Code Development and Engineering Validation of PWR Fuel Management Software Bamboo-C
-
摘要: 基于经典的“两步法”压水堆计算流程，采用目前最先进的核反应堆物理计算方法，研发了先进的压水堆燃料管理软件Bamboo-C。Bamboo-C软件主要由3个功能程序（LOCUST、SPARK、LtoS）组成，LOCUST为二维组件非均匀及等效均匀化计算程序，SPARK为三维堆芯稳态/瞬态分析程序，LOCUST和SPARK程序之间通过组件均匀化参数函数化程序LtoS链接。Bamboo-C软件具备完善的压水堆燃料管理与核设计必备的分析功能，主要包括：启动物理试验、动力学参数计算、控制棒微积分价值、功率运行跟踪等。最后，基于我国自主研发的CNP300、CNP650和CNP1000堆型的运行数据，完成了Bamboo-C软件的工业确认工作。结果表明，采用Bamboo-C软件获得的临界硼浓度、温度系数、控制棒价值以及功率分布等堆芯关键参数的计算值与实测值之间的误差均满足工业限值的要求。
-
关键词:
- 压水堆燃料管理 /
- Bamboo-C软件 /
- 工业确认
Abstract: Based on the conventional “two-step” scheme for the PWR fuel management, an advanced PWR fuel management software Bamboo-C has been developed by the most advanced methodologies in the reactor-physics field. Bamboo-C consists of three main functional codes: LOCUST code for the heterogeneous modeling and simulation and homogenization calculation of 2D assemblies; SPARK code for 3D core steady-state and transient analysis; and LtoS code for assembly homogenization parameter function, which links LOCUST and SPARK. Bamboo-C has all the necessary analysis functions for the fuel management and nuclear design of PWRs, mainly including the start-up physics tests, calculations of the neutron-kinetics parameters, differential and integral worth of rod cluster control assemblies (RCCAs), and power-operation following simulation. Finally, the engineering validations of Bamboo-C have been completed according to the operation data from the reactors CNP300, CNP650 and CNP1000 designed by China independently. The validation results show that the errors between the values of such key parameters of cores as critical boron concentration, temperature coefficient, RCCA worth, and power distributions, calculated by Bamboo-C, and their measured values satisfy the corresponding engineering criterion limits.-
Key words:
- Fuel management of PWRs /
- Bamboo-C code /
- Engineering validation
-
图 1 Bamboo-C软件的整体结构和计算流程
Figure 1. Overall Structure and Calculation Flowchart of Bamboo-C
图 2 LOCUST程序建立的带格架燃料组件物理模型
Figure 2. Physical Model of Fuel Assembly with Grid Built by LOCUST
图 3 LOCUST程序建立的径向反射层物理模型
1~9—不同位置处径向反射层的精细化物理模型
Figure 3. Physical Model of Radial Reflector Built by LOCUST
图 4 SPARK程序中重金属核素微观燃耗链
Figure 4. Microscopic Depletion Chain of Heavy-metal Nuclides in SPARK
图 5 CNP300启动物理试验误差统计
Figure 5. Statistics of Errors in Start-up Physics Test for CNP300
图 6 CNP300功率运行阶段硼浓度误差及其统计结果
10/295、284/295、1/295—对应区域的误差数量占总误差数量的份额；其余类同
Figure 6. Errors in Boron Concentration during Power Operation of CNP300 and Corresponding Statistical Result
图 7 CNP300功率运行阶段组件功率分布误差统计结果
Figure 7. Statistical Result of Errors in Assembly Power Distribution during Power Operation of CNP300
图 8 CNP650启动物理试验误差统计
Figure 8. Statistics of Errors in Start-up Physics Test for CNP650
图 9 CNP650功率运行阶段硼浓度误差及其统计结果
Figure 9. Errors in Boron Concentration during Power Operation of CNP650 and Corresponding Statistical Result
图 10 CNP650功率运行阶段组件功率分布误差统计结果
Figure 10. Statistical Result of Errors in Assembly Power Distribution during Power Operation of CNP650
图 11 CNP1000启动物理试验误差统计
Figure 11. Statistics of Errors in Start-up Physics Test for CNP1000
图 12 CNP1000功率运行阶段硼浓度误差及其统计结果
Figure 12. Errors in Boron Concentration during Power Operation of CNP1000 and Corresponding Statistical Result
-
[1] GIRIEUD P, DAUDIN L, GARAT C, et al. SCIENCE Version 2: The most recent capabilities of framatome 3d nuclear code package[R]. Frence: Framatome, 2001. [2] OUISLOUMEN M, HURIN H, MAYHUE L, et al. Quantification of the two-dimensional transport code paragon[R]. USA: Westinghouse Electric Company, 2004. [3] LIU Y. ANC: A Westinghouse advanced nodal computer code[R]. USA: Westinghouse Electric Company, 2012. [4] ZU T, XU J, TANG Y, et al. NECP-Atlas: A new nuclear data processing code[J]. Annals of Nuclear Energy, 2019(123): 153-161. [5] LI Y, ZHANG B, HE Q, et al. Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice[J]. Nuclear Engineering and Design, 2018(335): 432-440. [6] YANG W, WU H, LI Y, et al. Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core[J]. Nuclear Engineering and Design, 2018(337): 279-290. [7] CHEN J, LIU Z, ZHAO C, et al. A new high-fidelity neutronics code NECP-X[J]. Annals of Nuclear Energy, 2018(116): 417-428. [8] ZHENG Y, DU X, XU Z, et al. SARAX: A new code for fast reactor analysis part I: Methods[J]. Nuclear Engineering and Design, 2018(340): 421-430. [9] ZHENG Y, QIAO L, ZHAI Z, et al. SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification[J]. Nuclear Engineering and Design, 2018(331): 41-53. [10] LIU Z, HE Q, ZU T, et al. The pseudo-resonant-nuclide subgroup method based on global-local self-shielding calculation scheme[J]. Nuclear Science and Technology, 2017, 55(2): 217-228. [11] PUSA M. Computing the matrix exponential in burnup calculations[J]. Nuclear Science and Engineering, 2010(164): 140-150. [12] SMITH K. Assembly homogenization techniques for light water reactor analysis[J]. Progress in Nuclear Energy, 1986(17): 303-335. [13] RHODES J, SMITH K, XU Z. CASMO-5 energy release per fission model[C]. Interlaken Switzerland: PHYSOR, 2008. [14] TRKOV A, HERMAN M, BROWN A. ENDF-6 formats manual: BNL-90365[R]. USA: Brookhaven National Laboratory, 2012. [15] DOWNAR T, XU Y, SEKER V. Theory manual for the PARCS kinetics core simulator modules[D]. USA: University of Michigan, 2009. -
下载:
计量
- 文章访问数: 586
- HTML全文浏览量: 168
- PDF下载量: 75
- 被引次数: 0
