Two MCNP models (detailed and approximated) of University of Maryland Training Reactor were created. The detailed model attempted to simulate the reactor according to engineering specifications while the simplified model eliminated all structural materials above and below the core. Neutron flux spectrum calculations for both models within the core showed that the results obtained from both models agreed within less than 0.5%. It was concluded that reactors equipped with standard TRIGA fuels enriched to 20 percent in uranium-235 can be modeled with all structures above and below the core eliminated entirely from the model without increasing the error due to geometry modeling simplifications of the core. In TRIGA reactors supplied with standa...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
The scope of this contribution is to present the MCNP simulation of the TRIGA Mark II benchmark expe...
The investigation was conducted on the out-core neutron flux and burn-up at irradiated fuel stored i...
The one megawatt TRIGA reactor at Texas A&M has various methods of irradiating samples, but one of t...
The TRIGA Mark F reactor at the Armed Forces Radiobiology Research Institute in Bethesda Maryland is...
A project was initiated at the Jožef Stefan Institute to develop methodology for the validation of t...
The neutron flux distribution in the TRIGA Mark II reactor core installed at the Applied Nuclear Ene...
The neutron flux is a crucial parameter for the analysis of nuclear reactors, because it affects the...
The TRIGA Mark II research reactor has a flux spectrum with a predominance of thermal neutrons. Whil...
The Fluoride High-Temperature Reactor (FHR) and the Very High-Temperature Reactor (VHTR) are advance...
Graduation date: 2007Attila is a state-of-the-art radiation transport based code that is efficient, ...
International audienceAt the Reactor Physics Department of the Jozef Stefan Institute (JSI) a detail...
The Malaysian 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency is designed to effecti...
The TRIGA Mark II nuclear reactor operated by the Laboratory of Applied Nuclear Energy (LENA) of the...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
The scope of this contribution is to present the MCNP simulation of the TRIGA Mark II benchmark expe...
The investigation was conducted on the out-core neutron flux and burn-up at irradiated fuel stored i...
The one megawatt TRIGA reactor at Texas A&M has various methods of irradiating samples, but one of t...
The TRIGA Mark F reactor at the Armed Forces Radiobiology Research Institute in Bethesda Maryland is...
A project was initiated at the Jožef Stefan Institute to develop methodology for the validation of t...
The neutron flux distribution in the TRIGA Mark II reactor core installed at the Applied Nuclear Ene...
The neutron flux is a crucial parameter for the analysis of nuclear reactors, because it affects the...
The TRIGA Mark II research reactor has a flux spectrum with a predominance of thermal neutrons. Whil...
The Fluoride High-Temperature Reactor (FHR) and the Very High-Temperature Reactor (VHTR) are advance...
Graduation date: 2007Attila is a state-of-the-art radiation transport based code that is efficient, ...
International audienceAt the Reactor Physics Department of the Jozef Stefan Institute (JSI) a detail...
The Malaysian 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency is designed to effecti...
The TRIGA Mark II nuclear reactor operated by the Laboratory of Applied Nuclear Energy (LENA) of the...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
The scope of this contribution is to present the MCNP simulation of the TRIGA Mark II benchmark expe...
The investigation was conducted on the out-core neutron flux and burn-up at irradiated fuel stored i...