Recruitment for Postdoctoral Fellow
(Fixed-term researcher)

1. Physics	Chemistry	Mathematics	Geo and Environemtal Sciences	Biology	Radiation
   Mechanics	Material	Electricity and Electronics	Architectural and Civil Engineering	Applied Physics	Applied Chemistry
   Chemical Engineering	Measurements and Instruments	Computer and Information	Robotics	Other	All

2. No	Theme
   	Department	Section	Location	Contact Person	Radiation Worker/ Non-Radiation Worker	Field (for reference）
   	Summary
   J4	Study on the methodology of the structural integrity assessment for nuclear reactor components
   	Nuclear Safety Research Center	Structural Integrity Research Group	Tokai Research and Development Center Nuclear Science Research Institute	Yinsheng Li Tel:+81-29-282-6457 E-mail: li.yinsheng@jaea.go.jp	Non-Radiation Worker	Mechanics Material Applied Physics Physics Architectural and Civil Engineering Computer and Information
   	Because of the ageing degradation due to long term operation for Japanese nuclear power plants, developing the methodologies of structural integrity assessments for the reactor components concerning neutron irradiation, stress corrosion cracking and so on is of great importance. In this theme, researches on the deterministic approaches such as weld residual stress evaluation, crack propagation evaluation under large scale yielding condition, fracture evaluation concerning the crack or thinning for nuclear components are conducted on the basis of numerical simulation, material testing, and fracture testing and so on. In addition, probabilistic fracture mechanics analysis codes concerning ageing degradation of nuclear components are developed on the basis of the knowledge obtained from simulation and testing.
   J10	Study on a Level 3 Probabilistic Risk Analysis of nuclear power plants
   	Nuclear Safety Research Center	Radiation Risk Analysis Research Group	Tokai Research and Development Center Nuclear Science Research Institute	Masanori Kimura Tel:+81-29-282-5459 E-mail: kimura.masanori@jaea.go.jp	Non-Radiation Worker	Physics Chemistry Mathematics Geo and Environemtal Sciences Radiation Architectural and Civil Engineering Computer and Information
   	A level 3 probabilistic risk assessment (PRA) is an offsite consequence analysis for a severe accident and estimates the frequency and severity of the consequences to the public. Probabilistic accident consequence assessment models and computer codes are an integral part of level 3 PRA of nuclear power plants. Our research group has developed a level 3 PRA code, OSCAAR. In this theme, researches on the probabilistic accident consequence assessment for health effects and economic consequence are conducted considering site-dependent on metrological, population, agricultural and economic data by using OSCAAR.