Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been carried out utilizing coupled point kinetics, neutronics and thermal hydraulics code EUREKA-2/RR. From the previous calculations of neutronics parameters including percentage burnup of individual fuel elements performed so far for 700 MWD burnt core of TRIGA reactor showed that the fuel rod predicted as hottest at the beginning of cycle (fresh core) was found to remain as the hottest until 200 MWD of burn, but, with the progress of core burn, the hottest rod was found to be shifted and another rod in the core became the hottest. The present study intends to evaluate the thermal hydraulic parameters of these hottest fuel rods at different cycl...
ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE T...
The nuclear reactor has two types of power reactors based on the function that is used as electrical...
ABSTRACT Researches of steady-state thermal hydraulic performance of a large power PWR had been made...
Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been ...
This paper illustrates the effects on safety of TRIGA Mark-II research reactor of Bangladesh at its ...
The TRIGA-2000 research reactor in Bandung, Indonesia, has operated for over 50 years. Recently, the...
The conversion program of the 2 MW TRIGA reactor in Bandung consisted of the replacement of cylindri...
The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, refer...
Bandung TRIGA2000 Reactor, a General Atomic (GA)-made research reactor used for training, research a...
The investigation was conducted on the out-core neutron flux and burn-up at irradiated fuel stored i...
In order to prepare Malaysia to be nuclear ready, the Malaysian 1 MW TRIGA MARK II research reactor ...
Reactor TRIGA 2000 Bandung is result of upgrading TRIGA Mark II reactor from nominal power of 1 MW b...
NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 200...
The TRIGA2000 is one of the nuclear research reactors in Indonesia. TRIGA reactor fuel element is ro...
ABSTRACT In accordance with the discontinuation of TRIGA fuel element production by its producer, t...
ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE T...
The nuclear reactor has two types of power reactors based on the function that is used as electrical...
ABSTRACT Researches of steady-state thermal hydraulic performance of a large power PWR had been made...
Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been ...
This paper illustrates the effects on safety of TRIGA Mark-II research reactor of Bangladesh at its ...
The TRIGA-2000 research reactor in Bandung, Indonesia, has operated for over 50 years. Recently, the...
The conversion program of the 2 MW TRIGA reactor in Bandung consisted of the replacement of cylindri...
The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, refer...
Bandung TRIGA2000 Reactor, a General Atomic (GA)-made research reactor used for training, research a...
The investigation was conducted on the out-core neutron flux and burn-up at irradiated fuel stored i...
In order to prepare Malaysia to be nuclear ready, the Malaysian 1 MW TRIGA MARK II research reactor ...
Reactor TRIGA 2000 Bandung is result of upgrading TRIGA Mark II reactor from nominal power of 1 MW b...
NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 200...
The TRIGA2000 is one of the nuclear research reactors in Indonesia. TRIGA reactor fuel element is ro...
ABSTRACT In accordance with the discontinuation of TRIGA fuel element production by its producer, t...
ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE T...
The nuclear reactor has two types of power reactors based on the function that is used as electrical...
ABSTRACT Researches of steady-state thermal hydraulic performance of a large power PWR had been made...