Conveners
5.4 Advanced Fast Reactor Cladding Development II
- V. Chuyev
- Tai Asayama (Japan Atomic Energy Agency)
Mr
Alexander Kozlov
(Joint Stock Company "Institute of Nuclear Materials")
27/06/2017, 13:50
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Nowadays austenitic stainless steels are used as a cladding material for BN-600 and BN-800 reactors. Examinations carried out at the end of fuel element service life give the information about cladding state. On the basis of the examination it is necessary: 1 – to determine residual life and 2 – to find the way for its extension.
Extrapolation methods are generally used for the first aspect....
Mr
Vyacheslav Shikhalev
(Joint Stock Company "Institute of Nuclear Materials")
27/06/2017, 14:10
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Electrical potential testing which is a primary nondestructive testing method is used at JSC "INM" hot cells as an incoming inspection of spent BN-600 and BN-800 reactor fuel elements.
Electrical resistivity curves demonstrate the level of the fuel element defectiveness and help to work out a cladding dismantling plan for further post irradiation materials examination of the cladding problem...
409.
OPERABILITY VALIDATION OF FUEL PINS WITH CLADDINGS MADE OF EK164-ID STEEL IN THE BN-600 REACTOR
Mr
Sergey Belov
(JSC “Afrikantov OKBM”)
27/06/2017, 14:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
To ensure the increased fuel burn-up in the BN-600 and BN-800 reactors, EKA64-ID steel is going to be used as a fuel rod cladding material because it has bigger index of radiation resistance (swelling and creeping) in comparison with the used ChS68-ID steel. To introduce this steel, an irradiation examination of experimental FSAs is needed to be performed. Owing to the irradiation examination,...
Dr
Lizhen Tan
(Oak Ridge National Laboratory)
27/06/2017, 14:50
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Optimized Grade 92 has been developed at Oak Ridge National Laboratory in support of the USA Sodium-cooled Fast Reactor program. Composition modification and processing optimization successfully achieved the development of optimized Grade 92 with desired microstructures for superior properties. A variety of properties have been assessed for optimized Grade 92, which include tensile, creep,...
