KAERI is carrying out thermal-hydraulic safety research which is a prerequisite for reactor safety. Thermal-hydraulic safety research is to investigate the major thermal - hydraulic phenomena and to demonstrate the safety performance of major systems and components of nuclear power plants and apply it to a design and safety evaluation. By thoroughly studying a variety of thermal - hydraulic phenomenon and safety characteristics, we are preparing for the abnormalities or accidents which might happen in a nuclear reactor.

KAERI has upgraded its level of thermalhydraulic research infrastructures and related technology to those of advanced countries by constructing and operating a test facility which simulates comprehensive thermal-hydraulic behaviors at real nuclear power plants.

• Large-scale verification tests on the APR1400 new design features (MIDAS, VAPER, etc.)
• Thermal-hydraulic experiment for nuclear fuel and reactor cores focusing on the critical heat flux phenomenon
• Experiment and analysis on the severe accident behavior of nuclear reactors
• Development of the MARS, system safety analysis code
• Constructing and operating the ATLAS integral test facility

KAERI is developing Probabilistic Safety Assessment(PSA) technology for a large-scale complex such as nuclear power plants and chemical plants and supplying its own related technologies to the regulatory body and nuclear industries. KAERI has exported the developed PSA tools and related technologies to the USA and other countries.

• Development of KIRAP(KAERI Integrated Reliability Analysis code Package) and its export to the USA
• Supply the VIP, physical protection support code, to the IAEA
• Export FTREX, a core module for PSA, to the USA, Canada & etc. via EPRI

For the realistic safety analysis for the commercially operating CANDU reactors, we are developing a self-reliant lattice code (WIMS/CANDU), improving the fuel channel analysis methodology using CATHENA code, and performing 3 dimensional CFD analysis. Furthermore, our works deal with safety issues causing from an aged core and inquiry from the plant site.

• Reactor physics and thermal-hydraulics relevant to an aged core
• Development of a self reliant lattice code (WIMS-CANDU) for estimation of void reactivity
• 3D CFD analysis for moderator
• Validation of thermal-hydraulic analysis code and benchmarking tests using CFD code
• Establishment of data base for reactor physics and thermal-hydraulic tests
• Development of high burn-up and low enrichment fuel for improving economic and safety aspects of a CANDU reactor

KAERI is making efforts to harmonize nuclear energy and the environment with advanced radiation protection technologies. KAERI is also conducting researches on an environmental assessment around nuclear facilities to secure a nuclear safety. Nuclear Environmental research aimed at protecting humans and the environment from radiation is a prerequisite for ensuring a continuous utilization of nuclear energy.

• Development of the technology for an environmental radiation monitoring, assessment, analysis near nuclear facilities
• Development of the technology for radiation exposure and emergency management
• Analysis of radiation ecology and related research on radiation biology
• Establishment of the capability to manage the accidents at nuclear facilities and monitoring systems

Equipment at the operating reactors have been damaged due to such factors as high temperature, high pressure, irradiation and coolant. KAERI is making efforts to establish material damage fundamentals to assure the reliability and integrity of nuclear materials under extreme conditions.

Advanced and new structural materials with a higher resistance to harsh and extreme environments and proactive technologies against a material aging degradation are being developed to maintain and increase the safety of major reactor components.

KAERI is also developing advanced and new functional materials using nano technology.

• Development of proactive technologies against a nuclear material degradation
• Periodic surveillance tests on the operating reactors
• Development of innovative structural materials for advanced nuclear systems such as Gen-IV and fusion reactors
• Development of advanced and new materials using nano technology