• 不 限
  • 期刊论文
  • 硕博论文
  • 会议论文
  • 报 纸
  • 英文论文
  2. 您的位置
  3. 首页
  4. 会议论文
  5. Simulation the response characteristics of TEPC to low energy neutron and gamma irradiation with Mon

Simulation the response characteristics of TEPC to low energy neutron and gamma irradiation with Mon

来源 :第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) | 被引量 : 0次 | 上传用户：huangma2009
【摘 要】
：
For evaluation the characteristics of the tissue-equivalent proportional counter(TEPC)in low energy neutron and gamma radiation fields,the energy responses,angle sensitivity,detection efficiency of th
【作 者】
：
Haowei Li Shuhuan Liu Jihua Zhu Yuan Yuan Yao Zhang 
【机 构】
：
School of Nuclear Science and Technology,Xi'an Jiaotong University,Xi'an,Shaanxi,710049,China;Scho
【出 处】
：
第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)
【发表日期】
：
2016年3期
【关键词】
：
Tissue-Equivalent Proportional Counter (TEPC) Monte-Carlo Method Neutron and Gam 
下载到本地 , 更方便阅读
下载此文 赞助VIP
声明 : 本文档内容版权归属内容提供方 , 如果您对本文有版权争议 , 可与客服联系进行内容授权或下架
论文部分内容阅读
　　For evaluation the characteristics of the tissue-equivalent proportional counter(TEPC)in low energy neutron and gamma radiation fields,the energy responses,angle sensitivity,detection efficiency of the cylindrical and spherical structures TEPC are simulated with Monte Carlo method.The major influence factors on TEPC response characteristics are analyzed based on the simulation results.
其他文献
Brazing of SiC with high temperature low activation Ti-Si-Me alloys for fusion applications
SiC/SiC composites are the promising materials for flow channel insert and structural material in advanced fusion reactors.In order to obtain large size composite parts,development of joining technolo
会议
SiC/SiC compositeJoiningTi-Si alloyShear strengthMicro-alloying
The corrosion behaviour of CuCrZr alloy in the water coolant of fusion reactor
The corrosion tests in pure water at 150°C were performed to investigate the corrosion behavior of CuCrZr alloy at different dissolved oxygen content and different flow rate.The weight loss of the all
会议
CuCrZr alloycorrosionfusion reactordissolved oxygenflow rate
Creep deformation and rupture behavior of CLAM steel at 923K
The creep deformation and rupture behavior of CLAM steel has been studied in this article.Creep test were carried out at 923K over a stress range of 90-140MPa.The microstructure of the deformation zon
会议
China low activation martensitic steelHigh temperature creepMicrostructurePre
Effect of the precipitates on austenite grain growth in RAFM steel
Effect of the different types of precipitates and precipitation-dissolution behaviors on austenite grain growth in reduced activation ferritic/martensitic(RAFM)steel was studied by using metallography
会议
RAFM steelAustenite grain growthModellingPrecipitates
Experimental study on the deposition of corrosion products in fusion reactor
Deposition of corrosion products increases radiation in primary coolant loops of reactor.Therefore,the deposition and migration behavior of corrosion products is examined in this experiment.Objective
会议
DepositionCorrosion ProductsFusion Reactor
Design of an experimental loop for research Transport-Deposition behavior of corrosion product on fu
In primary loop,corrosion products in coolant flow come from radioactive zone and deposit on equipment and piping to produce radiation field.Research to determine the behavior of corrosion products de
会议
Corrosion ProductTransport-depositionExperimental LoopFusion Reactor
Hot deformation behavior and processing map of CLAM steel
The deformation behaviors of China Low Activation Martensitic(CLAM)steel were investigated by the thermal simulation compression test on Gleeble-3500 thermal simulator,under experimental parameters th
会议
CLAM steelhot deformationConstitutive equationprocessing map
Microstructural evolution of high Cr ferrite/martensite steel after deformation in metastable austen
High Cr ferrite/martensite steels are the primary candidate structural material used in first-wall of Test Blanket Module(TBM)for fusion reactor applications.In this paper,the influence of compressive
会议
High Cr ferrite/martensite steelDeformationMicrostructure
Kinetics of tritium release process in neutron-irradiated Li4SiO4
Understanding the behavior of tritium release from ceramic breeder materials is important for the design of solid breeding blanket and tritium recovery system in a fusion reactor.In this study,the kin
会议
Li4SiO4Tritium releaseDiffusionDesorptionisotope exchange
A low power front-end ASIC design for the 3D 14MeV neutron microdosimeter
Based on the output signal characteristics of the 14MeV neutron microdosimeter,a low noise,low power consumption and large dynamic range readout front-end electronics(FEE)based on 180nm CMOS technolog
会议
3D Microdosimeter14MeV NeutronFront-End ElectronicsDesign