A development program was undertaken to support the materials selection for steam generator piping and IHX which are to be used in Liquid Metal Fast Breeder Reactors (LMFBR). Four major topics were reviewed, describing the results obtained as well as the direction of future tests. These topics are: carbon transport in sodium, effect of carbon loss/gain upon materials in the reactor Intermediate Heat Transport System (IHTS), corrosion fatigue and aqueous corrosion. The results support the initial assumptions made in specifying the use of 2-1/4Cr-1Mo as the construction material for the evaporator and superheater and Type 316 piping of the IHT system. Future direction of the experimental programs is to further verify the materials choice and ...
AbstractPrototype Fast Breeder Reactor (PFBR) is a 500 MWe pool type sodium cooled reactor. The main...
This review considers the broad set of corrosive degradations that can occur in PWR steam generators...
AbstractNitrogen-alloyed low-carbon grade type 316L(N) SS is the principal material for high tempera...
Design and development of a once -through sodiumheated steam generator are discussed. Research propo...
Available information on the corrosion behavior and mechanical properties of structural materials in...
An attempt has been made to categorise the various materials, which have been considered for a sodiu...
The sodium cooled fast reactor is selected by France as the most mature GEN IV concept to be industr...
This report gives a description of the activities in design, fabrication, construction, and assembli...
Liquid sodium is used as a coolant in fast breeder reactors on account of its excellent heat transfe...
The use of liquid sodium as a heat transfer fluid has shown great promise and application in nuclear...
Development of advanced materials along with improved high temperature mechanical properties, partic...
AbstractLow cycle fatigue and long-term creep properties, as well as compatibility with liquid sodiu...
Activities in a program to develop and construct a steam generator and test loop for use with a 30-M...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
Abstract. Fast breeder reactors (FBRs) are destined to play a crucial role in the Indian nuclear pow...
AbstractPrototype Fast Breeder Reactor (PFBR) is a 500 MWe pool type sodium cooled reactor. The main...
This review considers the broad set of corrosive degradations that can occur in PWR steam generators...
AbstractNitrogen-alloyed low-carbon grade type 316L(N) SS is the principal material for high tempera...
Design and development of a once -through sodiumheated steam generator are discussed. Research propo...
Available information on the corrosion behavior and mechanical properties of structural materials in...
An attempt has been made to categorise the various materials, which have been considered for a sodiu...
The sodium cooled fast reactor is selected by France as the most mature GEN IV concept to be industr...
This report gives a description of the activities in design, fabrication, construction, and assembli...
Liquid sodium is used as a coolant in fast breeder reactors on account of its excellent heat transfe...
The use of liquid sodium as a heat transfer fluid has shown great promise and application in nuclear...
Development of advanced materials along with improved high temperature mechanical properties, partic...
AbstractLow cycle fatigue and long-term creep properties, as well as compatibility with liquid sodiu...
Activities in a program to develop and construct a steam generator and test loop for use with a 30-M...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
Abstract. Fast breeder reactors (FBRs) are destined to play a crucial role in the Indian nuclear pow...
AbstractPrototype Fast Breeder Reactor (PFBR) is a 500 MWe pool type sodium cooled reactor. The main...
This review considers the broad set of corrosive degradations that can occur in PWR steam generators...
AbstractNitrogen-alloyed low-carbon grade type 316L(N) SS is the principal material for high tempera...