Under a postulated scenario of Loss of Coolant Accident (LOCA) with un-availability of emergency core cooling system (ECCS) for Indian Pressurized Heavy Water Reactor (IPHWR), the channel integrity needs to be assured. An experimental facility is presently being developed at Indian Institute of Technology Roorkee (IIT R) India to study such a severe event. In this study a CFD simulation of fuel bundle weight simulator is being carried out using ANSYS 19.0 in transient thermal analysis using ANSYS Parametric Design Language (APDL) solver. The test facility aims to estimate the thermal aspect of weight bundle simulator which is the source of heat generation for pressure tube. Thermo-mechanical deformation of pressure tube will depend on the h...
PKL is the only test facility in Europe that replicates the entire primary side and the most importa...
International audienceThis study focuses on the coolability of a partially deformed fuel assembly of...
Thesis (M.Ing. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2004.The Pebb...
Thermal behavior of fuel channel under loss of coolant accident (LOCA) is a major concern for nuclea...
The pressure tubes (PT) in the Indian Pressurized Heavy Water Reactor (PHWR) are kept concentrically...
International audienceUnder limited core damage accidents (LCDAs) of Pressurized Heavy Water Reactor...
In a nuclear reactor Loss of Coolant accident (LOCA) considers wide range of postulated damage or ru...
ABSTRACT Researches of steady-state thermal hydraulic performance of a large power PWR had been made...
The scope of the presented thesis work aimed at investigating the thermal-hydraulic phenomena that t...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
The focus of the present research activity was the experimental and numerical investigation of some ...
The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressuriz...
In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the n...
The simulation of design basis accidents in a containment building is usually conducted with a lumpe...
After the FUKUSHIMA accident, passive systems become an important issue for the new projects of Pres...
PKL is the only test facility in Europe that replicates the entire primary side and the most importa...
International audienceThis study focuses on the coolability of a partially deformed fuel assembly of...
Thesis (M.Ing. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2004.The Pebb...
Thermal behavior of fuel channel under loss of coolant accident (LOCA) is a major concern for nuclea...
The pressure tubes (PT) in the Indian Pressurized Heavy Water Reactor (PHWR) are kept concentrically...
International audienceUnder limited core damage accidents (LCDAs) of Pressurized Heavy Water Reactor...
In a nuclear reactor Loss of Coolant accident (LOCA) considers wide range of postulated damage or ru...
ABSTRACT Researches of steady-state thermal hydraulic performance of a large power PWR had been made...
The scope of the presented thesis work aimed at investigating the thermal-hydraulic phenomena that t...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
The focus of the present research activity was the experimental and numerical investigation of some ...
The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressuriz...
In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the n...
The simulation of design basis accidents in a containment building is usually conducted with a lumpe...
After the FUKUSHIMA accident, passive systems become an important issue for the new projects of Pres...
PKL is the only test facility in Europe that replicates the entire primary side and the most importa...
International audienceThis study focuses on the coolability of a partially deformed fuel assembly of...
Thesis (M.Ing. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2004.The Pebb...