氮化铀热中子截面的第一性原理计算

王立鹏; 江新标; 吴宏春; 樊慧庆

doi:10.7498/aps.67.20180834

摘要

氮化铀（UN）因其较好的热物性和耐事故容错性成为先进动力堆的候选燃料，但目前热能区缺少可靠的UN热中子截面数据，这对于热中子反应堆物理计算是很不利的.本文基于量子力学的第一性原理，利用VASP/PHONON软件模拟计算了UN的声子态密度，以此为积分得到UN的定容比热容，并基于新制作的声子态密度，采用核截面处理程序NJOY/LEAPR，利用热中子散射理论，得到UN的S（，）数据，进而研究UN的热中子散射截面，并与传统压水堆的二氧化铀（UO2）进行对比.结果表明：优化的晶格参数与数据库符合较好，UN声子态密度的声子项和光子项较UO2的分隔更加明显，定容比热容计算结果与实验值一致，基于该声子态密度计算得到的UN中238U的非弹性散射和弹性散射截面比相同温度下UO2中238U小，UN中N仅考虑了非相干散射部分，随着温度升高，UN弹性散射截面变小，非弹性散射变大，并在高能段趋于自由核散射截面.本文的研究结果填补了UN热中子截面数据的缺失，为下一步系统研究UN燃料在轻水堆中的中子学性能奠定了基础.

关键词:

Abstract

Nuclear design and neutronic analysis of thermal neutron reactor need high reliable thermal neutron cross sections. Uranium mononitride (UN) is a candidate fuel material for advanced power reactor with its better thermodynamics and accident tolerance. However, in thermal neutron region, reliable thermal neutron scattering cross sections are lacked for UN, which is disadvantageous to reactor physics simulations. The scattering law of the UN fuel material may impact the thermal neutron spectrum and criticality of the reactor systems. Neutron cross sections in thermal range are correlated with energy, temperature, physical and chemical properties of the scattering medium, reflecting the phonon spectra of material itself. In this paper, based on the ab initio method of quantum mechanics, phonon density of states in UN are calculated by VASP/PHONON code, and used for integral to obtain UN heat capacity at a constant volume. Adopting this new phonon density of states, NJOY/LEAPR code is used to generate S (, ) data by thermal neutron scattering theory and NJOY/THERMR utilizes these data to produce thermal scattering matrix in order to investigate thermal kernel effect of UN. Subsequently, thermal neutron scattering cross sections of UN are generated with NJOY code system. Comparison with uranium dioxide (UO2) in the traditional PWR is done. Results indicate that optimized lattice parameter are in good agreement with the database; the optical modes are well separated from the acoustic modes compared with UO2; heat capacity at a constant volume is consistent with experimental value; the inelastic and elastic cross sections of 238U in UN are lower than those of 238U in UO2. N in UN only deals with incoherent part in elastic cross sections. As the temperature increases, elastic cross sections of UN decrease while inelastic ones increase, and cross sections approach to free atom cross section at high energies. Considering the limitations of 14N, the scattering law and inelastic scattering cross sections are also under investigation using 15N in UN compound. This paper's conclusion fulfill the vacancy of thermal neutron scattering cross sections of UN, which laid a foundation for systematic study on the neutronics properties of UN fuel in the light water reactors as well as for the design of new neutron moderators and neutron filer.

Keywords:

UN /
ab initio /
phonon spectrum /
thermal neutron scattering cross section

作者及机构信息

1.
1. 西安交通大学核科学与技术学院, 西安 710049;

2.
2. 西北核技术研究所, 西安 710024;

3.
3. 西北工业大学材料学院, 西安 710072

通信作者: 王立鹏, wang0214@126.com

Authors and contacts

1.
1. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China;

2.
2. Northwest Institute of Nuclear Technology, Xi'an 710024, China;

3.
3. School of Materials Science and Engineering, Northwestern Polytechnical University, Xi'an 710072, China

Corresponding author: Wang Li-Peng, wang0214@126.com

参考文献

[1]

