期刊:
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS,2017年406(Pt.B):470-474 ISSN:0168-583X
通讯作者:
Zhang, Chao;Wang, Dong-Qi
作者机构:
[Song, Huai-Zhi; Wang, Cheng-Jun; Zhang, Chao] Anhui Univ Sci & Technol, Sch Mat Sci & Engn, Huainan 232001, Peoples R China.;[Mao, Fei] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;[Wang, Dong-Qi] Chinese Acad Sci, Inst High Energy Phys, Multidisciplinary Initiat Ctr, Beijing 100049, Peoples R China.;[Zhang, Feng-Shou] Beijing Normal Univ, Coll Nucl Sci & Technol, Minist Educ, Key Lab Beam Technol & Mat Modificat, Beijing 100875, Peoples R China.;[Zhang, Feng-Shou] Beijing Radiat Ctr, Beijing 100875, Peoples R China.
通讯机构:
[Zhang, Chao] A;[Wang, Dong-Qi] C;Anhui Univ Sci & Technol, Sch Mat Sci & Engn, Huainan 232001, Peoples R China.;Chinese Acad Sci, Inst High Energy Phys, Multidisciplinary Initiat Ctr, Beijing 100049, Peoples R China.
会议名称:
27th International Conference on Atomic Collisions in Solids (ICACS)
会议时间:
JUL 24-29, 2016
会议地点:
Chinese Acad Sci, Inst Modern Phys, Lanzhou, PEOPLES R CHINA
会议主办单位:
Chinese Acad Sci, Inst Modern Phys
关键词:
Irradiation damage;SiC composites;Interphase;Electronic excitation effect;Two-temperature model
摘要:
Silicon carbide fiber-reinforced silicon carbide matrix composites have been investigated for their use as structural materials for advanced nuclear reactor. Although quite a number of researches have been devoted to probe the effects of irradiation on various properties of the composites, there is little known about the atomistic mechanism for irradiation resistance. In this study, a two-temperature model has been used to investigate the irradiation damage of SiC/Gra/SiC composites, which includes three parts and two SiC/C interfaces, two single crystal cubic silicon carbide on two sides and a few graphene sheets in the middle part. By simulating 100 keV displacement cascades, we find that the number of defects in the reinforcement is larger than that in the matrix, which indicates the damage in the reinforcement is more serious than that in the matrix. Moreover, we explicitly investigate the damage behavior of the interphase graphene layers and find that some atoms in one graphene sheet form many new chemical bonds with atoms in another one, which leads to the transition from sp(2) to sp(3) hybridization. The newly formed chemical bonds link the different graphene layers and make graphene-like electronic structure more "diamond-like", enhancing the irradiation resistance of the matrix. (C) 2017 Elsevier B.V. All rights reserved.
摘要:
The α decay half-life of the unknown nucleus ~(297)Og is predicted within the two-potential approach, and α preformation probabilities of 64 odd-A nuclei in the region of proton numbers 82<Z< 126 and neutron numbers 152<N<184, from ~(251)Cf to ~(295)Og, are extracted. In addition, based on the latest experimental data, a new set of parameters for α preformation probabilities considering the shell effect and proton-neutron interaction are obtained. The predicted α decay half-life of ~(297)Og is 0.16 ms within a factor of 4.97. The predicted spin and parity of the ground states for ~(269)Sg, ~(285)Fl and ~(293)Lv are 3/2~+,3/2~+ and 5/2~+,respectively.
期刊:
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 5,2017年5
通讯作者:
Cao Jian
作者机构:
[Cao Jian; Yang Sen-gai; Xiong Wen-bin; Li Hu-wei; Mao Huan; Wang Zhan-yong; Wang Chuang; Wang Jing] MEP, Nucl & Radiat Safety Ctr, Beijing 10082, Peoples R China.;[Xie Qin] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.
会议论文集名称:
Proceedings of the 2017 25th International Conference on Nuclear Engineering
摘要:
The whole core model of CEFR is established according to the parameters of China Experimental Fast Reactor which are given by IAEA-TECDOC-1531, and the physical parameters of CEFR are simulated with the MCNP4a program. The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design value, which successfully demonstrates the reliability of this MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.