The reactor core containment vessel temperatures after impact, and the design variables that affect the post impact survival of the system are analyzed. The heat transfer analysis includes conduction, radiation, and convection in addition to the core material heats of fusion and vaporization under partially burial conditions. Also, included is the fact that fission products vaporize and transport radially outward and condense outward and condense on cooler surfaces, resulting in a moving heat source. A computer program entitled Executive Subroutines for Afterheat Temperature Analysis (ESATA) was written to consider this complex heat transfer analysis. Seven cases were calculated of a reactor power system capable of delivering up to 300 MW o...
After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and und...
This paper deals with the design and the thermal analyses of an original core catcher, located insid...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
A computer program was developed to analyze the transient afterheat temperature and pressure respons...
Fukushima Daiichi NPP accident showed that plant technical support center (TSC) in an extreme and ra...
A study to determine the feasibility of containing the fission products of a mobile reactor in the e...
Impact tests of two 2-foot diameter containment models for mobile nuclear reactor
A general review is given of containment technology for water-coolednuclear reactors, including disc...
An impact test was conducted on an 1142 pound 2 foot diameter sphere model. The purpose of this test...
The first five reports in this series were submitted to the US AEC with the application (dated July ...
A two-dimensional, transient, heat-transfer analysis was made to determine the temperature response ...
Analysis of the processes in severe accidents at nuclear power plants has allowed distinguishing fou...
This dissertation covers the application of heat accumulation systems in nuclear power engineering, ...
[[abstract]]A series of MAAP3.0 calculations was made with varying parameters to simulate a postulat...
Aim of this work is to investigate transient heat transfer phenomena of interest for the thermal-hyd...
After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and und...
This paper deals with the design and the thermal analyses of an original core catcher, located insid...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
A computer program was developed to analyze the transient afterheat temperature and pressure respons...
Fukushima Daiichi NPP accident showed that plant technical support center (TSC) in an extreme and ra...
A study to determine the feasibility of containing the fission products of a mobile reactor in the e...
Impact tests of two 2-foot diameter containment models for mobile nuclear reactor
A general review is given of containment technology for water-coolednuclear reactors, including disc...
An impact test was conducted on an 1142 pound 2 foot diameter sphere model. The purpose of this test...
The first five reports in this series were submitted to the US AEC with the application (dated July ...
A two-dimensional, transient, heat-transfer analysis was made to determine the temperature response ...
Analysis of the processes in severe accidents at nuclear power plants has allowed distinguishing fou...
This dissertation covers the application of heat accumulation systems in nuclear power engineering, ...
[[abstract]]A series of MAAP3.0 calculations was made with varying parameters to simulate a postulat...
Aim of this work is to investigate transient heat transfer phenomena of interest for the thermal-hyd...
After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and und...
This paper deals with the design and the thermal analyses of an original core catcher, located insid...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...