Preliminary Research of Pebble Bed High-Temperature Gas-Cooled Reactor with Random Refueling Approach Based on VSOP
-
摘要: 球床式高温气冷堆（简称球床堆）具有连续在线换料的特点，燃料球在球床堆堆芯中缓慢流动，使用物理热工计算程序VSOP采用近似、平均的倒料方式模拟此过程，但在一定程度上抹除了球流运动的随机性。本文基于VSOP程序改进了球床堆堆芯倒料模型，提出随机倒料方法，研究了卸料合并平均效应的影响。结果表明，随机倒料能够提供更精细的卸料燃耗深度分布，卸料平均效应会导致燃耗峰展宽重叠。Abstract: The pebble bed high-temperature gas-cooled reactor (PB-HTGR) is characterized by continuous online refueling. The fuel ball flows slowly in the core of the reactor. The VSOP code, which is widely used in engineering design, employs an approximate and average refueling method to simulate the process, tending to diminish the randomness of the pebble flow of PBR to some extent. In this paper, a new approach of random refueling based on VSOP code is proposed, and it improves the core refueling model and focuses on the impact of the average merging effect of discharging fuel. The results show that the random refueling approach can provide a more refined discharge fuel burnup probability distribution, and the average merging effect of discharging fuel tends to the broadening and overlapping of burnup peaks.
-
图 1 VSOP程序HTR-PM传统倒料示意图
Figure 1. Schematic Diagram of HTR-PM Traditional Refueling in VSOP Code
图 2 HTR-PM 15批次传统倒料与随机倒料卸料燃耗深度分布
Figure 2. Discharge Burnup Probability Distribution of 15 Batches of Traditional Refueling and Random Refueling of HTR-PM
图 3 HTR-PM多批次传统倒料卸料燃耗深度分布
Figure 3. Discharge Burnup Probability Distribution of Multiple Batches of Traditional Refueling of HTR-PM
图 4 HTR-PM多批次随机卸料燃耗深度分布
Figure 4. Discharge Burnup Probability Distribution of Multiple Batches of Random Refueling of HTR-PM
表 1 HTR-PM多批次随机倒料与传统倒料关键参数分析
Table 1. Key Parameter Analysis of Multiple Batches of Random Refueling and Traditional Refueling of HTR-PM
关键参数 15批次15箱
传统倒料15批次75箱
随机倒料30批次150箱
随机倒料45批次225箱
随机倒料60批次300箱
随机倒料75批次375箱
随机倒料90批次450箱
随机倒料有效增殖系数（keff） 1.00480 1.00473 1.00460 1.00471 1.00468 1.00464 1.00467 乏燃料平均燃耗/ [MW·d·t−1(U)] 89804 89706 89085 89082 89085 89083 89083 
下载: 导出CSV
-
[1] ZHANG Z Y, WU Z X, SUN Y L, et al. Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM[J]. Nuclear Engineering and Design, 2006, 236(5-6): 485-490. doi: 10.1016/j.nucengdes.2005.11.024 [2] RÜTTEN H J, HAAS K A, BROCKMANN H, et al. V. S. O. P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009[Z]. Germany: Institut für Energieforschung, 2010. [3] RYCROFT C H, GREST G S, LANDRY J W, et al. Analysis of granular flow in a pebble-bed nuclear reactor[J]. Physical Review E, 2006, 74(2): 021306. doi: 10.1103/PhysRevE.74.021306 [4] XIA B, ZHANG J, GUO J, et al. Study on the curved channel model in the initial core loading of pebble bed high temperature reactors[J]. Journal of Physics: Conference Series, 2021, 2048(1): 012025. doi: 10.1088/1742-6596/2048/1/012025 [5] 郝琛,李富,郭炯. 球床高温气冷堆卸料燃耗阈值对平均卸料燃耗的影响[J]. 原子能科学技术,2013, 47(S1): 188-191. [6] CHEN H, FU L, JIONG G, et al. Quantitative analysis of uncertainty from pebble flow in HTR[J]. Nuclear Engineering and Design, 2015, 295: 338-345. doi: 10.1016/j.nucengdes.2015.10.005 [7] 李富,经荥清,胡永明,等. 高温气冷堆物理分析程序的发展与验证[C]//第三届反应堆物理与核材料学术研讨会论文集. 北京: 清华大学工程物理系,2007: 12-13. [8] CHEN H, FU L. Investigation on the pebble bed flow model in VSOP[J]. Nuclear Engineering and Design, 2014, 271: 352-355. doi: 10.1016/j.nucengdes.2013.11.061 [9] XIA B, GUO J, LI F. Impacts of burn-up measurement errors on discharge burn-up of PB-HTR[J]. Transactions, 2015, 113(1): 1287-1290. -
计量
- 文章访问数: 97
- HTML全文浏览量: 19
- PDF下载量: 50
- 被引次数: 0
