In-situ evaluation for activated concrete in accelerator facility with scintillation-type gamma-ray spectrometer

作     者：Go Yoshida Hiroshi Matsumura Koichi Nishikawa Akihiro Toyoda Yoshiharu Miyazaki Kazuyoshi Masumoto Hajime Nakamura Taichi Miura Go Yoshida;Hiroshi Matsumura;Koichi Nishikawa;Akihiro Toyoda;Yoshiharu Miyazaki;Kazuyoshi Masumoto;Hajime Nakamura;Taichi Miura

作者机构：High Energy Accelerator Research Organization(KEK)1-1 OhoTsukubaIbaraki 305-0801Japan The Medical and Pharmacological Research Center FoundationWo-32Inoyama-machiHakuiIshikawa 925-0613Japan 

出 版 物：《辐射防护》 (Radiation Protection)

年 卷 期：2020年第40卷第6期

页      面：545-549页

学科分类：082704[工学-辐射防护及环境保护] 08[工学] 081304[工学-建筑技术科学] 0805[工学-材料科学与工程（可授工学、理学学位）] 080502[工学-材料学] 082701[工学-核能科学与工程] 0827[工学-核科学与技术] 0813[工学-建筑学] 

基　　金：performed with the aid of the Radiation Safety Research Promotion Fund “Clearance of materials from the decommissioning of accelerator facilities” by the Japan Nuclear Regulation Authority 

主　　题：activation accelerator concrete scintillation detector PHITS code 

摘      要：The assessment of activated concrete is particularly difficult during the decommissioning of an accelerator *** analysis by core boring is the only method of investigating the activity of concrete *** address this problem,an in-situ and nondestructive analysis method was developed to determineγ-ray-emitting nuclides and their specific activities in the concrete walls and floor by using a portable germanium semiconductor *** this work,we examined a substitute for Ge detector to establish a simpler and more convenient *** candidates,we focused on some scintillation type spectrometers,and the possibility of a substitute for a Ge detector was examined by both simulation and *** detection limits were roughly estimated through Monte Carlo simulation for various scintillation crystals,and it was found that 1.5-inch LaBr3,CeBr3,and SrI2 could distinguish the clearance *** was confirmed that the 1.5-inch LaBr3 could reproduce the calibration curve of the Ge detector in the *** required thickness and length of the radiation shield for suppressing the background radiation during the measurement was also determined for the convenience of an actual decommissioning work.