​核反应堆核材料的应用评估和相关研究

   

082703-核技术及应用
082701-核能科学与工程

核石墨评估，反应堆组件应力分析

1998-06--2010-12   英国曼彻斯特大学   博士后
1993-01--1996-11   英国曼彻斯特大学   博士学位
1991-09--1992-12   英国曼彻斯特大学   硕士学位
1988-09--1991-07   英国曼彻斯特大学   学士学位

   

2013-03~现在, 中国科学院上海应用物理研究所, ****研究员
2011-01~2013-02,英国曼彻斯特大学, Research Fellow

石墨应力分析

   

[1] 张灿, 曾广礼, 夏汇浩, 贺周同, 蔡茂源. 一种抗拉强度测试方法及装置. CN: CN105043866A, 2015-11-11.

   

[1] Crystals. 2023, 第 3 作者
[2] Theoretical and Applied Fracture Mechanics. 2023, 第 5 作者
[3] Journal of Materials Research. 2022,   通讯作者  
[4] ASTM International. 2022,   通讯作者  
[5] Chen, Shuangjian, He, Tianbing, Zhao, Libin, Tsang, D K L. Microstructure and mechanical response of gas tungsten arc welded joints comprising a UNS N10003 alloy with different heat inputs. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING[J]. 2021, 803: http://dx.doi.org/10.1016/j.msea.2020.140494.
[6] 许俊, 管月霞, 曾广礼. Modified-ASME失效概率模型的验证与优化. 辐射研究与辐射工艺学报[J]. 2021, 第 3 作者39(3): 91-98, https://doi.org/10.11889/j.1000-3436.2021.rrj.39.030701.
[7] 曾广礼. Investigating creep behaviour of Ni-Cr-W alloy pressurized tube at 950C by using in-situ creep testing system. Nuclear Engineering and Technology. Nuclear Engineering and Technology. 2020, 第 1 作者  通讯作者  
[8] 管月霞, 刘新宽, 曾广礼, 高彦涛. 三维针刺C/C控制棒导向管侧向抗压强度评价的数值研究. 核技术[J]. 2020, 第 3 作者43(7): 77-84, http://lib.cqvip.com/Qikan/Article/Detail?id=7102269382.
[9] 曾广礼. Investigating creep behaviour of Ni-Cr-W alloy pressurized tube at 950C by using in-situ creep testing system. Nuclear Engineering and Technology. 2020, 第 1 作者  通讯作者  
[10] Yang, Xiong, Wang, Xue, Tsang, D K L. The effect of thermal oxidation on the coefficient of thermal expansion of nuclear graphite. JOURNAL OF MATERIALS SCIENCE[J]. 2020, 55(18): 7805-7815, https://www.webofscience.com/wos/woscc/full-record/WOS:000521887200001.
[11] 曾广礼. On the biaxial thermal creep-fatigue behaviour of Ni-base Alloy 617 at 950C. International Journal of Fatigue. 2020, 第 1 作者  通讯作者  
[12] 曾广礼. A numerical study of lateral compressive strength of 3D needle-punched C/C control rod guide tubes. Nuclear Techniques. 2020, 第 1 作者  通讯作者  
[13] Experimental Techniques. 2020, 第 7 作者
[14] Tsang, D K L. Material model for stress analysis of nuclear graphite component subject to irradiation. SCIENTIASINICAPHYSICAMECHANICAASTRONOMICA[J]. 2019, 49(11): 
[15] 曾广礼. Study on improved probability evaluation method of nuclear graphite based on ASME specification. Nuclear Techniques. 2019, 第 1 作者  通讯作者  
[16] 丁冬, 高彦涛, 杨雄, 钟阳, 曾广礼. 基于ASME规范的核石墨改进概率评价方法研究. 核技术[J]. 2019, 第 5 作者42(1): 85-90, http://lib.cqvip.com/Qikan/Article/Detail?id=7001139883.
[17] Cen, Qianying, Tsang, Derek Kwong Lai, Lu, Yanling. Creep damage analysis of thin-walled pressure vessel based on continuum damage model under static loading. INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING[J]. 2019, 177: http://dx.doi.org/10.1016/j.ijpvp.2019.103994.
[18] 曾广礼. 辐照环境下各向同性核石墨材料应力分析模型. 中国科学:物理学、力学、天文学[J]. 2019, 第 1 作者49(11): 107-116, https://www.sciengine.com/doi/10.1360/SSPMA2018-00243.
[19] 曾广礼. Dynamic characteristics identification of double graphite bricks in molten salt reactor considering fluid-structure interaction. Nuclear Engineering and Design. 2018, 第 1 作者  通讯作者  
[20] 曾广礼. Numerical study of dynamic behaviour for a single-layer graphite core in TMSR. Nuclear Science and Techniques. 2018, 第 1 作者  通讯作者  
[21] Yang, Xiong, Gao, YanTao, Zhong, Yang, Ding, Dong, Tsang, DerekKwongLai. Stress analysis of the TMSR graphite component under irradiation conditions. NUCLEAR SCIENCE AND TECHNIQUES[J]. 2018, 29(12): 173, http://lib.cqvip.com/Qikan/Article/Detail?id=676833480.
[22] 曾广礼. Four-point bending experiment and simulation of dog bone nuclear graphite. Nuclear Techniques. 2017, 第 1 作者  通讯作者  
[23] 杨雄, 曾广礼, 顾晨光, 钟阳, 丁冬. V型凹口对液态熔盐堆用核石墨构件应力分析的影响. 核技术[J]. 2017, 第 2 作者40(7): "49-55", http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2017.hjs.40.070601.
[24] 曾广礼. Effect of V shape notch on stress analysis of nuclear graphite component for liquid molten salt reactor. Nuclear Techniques. 2017, 第 1 作者  通讯作者  
