Add to ORKGThe paper presents results of nuclear criticality safety analysis of spent fuel storage for the 1st and 2nd unit of NPP Mochovce. The spent fuel storage pool (compact and reserve grid) was modeled using the Monte Carlo code MCNP5. Conservative approach was applied and calculation of keff values was performed for normal and various postulated emergency conditions in order to evaluate the final maximal keff values. The requirement of current safety regulations to ensure 5 % subcriticality was met except one especially conservative case
The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's...
Thesis (M.Sc. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2009.The developm...
Criticality safety reanalyzes of the NPP Krško spent fuel pool has been performed. Limiting critical...
The paper presents results of nuclear criticality safety analysis of spent fuel storage and handling...
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malays...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
This thesis considers criticality safety in the production and storage stages of the light water rea...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
[[abstract]]Using as a starting base the high-density spent-fuel storage racks to be put into the Ch...
This paper presents the validation of the continuous-energy Monte Carlo neutron-transport code MCS w...
A few years ago Westinghouse started the development of a new method for criticality calculations fo...
Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technol...
An assessment has been performed of the criticality potential associated with the disposal of spent ...
The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's...
Thesis (M.Sc. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2009.The developm...
Criticality safety reanalyzes of the NPP Krško spent fuel pool has been performed. Limiting critical...
The paper presents results of nuclear criticality safety analysis of spent fuel storage and handling...
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malays...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
This thesis considers criticality safety in the production and storage stages of the light water rea...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
[[abstract]]Using as a starting base the high-density spent-fuel storage racks to be put into the Ch...
This paper presents the validation of the continuous-energy Monte Carlo neutron-transport code MCS w...
A few years ago Westinghouse started the development of a new method for criticality calculations fo...
Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technol...
An assessment has been performed of the criticality potential associated with the disposal of spent ...
The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's...
Thesis (M.Sc. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2009.The developm...
Criticality safety reanalyzes of the NPP Krško spent fuel pool has been performed. Limiting critical...