Xi’an, Shanxi, China.
[9] ITER 双功能液态锂铅实验包层系统故障模式影响分析. 胡丽琴, 吴宜灿, 陈红丽, 等.
核科学与工程, 2008, 28(2): 167-171 .
[10] PSA 中不确定性分析实现方法研究. 李亚洲, 吴宜灿, 刘萍, 等. 核科学与工程, 2006,
26(4): 353-357.
[11] 聚变发电反应堆双冷液态锂铅包层的初步概率安全分析. 胡丽琴, 吴宜灿. 核科学与工
程, 2005, 25(2): 70-73.
[12] Preliminary Analysis of Typical Transients in Fusion Driven Subcritical System (FDS-I).
Y. Bai, Y. Ke, Y. Wu. The 15th International Conference on Nuclear Engineering
(ICONE-15), April 22-26, 2007, Nagoya, Japan.
[13] Preliminary Transient Thermal Analysis for Safety of the Dual-cooled Waste
Transmutation Blanket for the FDS-I. Y. Bai, H. Chen, Y. Ke, et al. Fusion Engineering
and Design, 81 (2006) 1397-1401.
[14] Preliminary Tritium Safety Analysis on China DFLL-TBM for ITER, Y. Song, Q.
Huang, M. Ni, et al. Fusion Engineering and Design, 84 (2009) 2114-2117.
[15] Neutronics Safety Analysis in Severe Transients of the Dual-Cooled Waste
Transmutation Blanket for the FDS-I. S. Zheng, Y. Wu. Fusion Engineering and Design,
81 (2006) 1425-1429.
[16] Failure Modes and Effects Analysis on ITER DFLL-TBM System. L. Hu, Y. Wu, H.
Chen, et al. Presented at the Fifth International Conference on Quality and Reliability
（ICQR 2007）
，Chiang Mai, Thailand，November 5-7, 2007.
V 液态金属回路代表性论文目录
一、核心论文
[1] 中国系列液态锂铅实验回路设计与研发进展. 吴宜灿，黄群英，朱志强，高胜，宋勇，
反应堆工程部代表性论文
李春京等. 核科学与工程，2009, 29（2）: 161-169.
[2] 液态铅铋回路设计研制与材料腐蚀实验初步研究. 吴宜灿，黄群英，柏云清，高胜，朱
志强，陈雅萍，凌新圳，刘静，祝玲琳. 核科学与工程，2010，30（3）
：238-243.
[3] Progress in compatibility experiments on lithium–lead with candidate structural
materials for fusion in China. Qunying Huang, Sheng Gao, Zhiqiang Zhu, Maolian
Zhang, Yong Song. Fusion Engineering and Design 84 (2009) 242–246.
[4] Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of
Fusion Reactor. Qunying Huang, Sheng Gao, Zhiqiang Zhu, Zhihui Guo, Xinzhen Ling,
Zilin Yan. Advances in Science and Technology 73 (2010) 41-50.
[5] Corrosion experiment in the first liquid metal LiPb loop of China. Qunying Huang,
Maolian Zhang, Zhiqiang Zhu, Sheng Gao,Yican Wu. Fusion Engineering and Design
82 (2007) 2655–2659.
[6]
Design of auxiliary system for the dual functional lithium–lead test blanket module in
ITER. M. Zhang, Y. Wu, Q. Huang, X. He, C. Li, FDS team. Fusion Eng. Des., 81 (2006)
671–675.
二、代表性论文
[1]
Corrosion behavior of CLAM steel in static and flowing LiPb at 480℃ and 550℃.
Sheng Gao, Qunying Huang, Zhiqiang Zhu, Zhihui Guo, Xinzhen Ling, Yaping Chen.
Fusion Engineering and Design 86 (2011) 2627–2631.
[2] Design analysis of DRAGON-IV LiPb loop. Zhiqiang Zhu, Qunying Huang, Sheng Gao,
Yong Song, Chunjing Li, Lei Peng, Hongli Chen. Fusion Engineering and Design 86
(2011) 2666–2669.
[3] Corrosion analysis of CLAM steel in flowing liquid LiPb at 480℃. Yaping Chen,
Qunying Huang, Sheng Gao, Zhiqiang Zhu, Xinzhen Ling. Fusion Engineering and
Design 85 (2010) 1909–1912.
[4] Compatibility of atmospheric plasma sprayed Al2O3 coatings on CLAM with liquid
LiPb. Zhihui Guo, Qunying Huang, Zilin Yan, Yong Song, Zhiqiang Zhu, Sheng Gao.
Fusion Engineering and Design 85 (2010) 1469–1473.
[5] Vacuum plasma sprayed FeAl/Al2O3 functionally graded coatings for fusion reactor
applications. Zilin Yan, Qunying Huang, Zhihui Guo, Yong Song, Chunjing Li, Shaojun
Liu. Fusion Engineering and Design 85 (2010) 1542–1545.
[6] Preliminary experiments on the corrosion of CLAM steel in flowing eutectic LiPb. Z.
Zhu, M. Zhang, S.Gao, Y. Song, C.Li, L. Peng, Z. Guo, Y. Wang, S. Liu, M. Kong, Q.
Huang, FDS Team. Fusion Engineering and Design 84 (2009) 5–8.
反应堆工程部代表性论文
[7] 中国液态锂铅热对流实验回路 DRAGON- Ñ 温度场和速度场数值模拟分析. 朱志强，汪
卫华，章毛连，高胜，金鸣，宋勇，黄群英，吴宜灿，FDS 团队. 核科学与工程，2008,
28 (2): 80-84.
[8] 中国低活化马氏体钢 CLAM 在液态锂铅中的腐蚀初步实验研究. 高胜，章毛连，朱志
强，黄群英，李春京等. 核科学与工程，2007, 27（1）
：51-54.
[9] Compatibility of SiC with static liquid LiPb at 800℃. Xinzhen Ling, Qunying Huang,
Sheng Gao, Zhiqiang Zhu, Yaping Chen. Fusion Engineering and Design 86 (2011)
2655–2657.
[10] Preliminary experiment on compatibility of SiCf/SiC composites in static liquid LiPb at
700℃. Z.Q. Zhu, Q.Y. Huang, S. Gao, X.G. Zhou, X.Z. Ling, Y.P. Chen, M.L. Zhang. Fusion
Engineering and Design 84 (2009) 2048–2051.
VI CLEAR 设计代表性论文目录
代表性论文
[1]
Overview of China Lead Alloy cooled Reactor Development and ADS Program in China,
Y.Wu, Y.Bai, W.Wang, et.al, NUTHOS-9,Kaohsiung,Taiwan,September 9-13,2012.
[2]
Natural Circulation Characteristics of China Lead Alloy Cooled Research Reactor
CLEAR-I,MingJIN,ZhaoCHEN,HongliCHEN,etc.NUTHOS-9,Kaohsiung,Taiwan,Septe
mber 9-13,2012.
[3]
Preliminary Thermal-hydraulic Design and Analysis of China Lead Alloy Cooled Resear
ch Reactor (CLEAR-I),
Hongli CHEN, Zhao CHEN, Tao ZHOU, Ming JIN, Yunqing BAI, Weihua WANG.
NUTHOS-9，Kaohsiung, Taiwan, September 9-13, 2012.