Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technology options for the first nuclear power plant program in Indonesia. The reactor is a High Temperature Gas-Cooled Reactor-type with spherical fuel elements called pebbles. To support this program, it is necessary to prepare dry cask to safely store the spent pebble fuels that will be generated by the RDNK. The dry cask design has been proposed based on the Castor THTR/AVR but modified with air gaps to facilitate decay heat removal. The objective of this study is to evaluate criticality safety through keff value of the proposed dry cask design for the RDNK spent fuel. The keff values were calculated using MCNP5 program for the dry cask with 2...
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent...
In this study, the analysis of a dry storage cask for accident-tolerant and high-burnup spent fuel w...
This design calculation updates the previous criticality evaluation for the fuel handling, transfer,...
Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technol...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malays...
Various spent fuel dry storage casks have been installed as an interim spent fuel storage with desig...
The shortage of nuclear spent fuel storage pool has been issued. The spent fuel storage and transpor...
Thesis (M.Sc. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2009.The developm...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
The purpose of this design calculation is to demonstrate that the handling operations of transportat...
A dry storage for RBMK spent fuel is under construction at the Ignalina site in Lithuania. Spent fue...
Approximately every 18 months, the fuel in a nuclear reactor is replaced, given that most of the fis...
This work addresses the neutronic performance and criticality safety issues of transport casks for f...
The paper presents results of nuclear criticality safety analysis of spent fuel storage for the 1st ...
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent...
In this study, the analysis of a dry storage cask for accident-tolerant and high-burnup spent fuel w...
This design calculation updates the previous criticality evaluation for the fuel handling, transfer,...
Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technol...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malays...
Various spent fuel dry storage casks have been installed as an interim spent fuel storage with desig...
The shortage of nuclear spent fuel storage pool has been issued. The spent fuel storage and transpor...
Thesis (M.Sc. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2009.The developm...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
The purpose of this design calculation is to demonstrate that the handling operations of transportat...
A dry storage for RBMK spent fuel is under construction at the Ignalina site in Lithuania. Spent fue...
Approximately every 18 months, the fuel in a nuclear reactor is replaced, given that most of the fis...
This work addresses the neutronic performance and criticality safety issues of transport casks for f...
The paper presents results of nuclear criticality safety analysis of spent fuel storage for the 1st ...
Monte Carlo criticality safety and sensitivity calculations of pressurized water reactor (PWR) spent...
In this study, the analysis of a dry storage cask for accident-tolerant and high-burnup spent fuel w...
This design calculation updates the previous criticality evaluation for the fuel handling, transfer,...