International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)

Session

5.3 Advanced Fast Reactor Cladding Development I

27 Jun 2017, 10:20

Yekaterinburg

Conveners

5.3 Advanced Fast Reactor Cladding Development I

• Liudmila Zabudko (Innovative &Technology Center by "PRORYV" Project)
• Jeong-Yong Park (Korea Atomic Energy Research Institute)

77. Development of core and structural materials for fast reactors

Dr Tai Asayama (Japan Atomic Energy Agency)

27/06/2017, 10:20

Track 5. Fast Reactor Materials (Fuels and Structures) and Technology

ORAL

This paper summarizes ongoing efforts in Japan Atomic Energy Agency on the development of core and structural materials for sodium-cooled fast reactors. For core materials, oxide dispersion strengthened (ODS) steels and 11Cr ferritic steel (PNC-FMS) will be applied to fuel pin cladding and wrapper tube, respectively. As for ODS steel, 9Cr,11Cr-ODS steels have been extensively developed. Their...

32. Results of monitoring, using high-resolution neutron diffraction, of radiation-induced damages in claddings of fuel pins after their performance in the reactor BN-600 as a ground for prolongation of their life expectancy

Dr Vladimir Bobrovskii (M.N. Miheev Institute of Metal Physics of Ural Branch of Russian Academy of Sciences)

27/06/2017, 10:40

Track 5. Fast Reactor Materials (Fuels and Structures) and Technology

ORAL

Fast neutron irradiation gives rise to rather complex processes developing in the fuel element claddings that lower their technical characteristics and restrict time of safe exploitation. Neutron diffraction studies open up a possibility to monitor them even at a stage of incubation period and thereby to promote development of reliable methods for life expectancy prolongation of the reactor...

153. FRACTURE STRAIN AND FRACTURE TOUGHNESS PREDICTION FOR IRRADIATED AUSTENITIC STEELS OVER WIDE RANGE OF TEMPERATURES TAKING INTO ACCOUNT THE EFFECT OF SWELLING AND THERMAL AGEING

Dr Alexander Sorokin (Central Research Institute of Structural Materials “Prometey”)

27/06/2017, 11:00

Track 5. Fast Reactor Materials (Fuels and Structures) and Technology

ORAL

Fracture toughness and fracture strain of austenitic steels are the important performance properties, which control serviceability of the components of fast reactors including fuel assemblies. It is known that the above properties decrease under irradiation and thermal ageing. Especially strong decrease of fracture toughness occurs under irradiation accompanied by swelling. It is necessary to...

5. IAEA activities in the area of Nuclear Power Reactor Fuel Engineering

Dr Mikhail Veshchunov (IAEA)

27/06/2017, 11:20

Track 5. Fast Reactor Materials (Fuels and Structures) and Technology

ORAL

The main IAEA program implementation tools in the area of fuel engineering are Coordinated Research Projects (CRP), Technical Meetings (TM), Expert Reviews, and NEA-IAEA International Fuel Performance Experiments (IFPE) Database. This report provides information about organization and implementation practices of these activities, and summarizes their major outputs including ongoing CRPs and...

94. Examination of Fast Reactor Materials and Structural Elements at JSC “INM” Premises

Mr Alexander Kozlov (Joint Stock Company "Institute of Nuclear Materials")

27/06/2017, 11:40

Track 5. Fast Reactor Materials (Fuels and Structures) and Technology

ORAL

At the Institute of Nuclear Materials post irradiation examination has been carried out since BN-600 reactor commissioning to justify safety and reliability of different core elements during routine operation and to search for new ways of extending their service life. The examination is carried out in close cooperation with the design bureau (Afrikantov OKBM), nuclear operator (Beloyarsk NPP),...