论文摘要
A shield module is associated with an Indian Test Blanket Module（TBM） in ITER to limit the radiation doses in port inter-space areas. The shield module is made of stainless steel plates and water channels. It is identified as an important component for radiation protection because of its radiation exposure control functionality. The radiation protection classification leads to more assurance of the component design. In order to validate and verify the design of the shield module, a neutronic laboratory-scale experiment is designed and executed. The experiment is planned by considering the irradiation under a neutron source of 14 Me V and yields of 1010 n s-1. The reference neutron spectrum of the ITER TBM shield module has been achieved through optimization of the neutron source spectrum by a combination of steel and lead materials. The neutron spectrum and flux are measured using a multiple foil activation technique and neutron dose-rate meter LB 6411（He-3 proton recoil counter with polyethylene）,respectively. The neutronic design simulation is assessed using MCNP5 and FENDL 2.1 crosssection data. The paper covers neutronic design, irradiation and the outcome of the experiment in detail.
论文目录
文章来源
类型: 期刊论文
作者: H L SWAMI,M ABHANGI,Sanchit SHARMA,S TIWARI,A N MISTRY,V VASAVA,V MEHTA,S VALA,C DANANI,V CHAUDHARI,P CHAUDHURI
来源: Plasma Science and Technology 2019年06期
年度: 2019
分类: 基础科学,工程科技Ⅱ辑
专业: 核科学技术
单位: Pandit Deendayal Petroleum University (HBNI)
分类号: TL344
页码: 151-156
总页数: 6
文件大小: 864K
下载量: 1