Multiphysics Investigation on Coolant Thermohydraulic Conditions and Fuel Rod Behavior During a Loss-of-Coolant Accident [PDF]
This article simulates the multiphysics coolant thermohydraulic conditions and fuel performance of a pressurized water reactor (PWR) during a loss-of-coolant accident (LOCA).
Meng Yu +3 more
doaj +2 more sources
BWR Loss-of-Coolant Accident Tests at ROSA-III with High Temperature Emergency Core Coolant Injection [PDF]
The effects of emergency core coolant (ECC) temperature on the performance of the emergency core cooling system (ECCS) during a loss-of-coolant accident (LOCA) of a boiling water reactor (BWR) were investigated experimentally using the Rig of Safety Assessment (ROSA)-III integral test facility.
Yutaka Kukita, Kanji Tasaka
exaly +4 more sources
VALIDATION OF COOLANT THERMAL RESPONSE IN A TRANSIENT FINITE DIFFERENCE THERMAL TRANSPORT MODEL WITH APPLICATIONS TO FAST SPECTRUM REACTORS [PDF]
Transient behavior in nuclear reactors is important in accidents and with reactivity control systems that are driven by thermal feedback. Here, we describe a transient finite difference model for a pin cell system.
Holdampf Sydney A. +2 more
doaj +1 more source
The analysis of the known results of RELAP5/V.3.2 simulation for loss of coolant & blackout accidents at WWER nuclear power plants showed that the design accident management strategies with design passive safety systems do not provide the necessary ...
Володимир Іванович Скалозубов +5 more
doaj +5 more sources
Modernized loss-of-coolant & blackout accident management strategy at nuclear power plants with wwer
The analysis of the known results of RELAP5/V.3.2 simulation for loss of coolant & blackout accidents at WWER nuclear power plants showed that the design accident management strategies with design passive safety systems do not provide the necessary ...
Володимир Іванович Скалозубов +5 more
doaj +5 more sources
Safety Researches on LWR Loss-of-Coolant Accident [PDF]
On the LWR LOCA safety, many experimental and analytical works were performed in the governmental organization and the nuclear industries. The works covers not only LOCA ECCS studies but also studies on containment spray, hydrogen diffusion in the containment, pressure suppression and pipe behavior.
SATO, Kazuo +2 more
openaire +1 more source
Rotor Cascade Assessment at Off-Design Condition: An Aerodynamic Investigation on Platform Cooling
Off-design condition of a rotor blade cascade with and without platform cooling was experimentally investigated. The ability of the gas turbine to operate down to 50% to 20% of its nominal intake air flow rate has an important consequence in the change ...
Hamed Abdeh +2 more
doaj +1 more source
Analysis of Loss-of-Coolant Accidents in the NBSR [PDF]
This report documents calculations of the fuel cladding temperature during loss-of-coolant accidents in the NBSR. The probability of a pipe failure is small and procedures exist to minimize the loss of water and assure emergency cooling water flows into the reactor core during such an event.
L. Cheng, D. Diamond
openaire +1 more source
Analysis of mass transfer processes in a reactor during a loss-of-coolant accident [PDF]
The purpose of the work was to optimize the parameters of the spillage system equipped with a gas pressure hydroaccumulator for a ship pressurized water reactor in a loss-of-coolant accident.
Aleksey Kulikov +2 more
doaj +3 more sources
The sensitivity analysis for APR1400 nodalization under Large Break LOCA condition based on mars code [PDF]
The phenomena of loss of coolant accident have been investigated for long time and the result of experiment shows that the flow condition in the downcomer during the end-of-blowdown were highly multi-dimensional at full-scale.
Jang Hyung-Wook +3 more
doaj +1 more source

