Add to ORKGThe paper presents results of nuclear criticality safety analysis of spent fuel storage and handling for the 1st and 2nd unit of NPP Mochovce. Spent fuel storage pool (compact and reserve grid) and T-12 transport cask were modeled using the Monte Carlo code MCNP5. Conservative approach was applied and calculation of max eff k values was performed for normal and various postulated emergency conditions in order to evaluate the final maximal max eff k values. The requirement of current safety regulations to ensure 5% subcriticality was met except some especially conservative cases
A few years ago Westinghouse started the development of a new method for criticality calculations fo...
According to the fresh fuel management procedure, fuel assemblies – after nuclear fuel delivery to t...
Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malays...
The paper presents results of nuclear criticality safety analysis of spent fuel storage and handling...
The paper presents results of nuclear criticality safety analysis of spent fuel storage for the 1st ...
Criticality safety reanalyzes of the NPP Krško spent fuel pool has been performed. Limiting critical...
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent...
This paper presents the validation of the continuous-energy Monte Carlo neutron-transport code MCS w...
This paper presents the validation of the MCS code for critical safety analysis with burnup credit f...
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...
A criticality safety analysis was performed for the APR-1400 spent fuel pool region-II to ensure the...
[[abstract]]Using as a starting base the high-density spent-fuel storage racks to be put into the Ch...
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...
Many conservative assumptions for subcriticality assessment calculations have to be made in current ...
A few years ago Westinghouse started the development of a new method for criticality calculations fo...
According to the fresh fuel management procedure, fuel assemblies – after nuclear fuel delivery to t...
Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malays...
The paper presents results of nuclear criticality safety analysis of spent fuel storage and handling...
The paper presents results of nuclear criticality safety analysis of spent fuel storage for the 1st ...
Criticality safety reanalyzes of the NPP Krško spent fuel pool has been performed. Limiting critical...
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent...
This paper presents the validation of the continuous-energy Monte Carlo neutron-transport code MCS w...
This paper presents the validation of the MCS code for critical safety analysis with burnup credit f...
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...
A criticality safety analysis was performed for the APR-1400 spent fuel pool region-II to ensure the...
[[abstract]]Using as a starting base the high-density spent-fuel storage racks to be put into the Ch...
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...
Many conservative assumptions for subcriticality assessment calculations have to be made in current ...
A few years ago Westinghouse started the development of a new method for criticality calculations fo...
According to the fresh fuel management procedure, fuel assemblies – after nuclear fuel delivery to t...
Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malays...