An RIA (reactivity initiated accident) analysis has been carried out for the TRIGA Mark II research reactor considering both step and ramp reactivity ranges within 0.5 % dk/k (< $1) to 2.0 % dk/k (>$2). The insertion time was set at 10 s. Based on the fact that a reactor becomes unprotected if scram does not work at the event of danger, to define unprotected conditions, the time to actuate scram (trip) was taken as close to total simulation time. In this long duration of scram inactivity, it is obtained from the present analysis that the reactor remained safe to up to 1.8 % dk/k ($2.57) for step reactivity and 1.99 % dk/k ($2.84) for ramp reactivity. In addition to negative temperature coefficient of reativity, probably the longer tim...
Control and safety of nuclear reactors are significantly influenced by the determination of safety p...
The Reactivity Initiated Accident Scoping Test (RIA-ST) was successfully completed August 30, 1978. ...
Due to the very stringent safety requirements of nuclear facilities, there is a need of developing p...
An RIA (reactivity initiated accident) analysis has been carried out for the TRIGA Mark II research ...
This paper illustrates the effects on safety of TRIGA Mark-II research reactor of Bangladesh at its ...
ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE T...
The main purpose of reactor safety is not to permit any release of radioactivity from the reactor co...
Hypothetical transients and accidents are used in the design and safety analysis of light-water reac...
Bandung TRIGA2000 Reactor, a General Atomic (GA)-made research reactor used for training, research a...
Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been ...
Analysis of the control rod insertion is important as it is closely related to reactor safety. Previ...
In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up i...
The RELAP5/MOD3.3 code has been applied for thermal hydraulic analysis of power reactors as well as ...
During operation of nuclear power reactors reactivity initiated accidents (RIA) can occur, such as a...
ABSTRACT -Reactivity Initiated Accident (RIA) leads to an unwanted increase in fission rate and powe...
Control and safety of nuclear reactors are significantly influenced by the determination of safety p...
The Reactivity Initiated Accident Scoping Test (RIA-ST) was successfully completed August 30, 1978. ...
Due to the very stringent safety requirements of nuclear facilities, there is a need of developing p...
An RIA (reactivity initiated accident) analysis has been carried out for the TRIGA Mark II research ...
This paper illustrates the effects on safety of TRIGA Mark-II research reactor of Bangladesh at its ...
ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE T...
The main purpose of reactor safety is not to permit any release of radioactivity from the reactor co...
Hypothetical transients and accidents are used in the design and safety analysis of light-water reac...
Bandung TRIGA2000 Reactor, a General Atomic (GA)-made research reactor used for training, research a...
Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been ...
Analysis of the control rod insertion is important as it is closely related to reactor safety. Previ...
In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up i...
The RELAP5/MOD3.3 code has been applied for thermal hydraulic analysis of power reactors as well as ...
During operation of nuclear power reactors reactivity initiated accidents (RIA) can occur, such as a...
ABSTRACT -Reactivity Initiated Accident (RIA) leads to an unwanted increase in fission rate and powe...
Control and safety of nuclear reactors are significantly influenced by the determination of safety p...
The Reactivity Initiated Accident Scoping Test (RIA-ST) was successfully completed August 30, 1978. ...
Due to the very stringent safety requirements of nuclear facilities, there is a need of developing p...