不同数据库中56Fe评价截面对屏蔽计算影响研究

辐射防护 ›› 2023, Vol. 43 ›› Issue (S1): 1-7.

不同数据库中⁵⁶Fe评价截面对屏蔽计算影响研究

池晓淼, 韩毅, 陈法国, 马翔宇, 沈华亚

中国辐射防护研究院,太原 030006

收稿日期:2022-12-07 出版日期:2023-08-15 发布日期:2023-09-14
通讯作者: 陈法国。E-mail:chenfaguo1@126.com
作者简介:池晓淼(1994—),男,2017年毕业于哈尔滨工程大学核科学与核技术专业,获学士学位,2020年毕业于哈尔滨工程大学核科学与技术专业,获硕士学位,助理研究员。E-mail:chixiaomiao_heu@163.com
基金资助:
国防基础研究计划(批准号:JCKY2020201C016),山西省基础研究计划基金(批准号:20210302124178)。

Research on the influence of ⁵⁶Fe evaluation cross section of different databases on shielding calculation

CHI Xiaomiao, HAN Yi, CHEN Faguo, MA Xiangyu, SHEN Huaya

China Institute for Radiation Protection, Taiyuan 030006

Received:2022-12-07 Online:2023-08-15 Published:2023-09-14

摘要/Abstract

摘要： 为了对各类评价库中⁵⁶Fe截面在屏蔽计算方面的适用性和精确度进行评估,选用FE DIA100 R150代表性基准题对不同评价库及同一评价库不同版本中⁵⁶Fe截面数据质量进行评价;并基于CENDL-3.2评价库,开展了对⁵⁶Fe的敏感性分析工作,主要对其关键反应道截面在屏蔽计算方面的影响进行研究。研究结果表明:(1)由于⁵⁶Fe的弹性散射截面和非弹性散射截面数据准确度的缺失,导致1.20~1.70 MeV、10.00~17.00 MeV等能区,各类评价库计算值与实验测量值差异均较大;(2)⁵⁶Fe中的(n, n)和(n, n′)d反应截面对屏蔽计算影响最为敏感;(3)CENDL-3.2中⁵⁶Fe(n, n)反应截面值在0.01~0.10 MeV能区较真实值截面值偏高。

关键词: ⁵⁶Fe, 屏蔽计算, 评价核数据库, 敏感性分析

Abstract: ⁵⁶Fe evaluation cross sections are still being updated at home and abroad. In order to evaluate the applicability and accuracy of ⁵⁶Fe cross sections in various evaluation libraries and different versions of the same evaluation library in shielding calculation, this paper selects the FE DIA100 R150 benchmark with the evaluation the cross-section data quality of ⁵⁶Fe in different evaluation libraries. And based on the CENDL-3.2 evaluation library, the sensitivity analysis of ⁵⁶Fe stable isotopes was carried out, and the influence of key reaction channel sections of ⁵⁶Fe on shielding calculation was studied. Some main conclusions are drawn as follows. 1) Due to the lack of accuracy of the elastic scattering cross section and inelastic scattering cross section of ⁵⁶Fe, there are large differences between the calculated values of various evaluation libraries and the experimental measurements in the energy regions of 1.20-1.70 MeV and 10.00-17.00 MeV. 2) The (n, n) and (n, n′)d reaction cross-sections in ⁵⁶Fe are the most sensitive factors to the influence of shielding calculations. 3) In CENDL-3.2, the cross section value of ⁵⁶Fe(n, n) is higher than the real value in the energy region of 0.01-0.10 MeV.

Key words: ⁵⁶Fe, shielding calculations, evaluation nuclear database, sensitivity analysis

中图分类号:

TL328

池晓淼, 韩毅, 陈法国, 马翔宇, 沈华亚. 不同数据库中⁵⁶Fe评价截面对屏蔽计算影响研究[J]. 辐射防护, 2023, 43(S1): 1-7.

CHI Xiaomiao, HAN Yi, CHEN Faguo, MA Xiangyu, SHEN Huaya. Research on the influence of ⁵⁶Fe evaluation cross section of different databases on shielding calculation[J]. RADIATION PROTECTION, 2023, 43(S1): 1-7.

