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浏览/检索结果: 共5条，第1-5条 帮助 已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Measurement of the neutron total cross section of carbon at the Back-n white neutron beam of CSNS 期刊论文 NUCLEAR SCIENCE AND TECHNIQUES, 2019, 卷号: 30 作者:  Liu, Xing-Yan;  Yang, Yi-Wei;  Liu, Rong;  Wen, Jie;  Wen, Zhong-Wei 收藏  |  浏览/下载：40/0  |  提交时间：2019/12/30 CSNS  Back-n white neutron source  NTOX  Neutron total cross section  Carbon  Multilayer fast fission chamber   Measurement of the neutron total cross section of carbon at the Back-n white neutron beam of CSNS 期刊论文 NUCLEAR SCIENCE AND TECHNIQUES, 2019, 卷号: 30, 期号: 9 作者:  Liu, Xing-Yan;  Yang, Yi-Wei;  Liu, Rong*;  Wen, Jie;  Wen, Zhong-Wei 收藏  |  浏览/下载：29/0  |  提交时间：2019/12/27 Back-n white neutron source  CSNS  Carbon  Multilayer fast fission chamber  NTOX  Neutron total cross section   Monte carlo simulation of biological shielding parameters in pgnaa 期刊论文 Micro & nano letters, 2018, 卷号: 13, 期号: 4, 页码: 457-460 作者:  Yang, Jianbo;  Peng, Kexin;  Qiao, Yujie;  Zhang, Can;  Li, Rui 收藏  |  浏览/下载：67/0  |  提交时间：2019/04/23 Monte carlo methods  Radiation protection  Neutron activation analysis  Spontaneous fission  Lead  Boron compounds  Lithium compounds  Neutron absorption  Multilayers  Composite material interfaces  Biological effects of gamma-rays  Monte carlo simulation  Biological shielding parameters  Pgnaa  Prompt neutron activation analysis  Cf-252 spontaneous fission neutron  Optimised radiation protection design parameters  Mcnp monte carlo code  Lead shield thickness  Sample chamber  Neutron-absorbing materials  Biological multilayer composite shield  Thick pb innermost layer  Moderation layer  Thick paraffin  Thick borax  Pgnaa facility  Size 2 mm to 25 cm  Pb  B4c  B2o3  Lioh  Lif   Monte Carlo simulation of biological shielding parameters in PGNAA 期刊论文 MICRO & NANO LETTERS, 2018, 卷号: 13, 期号: 4, 页码: 457-460 作者:  Li, R;  Yang, JB;  Peng, KX;  Qiao, YJ;  Zhang, C 收藏  |  浏览/下载：47/0  |  提交时间：2019/09/24 Monte Carlo methods  radiation protection  neutron activation analysis  spontaneous fission  lead  boron compounds  lithium compounds  neutron absorption  multilayers  composite material interfaces  biological effects of gamma-rays  Monte Carlo simulation  biological shielding parameters  PGNAA  prompt neutron activation analysis  Cf-252 spontaneous fission neutron  optimised radiation protection design parameters  MCNP Monte Carlo code  lead shield thickness  sample chamber  neutron-absorbing materials  biological multilayer composite shield  thick Pb innermost layer  moderation layer  thick paraffin  thick borax  PGNAA facility  size 2 mm to 25 cm  Pb  B4C  B2O3  LiOH  LiF