[1] Choi J, Ebbinghaus B, Meier T 2006 UCRL-TR-218931 (Lawrence Livermore National Laboratory)
[2] Zakova J, Wallenius J 2012 Ann. Nucl. Energy 47 182
[3] Hawari A I 2014 Nucl. Data Sheets 118 172
[4] Wang L P, Jiang X B, Zhao Z M, Chen L X 2013 Nucl. Eng. Des. 262 365
[5] Wang L P, Jiang X B, Zhao Z M, Chen L X 2015 Proceedings of the 23 th International Conference on Nuclear Engineering Chiba, Japan, May 17-21, 2015 ICONE23-TP046
[6] X-5 Monte Carlo Team 2003 LA-03-1987-M (Los Alamos National Laboratory)
[7] Brown D A, Chadwick M B, Capote R, et al. 2018 Nucl. Data Sheets 148 1
[8] Zhu Y W, Hawari A I 2015 Proceedings of International Conference on Nuclear Criticality Safety Charlotte, North Carolina, September 13-17, 2015 p874
[9] Zhu Y W, Hawari A I 2018 Proceedings of the PHYSOR 2018 Cancun, Mexico, April 22-26, 2018
[10] Macfarlane R E, Muir D W 1994 LA-12470-M (Los Alamos National Laboratory)
[11] Macfarlane R E, Muir D W 2012 LA-UR-12-27079 (Los Alamos National Laboratory)
[12] Bell G I, Gasstone S (translated by Qian Li) 1970 Nuclear Reactor Theory (Beijing: Science Press) pp235-243 (in Chinese)[贝尔 G I, 格拉斯 S 著 (千里译) 1970 核反应堆理论 (北京: 原子能出版社)第235–243页]
[13] Xie Z S, Yin B H 2004 Nuclear Reactor Physics Analysis (Beijing: Atom Press) p120 (in Chinese)[谢仲生, 尹邦华 2004 核反应堆物理分析 (北京: 原子能出版社) 第120页]
[14] Mclane V 2009 BNL-NCS-44945-01/03-Rev (Brookhaven National Laboratory)
[15] Mattes M, Keinert J 2005 INDC(NDS)-0470 (International Nuclear Data Committee)
[16] MedeA_221 2017 Materials Design Inc., Angel Fire, NM, USA.
[17] Perdew J P, Burke K, Ernzerhof M 1996 Phys. Rev. Lett. 77 3865
[18] Sears V F 1992 International Tables for Crystallography (Vol. C) Mathematical, Physical and Chemical Tables (Dordrecht: Kluwer Academic Publishers)
[19] Koppel J U, Houston D H 1968 GA-8774 Revised (U. S. Atomic Energy Commission)
[20] Kurosaki K, Yano K, Yamada K 2000 J. Alloys Compd. 297 1
[21] Hayes S L, Thomas J K, Peddicord K L 1990 J. Nucl. Mater. 171 262

施引文献

[1]

[1] Choi J, Ebbinghaus B, Meier T 2006 UCRL-TR-218931 (Lawrence Livermore National Laboratory)
[2] Zakova J, Wallenius J 2012 Ann. Nucl. Energy 47 182
[3] Hawari A I 2014 Nucl. Data Sheets 118 172
[4] Wang L P, Jiang X B, Zhao Z M, Chen L X 2013 Nucl. Eng. Des. 262 365
[5] Wang L P, Jiang X B, Zhao Z M, Chen L X 2015 Proceedings of the 23 th International Conference on Nuclear Engineering Chiba, Japan, May 17-21, 2015 ICONE23-TP046
[6] X-5 Monte Carlo Team 2003 LA-03-1987-M (Los Alamos National Laboratory)
[7] Brown D A, Chadwick M B, Capote R, et al. 2018 Nucl. Data Sheets 148 1
[8] Zhu Y W, Hawari A I 2015 Proceedings of International Conference on Nuclear Criticality Safety Charlotte, North Carolina, September 13-17, 2015 p874
[9] Zhu Y W, Hawari A I 2018 Proceedings of the PHYSOR 2018 Cancun, Mexico, April 22-26, 2018
[10] Macfarlane R E, Muir D W 1994 LA-12470-M (Los Alamos National Laboratory)
[11] Macfarlane R E, Muir D W 2012 LA-UR-12-27079 (Los Alamos National Laboratory)
[12] Bell G I, Gasstone S (translated by Qian Li) 1970 Nuclear Reactor Theory (Beijing: Science Press) pp235-243 (in Chinese)[贝尔 G I, 格拉斯 S 著 (千里译) 1970 核反应堆理论 (北京: 原子能出版社)第235–243页]
[13] Xie Z S, Yin B H 2004 Nuclear Reactor Physics Analysis (Beijing: Atom Press) p120 (in Chinese)[谢仲生, 尹邦华 2004 核反应堆物理分析 (北京: 原子能出版社) 第120页]
[14] Mclane V 2009 BNL-NCS-44945-01/03-Rev (Brookhaven National Laboratory)
[15] Mattes M, Keinert J 2005 INDC(NDS)-0470 (International Nuclear Data Committee)
[16] MedeA_221 2017 Materials Design Inc., Angel Fire, NM, USA.
[17] Perdew J P, Burke K, Ernzerhof M 1996 Phys. Rev. Lett. 77 3865
[18] Sears V F 1992 International Tables for Crystallography (Vol. C) Mathematical, Physical and Chemical Tables (Dordrecht: Kluwer Academic Publishers)
[19] Koppel J U, Houston D H 1968 GA-8774 Revised (U. S. Atomic Energy Commission)
[20] Kurosaki K, Yano K, Yamada K 2000 J. Alloys Compd. 297 1
[21] Hayes S L, Thomas J K, Peddicord K L 1990 J. Nucl. Mater. 171 262

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