This paper summarizes the computational capabilities in the area of liquid metal fast breeder reactor (LMFBR) system-wide transient analysis in the United States, identifies various numerical and physical approximations, the degree of empiricism, range of applicability, model verification and experimental needs for a wide class of protected transients, in particular, natural circulation shutdown heat removal for both loop- and pool-type plants
computer program DYNAPCON for the transient analysis of a prestressed concrete reactor vessel (PCRV)...
Integrity of piping systems is one of the main concerns of the safety issues of Liquid Metal Fast Br...
The general objective of the study is to perform a diversion analysis and an assessment of the avail...
The title of this session is taken to imply the system-wide thermohydraulic simulation of liquid met...
This paper deals with the modeling and simulation of system-wide transients in LMFBRs. Unprotected e...
Experimental Breeder Reactor II (EBR-II) is a Liquid Metal Reactor(LMR) at Argonne National Laborato...
Core thermal-hydraulic design and performance analyses for Liquid Metal Fast Breeder Reactors (LMFBR...
In the summer of 1974, the Theoretical Division of the Los Alamos Scientific Laboratory began severa...
This paper describes the code capability related to the safety requirements in nuclear plants. The ...
The neutronics and thermodynamics of an LMFBR primary system have been simulated using the DSNP simu...
Much recent R and D has been devoted to the safety of liquid metal fast breeder reactors (LMFBR's). ...
Unprotected loss of flow (ULOF) analysis of metal (U-Pu-6% Zr) fuelled 500 MWe and 1000 MWe pool typ...
M2LFR-1000 is a medium-power modular lead-cooled fast reactor, developed by University of Science an...
Models for components and processes that are needed for simulation of thermohydraulic transient in a...
International audienceDesign and safety studies for Sodium cooled Fast Reactors (SFR) include therma...
computer program DYNAPCON for the transient analysis of a prestressed concrete reactor vessel (PCRV)...
Integrity of piping systems is one of the main concerns of the safety issues of Liquid Metal Fast Br...
The general objective of the study is to perform a diversion analysis and an assessment of the avail...
The title of this session is taken to imply the system-wide thermohydraulic simulation of liquid met...
This paper deals with the modeling and simulation of system-wide transients in LMFBRs. Unprotected e...
Experimental Breeder Reactor II (EBR-II) is a Liquid Metal Reactor(LMR) at Argonne National Laborato...
Core thermal-hydraulic design and performance analyses for Liquid Metal Fast Breeder Reactors (LMFBR...
In the summer of 1974, the Theoretical Division of the Los Alamos Scientific Laboratory began severa...
This paper describes the code capability related to the safety requirements in nuclear plants. The ...
The neutronics and thermodynamics of an LMFBR primary system have been simulated using the DSNP simu...
Much recent R and D has been devoted to the safety of liquid metal fast breeder reactors (LMFBR's). ...
Unprotected loss of flow (ULOF) analysis of metal (U-Pu-6% Zr) fuelled 500 MWe and 1000 MWe pool typ...
M2LFR-1000 is a medium-power modular lead-cooled fast reactor, developed by University of Science an...
Models for components and processes that are needed for simulation of thermohydraulic transient in a...
International audienceDesign and safety studies for Sodium cooled Fast Reactors (SFR) include therma...
computer program DYNAPCON for the transient analysis of a prestressed concrete reactor vessel (PCRV)...
Integrity of piping systems is one of the main concerns of the safety issues of Liquid Metal Fast Br...
The general objective of the study is to perform a diversion analysis and an assessment of the avail...