期刊首页 优先出版 当期阅读 过刊浏览 作者中心 关于期刊 English

《工程(英文)》 >> 2017年 第3卷 第4期 doi: 10.1016/J.ENG.2017.04.016

用于先进核反应堆综合设计的计算工具

TerraPower, LLC, Bellevue, WA 98005, USA

录用日期: 2017-06-23 发布日期: 2017-08-30

下一篇 上一篇

摘要

先进核反应堆可为全世界提供安全、清洁、可靠的电能。从概念设计前期,到详细设计工作、执照申请和电站运行等不同阶段,开发先进核反应堆对计算模型的依赖程度都非常高。一个综合性反应堆建模框架不仅可以实现无缝通信、连接、自动化和连续开发等功能,更可以极大地提高反应堆设计工作的能力和效率。在这种系统中,各种关键性能指标(如最优燃料管理、设计基础事故状态下包壳的峰值温度、平准化发电成本等)可以明确地与设计输入数据(如集成模块管道的厚度、容差等数据)联系在一起,保证极高的设计一致性。此系统结合高性能计算系统之后,能够同时执行数千个集成的案例对整个系统进行敏感性分析,从而高效、可靠地评估各种设计,确定最优方案。TerraPower 公司开发了一款类似的工具,他们将其命名为“高级反应堆建模接口系统”(ARMI),并已将其应用于目前正在开发的TerraPower 行波反应堆设计及其他创新性能源产品的设计工作中。ARMI 系统使用之前已有的、具有强大谱系的各种工具,以及创新性设计所需的多种新的物理和数据管理模块。此系统将之前已有的和各种新的物理测量值(这些数据对任何优秀的设计而言都是非常重要的基础数据)进行了对比确认和验证。本文综述了集成反应堆堆芯工程设计工具的情况和TerraPower 公司的生产实践情况。

图片

图1

图2

图3

图4

图5

图6

图7

参考文献

[ 1 ] Haigh T, Priestley M, Rope C. ENIAC in action: Making and remaking the modern computer. Cambridge: MIT Press; 2016.

[ 2 ] Greenspan H, Kelber CN, Okrent D, editors. Computing methods in reactor physics. New York: Gordon and Breach Science Publishers; 1968.

[ 3 ] Gilleland J, Petroski R, Weaver K. The traveling wave reactor: Design and development. Engineering 2016;2(1):88–96 链接1

[ 4 ] Gamma E, Helm R, Johnson R, Vlissides H. Design patterns: Elements of reusable object-oriented software. Boston: Addison-Wesley Longman Publishing Co., Inc; 1995.

[ 5 ] Lee C, Yang WS. MC2-3: Multigroup cross section generation code for fast reactor analysis. Nuclear Sci Eng. Epub 2017 Jun 30 链接1

[ 6 ] Derstine KL. DIF3D: A code to solve one-, two-, and three-dimensional finite-difference diffusion theory problems. Report.Illinois: Argonne National Laboratory; 1984 Apr. Report No.: ANL-82-64.

[ 7 ] Olson A. A users guide for the REBUS-PC code, version 1.4. Illinois: Argonne National Laboratory ; 2001 Dec. Report No.: ANL/RERTR/TM-32. Contract No.: W-31-109-ENG-38.

[ 8 ] Hosteny RP. ARC system fuel cycle analysis capability, REBUS-2, Report. Illinois: Argonne National Laboratory; 1978 Jan. Report No.: ANL-772-1.

[ 9 ] Chadwick MB, Herman M, Oblo?insky P, Dunn ME, Danon Y, Kahler AC, et al.ENDF/B-VII. 1. Nuclear data for science and technology: Cross sections, covariances, fission product yields and decay data. Nucl Data Sheets 2011;112(12):2887–996 链接1

[10] Salvatores M, Palmiotti G, Aliberti G, Archier P, De Saint Jean C, Dupont E, et al.Methods and issues for the combined use of integral experiments and covariance data: Results of a NEA international collaborative study. Nucl Data Sheets 2014;118:38–71 链接1

[11] Pelowitz DB. MCNPX user’s manual version 2.5.0. Los Alamos: Los Alamos National Laboratory; 2005 Apr. Report No.: LA-CP-05-0369.

[12] Ellis T, Petroski R, Hejzlar P, Zimmerman G, McAlees D, Whitmer C, et al.Traveling-wave reactors: A truly sustainable and full-scale resource for global energy needs. In: Proceedings of ICAPP’10 ; 2010 Jun 13–17; San Diego, USA. Illinois: American Nuclear Society; 2010. p. 10189.

[13] Miller SJ, Latta R. Fuel performance modeling of traveling wave reactor fuel elements [poster session]. In: Materials Modeling and Simulation for Nuclear Fuels 2013 Workshop; 2013 Oct 14–16; Chicago, IL, USA. 2013.

[14] Cohen M, Werner M, Johns C. Mechanical model of a TerraPower, traveling wave reactor fuel assembly duct. In: 22nd International Conference on Structural Mechanics in Reactor Technology; 2013 Aug 18–23; San Francisco, CA, USA. Red Hook: Curran Associates, Inc.; 2014.

[15] Dunn FE, Prohammer FG. The SASSYS LMFBR systems analysis code. Math Comput Simul 1984;26(1):23–6 链接1

[16] Breiman L, Friedman JH. Estimating optimal transformations for multiple regression and correlation. J Am Stat Assoc 1985;80(391):580–98 链接1

[17] Messac A. Physical programming-effective optimization for computational design. AIAA J 1996;34(1):149–58 链接1

[18] American Society of Mechanical Engineers.Quality assurance requirements for nuclear facility applications. NQA-1-2008. New York: American Society of Mechanical Engineers; 2008.

[19] American Society of Mechanical Engineers.Addenda to ASME NQA-1-2008, Quality assurance requirements for nuclear facility applications. NQA-1a-2009. New York: American Society of Mechanical; 2009.

[20] OECD Nuclear Energy Agency.International handbook of evaluated reactor physics benchmark experiments. Paris: OECD Nuclear Energy Agency; 2009.

[21] Xu Z, Onufer M, Touran N. Reactor physics benchmark suite development for nuclear analysis codes and methods validations in travelling wave reactor applications. In: Proceedings of the Physics of Reactors Conference: Unifying Theory and Experiments in the 21st Century (PHYSOR 2016); 2016 May 1–5; Sun Valley, ID, USA. Illinois: American Nuclear Society; 2016. p. 362–76.

相关研究