التفاصيل البيبلوغرافية
| العنوان: |
不同评价核数据库对堆芯物理计算结果有效增殖系数的影响与分析. (Chinese) |
| Alternate Title: |
Influence and Analysis of Different Evaluation Nuclear Data Libraries on Reactor Core Physics Calculation keff. (English) |
| المؤلفون: |
秦凯文, 杨波, 刘豪杰, 钱云琛, 王子鸣, 刘义保 |
| المصدر: |
Science Technology & Engineering; 2023, Vol. 23 Issue 3, p1063-1068, 6p |
| Abstract (English): |
The accuracy of nuclear data affects reactor safety and is of great significance in the process of reactor core physics calculations. In order to study the influence of different nuclear databases on the effective multiplication factor of the critical calculation results, the five latest international evaluation nuclear databases ENDF/B-VIII.0, JENDL5, JEFF3.3, BROND3.1 and CENDL3.2 based on the nuclear data processing program NJOY21 were produced, 119 critical benchmark models specifically was selected for nuclear data examination, and MCNP6.1 was used to carry out the criticality calculations. The influence of nuclear databases on the critical calculation was determined by statistically analyzing of the ratio of the deviation between the calculation results and the benchmark experiment results to the uncertainty of the benchmark experiment, and its three characteristic quantities. The results show that the accuracy of the critical calculation results using the ENDF/B-VIII.0 nuclear database is higher, whereas the BROND3.1 and CENDL3.2 nuclear databases show large errors in the critical calculation process, and data analysis reveals that the main reason for this is that the BROND3.1 and CENDL3.2 nuclear databases lack the thermal neutron scattering cross-section data S (α,β). The thermal neutron scattering cross section data S (α,β) from the ENDF/B-VIII.0 nuclear database was imported for critical simulation into the BROND3.1 and CENDL3.2 nuclear databases, and the calculation results were significantly improved. Therefore, it is recommended that the thermal neutron scattering cross-section data S (α,β) be improved as soon as possible in future nuclear data evaluation work in order to improve the accuracy of the nuclear database in the process of reactor physics calculations. [ABSTRACT FROM AUTHOR] |
| Abstract (Chinese): |
核数据的准确性影响反应堆安全，在反应堆堆芯物理计算过程中具有重要意义。为了研究不同核数据库对临界计算结果有效增殖系数的影响，基于核数据处理程序NJOY21对国际上最新的5个评价核数据库ENDF/B-Ⅷ.0、JENDL5、JEFF3.3、BROND3.1、CENDL3.2进行制作，选取专门用于核数据检验的119道临界基准模型，利用MCNP6.1开展临界计算。通过统计分析不同核数据库计算结果与基准实验结果的偏差与基准实验不确定性的比值及其三个特征量来判断核数据库对临界计算的影响。结果表明：采用ENDF/B-VIII.0核数据库的临界计算结果准确性更高，其中BROND3.1和CENDL3.2核数据库在临界计算过程中出现了较大误差，通过数据分析发现其主要原因是BROND3.1和CENDL3.2核数据库缺乏热中子散射截面数据S（α,β）。将ENDF/B-VIII.0核数据库中的热中子散射截面数据S（α,β）导入BROND3.1、CENDL3.2核数据库中进行临界模拟，计算结果发生了明显改善。因此，建议在今后的核数据评价工作中尽快完善热中子散射截面数据S（α,β）,以提高核数据库在反应堆物理计算过程中的准确性。 [ABSTRACT FROM AUTHOR] |
|
Copyright of Science Technology & Engineering is the property of Chinese Society of Technology Economics and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.) |
| قاعدة البيانات: |
Complementary Index |