Results 31 to 40 of about 167,510,152 (115)
Simulation of loss-of-coolant accident with thin-walled cladding tubes
A loss-of-coolant accident in a nuclear power plant was simulated in the CODEX-SLIM experiment. The electrically heated fuel rod bundle contained cladding material used at a VVER-440 power plant.
Zoltán Kis +8 more
core +1 more source
Analysis of an AP600 intermediate-size loss-of-coolant accident [PDF]
, 1995 A postulated double-ended guillotine break of an AP600 direct-vessel-injection line has been analyzed. This event is characterized as an intermediate-break loss-of-coolant accident.
Boyack, B. E., Lime, J. F.
core
BWR pool dynamics in a loss of coolant accident. Calculation of the air-venting phase [PDF]
, 1978 The authors calculated the air-venting phase of a loss of coolant accident (LOCA) in a BWR pool using both compressible and incompressible finite difference schemes, and compared the results with experiments made at the University of California, Los ...
McMaster, W. H. +3 more
core +1 more source
, 2003 Fifth volume of the final report produced by the Columbia Accident Investigation Board including documents produced by NASA and other organizations that were provided to the Columbia Accident Investigation Board in support of its inquiry into the ...
Columbia Accident Investigation Board
core
Large break loss-of-coolant accident analyses for the high flux isotope reactor [PDF]
, 1989 The US Department of Energy's High Flux Isotope Reactor (HFIR) was analyzed to evaluate it's response to a spectrum of loss-of-coolant accidents (LOCAs) with potential for leading to core damage.
Taleyarkhan, R.P. (Oak Ridge National Lab., TN (USA))
core
Columbia Accident Investigation Board Report: Volume 6.Transcripts of Board Public Hearings
, 2003 Sixth volume of the final report produced by the Columbia Accident Investigation Board including transcripts of board public hearings held in Houston, Texas; Cape Canaveral, Florida; and Washington ...
Columbia Accident Investigation Board
core
Emergency Strategy Research of Loss of Coolant Accident for Small Modular Reactor
, 2017 This paper researched the behavior of 20mm break Loss of Coolant Accident (LOCA) which is located in the Direct Vessel Injection (DVI) line of the integrated small modular reactor (SMR) in case of full power with RELAP5-3KEYMASTER simulation system.
Wang Yuqi, Yu Aimin, Yang Qingming
core +1 more source
Columbia Accident Investigation Board Report: Volume 2. CAIB Technical Documents Cited in the Report
, 2003 Second volume of the final report produced by the Columbia Accident Investigation Board including appendices on reports produced by NASA and other organizations in support of the investigation into the February 1, 2003 destruction of the Space Shuttle ...
Columbia Accident Investigation Board
core
, 2003 Third volume of the final report produced by the Columbia Accident Investigation Board including assorted technical documents produced by NASA and other organizations in support of the Board's inquiry into the February 1, 2003 destruction of Space ...
Columbia Accident Investigation Board
core
, 2020 The spent fuel storage system is designed to store and cool the spent fuel within several years with account for scheduled refueling and emergency unloading of the entire reactor core.
Pirouzmand, A. +3 more
core +1 more source