This report summarizes NSAC study of reactor core thermal conditions during the accident at Three Mile Island, Unit 2. The study focuses primarily on the time period from core uncovery (approximately 113 minutes after turbine trip) through the initiation of sustained high pressure injection (after 202 minutes). The transient analysis is based upon established sequences of events; plant data; post-accident measurements; interpretation or indirect use of instrument responses to accident conditions
Oct. 1979.Cover title: Staff reports to the President's Commission on the Accident at Three Mile Isl...
Core bore samples were obtained from the severely damaged TMI-2 core during July and August, 1986. A...
Graduation date: 1984The 1979 incident at Three Mile Island drew attention to weaknesses in the capa...
This report discusses preliminary studies of the Three Mile Island Unit 2 (TMI-2) accident based on ...
An overview is presented of the current activities within the international consortium participating...
SCDAP/RELAP5/MOD3.1, an integrated thermal hydraulic analysis code developed primarily to simulate s...
A best-estimate postaccident analysis of the TMI-2 reactor system was made with the TRAC code. Based...
This report summarizes the investigations on instrumentation and electrical systems that were subjec...
Viewgraphs are presented that describe the Three Mile Island-2 reactor; the severe accident in the r...
The Three Mile Island nuclear plant (Unit 2) was modeled using the Transient Reactor Analysis Code (...
Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis a...
About 10 hours after the March 28, 1979 loss-of-coolant accident began at Three Mile Island Unit 2 (...
A discussion is presented of the operator/instrumentation interactions which had an effect on the co...
The Three Mile Island Unit 2 accident of March 28, 1979 presents unique research opportunities that ...
A description of the accident at Three Mile Island-2 reactor is presented. Activities related to the...
Oct. 1979.Cover title: Staff reports to the President's Commission on the Accident at Three Mile Isl...
Core bore samples were obtained from the severely damaged TMI-2 core during July and August, 1986. A...
Graduation date: 1984The 1979 incident at Three Mile Island drew attention to weaknesses in the capa...
This report discusses preliminary studies of the Three Mile Island Unit 2 (TMI-2) accident based on ...
An overview is presented of the current activities within the international consortium participating...
SCDAP/RELAP5/MOD3.1, an integrated thermal hydraulic analysis code developed primarily to simulate s...
A best-estimate postaccident analysis of the TMI-2 reactor system was made with the TRAC code. Based...
This report summarizes the investigations on instrumentation and electrical systems that were subjec...
Viewgraphs are presented that describe the Three Mile Island-2 reactor; the severe accident in the r...
The Three Mile Island nuclear plant (Unit 2) was modeled using the Transient Reactor Analysis Code (...
Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis a...
About 10 hours after the March 28, 1979 loss-of-coolant accident began at Three Mile Island Unit 2 (...
A discussion is presented of the operator/instrumentation interactions which had an effect on the co...
The Three Mile Island Unit 2 accident of March 28, 1979 presents unique research opportunities that ...
A description of the accident at Three Mile Island-2 reactor is presented. Activities related to the...
Oct. 1979.Cover title: Staff reports to the President's Commission on the Accident at Three Mile Isl...
Core bore samples were obtained from the severely damaged TMI-2 core during July and August, 1986. A...
Graduation date: 1984The 1979 incident at Three Mile Island drew attention to weaknesses in the capa...