[25] Yang, Xiong, Tsang, D K L. Evaluating Young's modulus of porous nuclear graphite by a novel multi-scale method. JOURNAL OF MATERIALS SCIENCE[J]. 2017, 52(18): 10959-10971, https://www.webofscience.com/wos/woscc/full-record/WOS:000405305400028.
[26] 顾晨光, 曾广礼, 杨雄, 钟阳, 丁冬. 犬骨型核石墨四点弯曲实验与模拟. 核技术[J]. 2017, 第 2 作者40(5): "61-66", http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2017.hjs.40.050601.
[27] Treifi, Muhammad, Oyadiji, S Olutunde, Tsang, Derek K L. Computation of the stress intensity factors of sharp notched plates by the fractal-like finite element method. INTERNATIONAL JOURNAL FOR NUMERICAL METHODS IN ENGINEERING[J]. 2009, 77(4): 558-580, https://www.webofscience.com/wos/woscc/full-record/WOS:000262546100006.
[28] Treifi, Muhammad, Oyadiji, S Olutunde, Tsang, Derek K L. Computations of the stress intensity factors of double-edge and centre V-notched plates under tension and anti-plane shear by the fractal-like finite element method. ENGINEERING FRACTURE MECHANICS[J]. 2009, 76(13): 2091-2108, http://dx.doi.org/10.1016/j.engfracmech.2009.05.018.
[29] 曾广礼. Computation of modes I and II stress intensity factors of sharp notched plates under in-plane shear and bending loading by the fractal-like finite element method. International Journal of Solids and Structures. 2008, 第 1 作者
[30] Tsang, D K L, Marsden, B J, Vreeling, J A, van der Laan, J. Analyses of a restrained growth graphite irradiation creep experiment. NUCLEAR ENGINEERING AND DESIGN[J]. 2008, 238(11): 3026-3030, http://dx.doi.org/10.1016/j.nucengdes.2007.12.017.
[31] 曾广礼. Super singular element method for 2D crack analysis. Proceedings of the Royal Society. 2008, 第 1 作者
[32] 曾广礼. Constitutive material model for the prediction of stress in irradiated anisotropic graphite components. Journal of Nuclear Materials. 2008, 第 1 作者
[33] 曾广礼. Effect of dimensional change strain in nuclear graphite component stress analysis. Nuclear Engineering and Design. 2007, 第 1 作者
[34] Tsang, D K L, Oyadiji, S O, Leung, A Y T. Two-dimensional fractal-like finite element method for thermoelastic crack analysis. INTERNATIONAL JOURNAL OF SOLIDS AND STRUCTURES[J]. 2007, 44(24): 7862-7876, http://dx.doi.org/10.1016/j.ijsolstr.2007.05.008.
[35] Tsang, DKL, Marsden, BJ. The development of a stress analysis code for nuclear graphite components in gas-cooled reactors. JOURNAL OF NUCLEAR MATERIALS[J]. 2006, 350(3): 208-220, http://dx.doi.org/10.1016/j.jnucmat.2006.01.015.
[36] Tsang, D K L. A numerical study of a detonation wave in detonation transmission tubing. MATHEMATICAL AND COMPUTER MODELLING[J]. 2006, 44(7-8): 717-734, http://dx.doi.org/10.1016/j.mcm.2006.02.008.
[37] Tsang, DKL, Marsden, BJ, Fok, SL, Hall, G. Graphite thermal expansion relationship for different temperature ranges. CARBON[J]. 2005, 43(14): 2902-2906, http://dx.doi.org/10.1016/j.carbon.2005.06.009.
[38] 曾广礼. Dynamic fractal-like finite element method for a penny-shaped crack subject to mode I dynamic loading. The International Journal of Applied Mathematics and Mechanics. 2005, 第 1 作者
[39] 曾广礼. A simple mathematical model for isotropic nuclear graphite under irradiation condition. The International Journal of Applied Mathematics and Mechanics. 2005, 第 1 作者
[40] 曾广礼. The initiation process inside a detonation delay element. The International Journal of Applied Mathematics and Mechanics. 2005, 第 1 作者
[41] Tsang, DKL, Oyadiji, SO, Leung, AYT. Applications of numerical eigenfunctions in the fractal-like finite element method. INTERNATIONAL JOURNAL FOR NUMERICAL METHODS IN ENGINEERING[J]. 2004, 61(4): 475-495, https://www.webofscience.com/wos/woscc/full-record/WOS:000224001100001.
[42] Tsang, DKL, Oyadiji, SO, Leung, AYT. Multiple penny-shaped cracks interaction in a finite body and their effect on stress intensity factor. ENGINEERING FRACTURE MECHANICS[J]. 2003, 70(15): 2199-2214, http://dx.doi.org/10.1016/S0013-7944(02)00206-0.
[43] 应用力学学报. 2003, 第 4 作者
[44] Leung, AYT, Tsang, KL. Mode III two-dimensional crack problem by two-level finite element method. INTERNATIONAL JOURNAL OF FRACTURE[J]. 2000, 102(3): 245-258, https://www.webofscience.com/wos/woscc/full-record/WOS:000088936500003.
[45] 曾广礼. wo-Level finite element method for a finite body with penny-shaped cracks. INTERNATIONALJOURNALOFFRACTURE. 1999, 第 1 作者