参考文献 20

[1]	Oyama Y, Kosako K, Maekawa H. Measurement and calculations of angular neutron flux spectra from iron slabs bombarded with 14. 8 MeV neutrons[J]. Nuclear Science & Engineering the Journal of the American Nuclear Society, 1993, 115:1(1):24-37.
[2]	Wenner M T, Haghighat A, Adams J M, et al. Novel investigation of iron cross sections via spherical shell transmission measurements and particle transport calculations for material embrittlement studies[J]. Nuclear Science and Engineering, 2017, 170(3): 207-233.
[3]	Chadwick M B, Dupont E, Bauge E, et al. The CIELO collaboration: neutron reactions on 1H, 16O, 56Fe, 235, 238U, and 239Pu[J]. Nuclear Data Sheets, 2014, 118: 1-25.
[4]	Brown D A,Chadwick M B, Capote R, et al. ENDF/B-VIII.0: The 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data[J]. Nuclear Data Sheets, 2018, 148:1-142.
[5]	Herman M, Trkow A, Capote R, et al.Evaluation of neutron reactions on iron isotopes for CIELO and ENDF/B-VIII.0[J]. Nuclear Data Sheets, 2018, 148:214-253.
[6]	Ge Z, Xu R, Wu H, et al. CENDL-3.2: The new version of Chinese general purpose evaluated nuclear data library[C]// European Physical Journal Web of Conferences. EPJWC, 2020.
[7]	钱晶, 葛智刚, 刘廷进,等. 20 MeV以下快中子与56Fe非弹性散射截面的分歧研究[J]. 原子核物理评论, 2017, 34(3):514-519.
[8]	Jansky B, Otopal P, Novak E. Data for calculation of the neutron and gamma leakage spectra from iron and water spheres with Cf-252 neutron source in centre (version 23. 11. 2000)[R]. Nuclear Research Institute Rez, 2000.
[9]	Iwamoto O, Iwamoto N, Shibata K, et al. Status of JENDL[C]//EPJ Web of Conferences. EDP Sciences, 2020, 239: 09002.
[10]	Plompen A J M, Cabellos O, De Saint Jean C, et al. The joint evaluated fission and fusion nuclear data library, JEFF-3.3[J]. The European Physical Journal A, 2020, 56(7): 1-108.
[11]	Blokhin A I, Gai E V, Ignatyuk A V, et al. New version of neutron evaluated data library BROND-3.1[J]. Yad Reak Konst, 2016, 2(2): 62.
[12]	Goorley T, James M, Booth T, et al. Initial MCNP6 release overview - MCNP6 version 1.0[R]. 2013.
[13]	Conlin J L, Kahler A C, McCartney A P, et al. NJOY21: Next generation nuclear data processing capabilities[C]//EPJ Web of Conferences. EDP Sciences, 2017, 146: 09040.
[14]	李松阳, 王侃, 余纲林. MCNP温度相关中子截面库制作方法[J]. 核动力工程, 2008, 29(4):10-13+30.
[15]	Sajo E, Williams M L, Asgari M. Comparison of measured and calculated neutron transmission through steel for a 252Cf source[J]. Annals of Nuclear Energy, 1993, 20(9): 585-604.
[16]	Jansky B, Turzik Z, Novak E, et al. Neutron spectra measurement and calculations using different data libraries in iron benchmark assembly[C]//International Conference on Nuclear Data for Science and Technology. EDP Sciences, 2007: 961-964.
[17]	Shu W, Zu T, Cao L, et al. Performance of CENDL-3.2 evaluated nuclear data library for the shielding benchmarks[J]. Progress in Nuclear Energy, 2021, 136: 103727.
[18]	Nunnenmann E, Fischer U. V&V analyses of the GEANT4 Monte Carlo code toolkit with computational and experimental fusion neutronics benchmarks[J]. Fusion Engineering and Design, 2019, 146: 1579-1582.
[19]	Devkin B V, Kobozev M G, Simakov S P, et al. Neutron leakage spectra from iron spheres[C]// 18th Symp. on Fusion Technology, 22-26 Aug 1994. 1994.
[20]	Williams M L, Aboughantous C, Asgari M, et al. Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V and ENDF/B-VI iron evaluations[J]. Annals of Nuclear Energy, 1991, 18(10): 549-565.

不同数据库中⁵⁶Fe评价截面对屏蔽计算影响研究

Research on the influence of ⁵⁶Fe evaluation cross section of different databases on shielding calculation

PDF (PC)

赞

可视化

摘要/Abstract

引用本文

使用本文

参考文献 20

相关文章 1

Metrics

本文评价

推荐阅读 10