   

（ 1 ） 石墨堆芯结构安全分析, 主持, 市地级, 2013-03--2016-03

（1）Whole core analysis   DKL Tsang   2012-09-23
（2） Crack propagation analysis in nuclear graphite by using Extended Finite Element Method (XFEM)   DKL Tsang   2012-09-23
（3）Proposed a new multi-scale modelling method for nuclear graphite   DKL Tsang   2012-07-10
（4）Manchester AGR core modelling (MANACM) code for 3D dynamic analysis of graphite core   DKL Tsang and BJ Marsden   2011-10-31
（5）The effect of creep strain on nuclear graphite stress analysis   DKL Tsang and BJ Marsden   2011-10-31
（6）Manchester AGR Core Modelling (MANACM) code for 3D dynamic analysis of graphite core   DKL Tsang and BJ Marsden   2011-09-20
（7）Modelling an advanced gas-cooled reactor (AGR) core using ABAQUS   DKL Tsang, BJ Marsden and GB Heys   2011-05-17

已指导学生

顾晨光  硕士研究生  082701-核能科学与工程  

杨雄  博士研究生  082701-核能科学与工程  

丁冬  硕士研究生  085226-核能与核技术工程  

钟阳  博士研究生  082701-核能科学与工程  

岑倩莹  硕士研究生  082701-核能科学与工程  

许俊  硕士研究生  082701-核能科学与工程  

现指导学生

熊东波  硕士研究生  082701-核能科学与工程