Results 21 to 30 of about 9,551,406 (202)
, 2021 Repository containing the Serpent 2 input files and output data for a 3D CANDU-6 quarter core.The "Input Files" folder contains:- The Portable Batch System file - The refueling and error checking python script- The Serpent 2 CANDU-6 model files.
Burkhardt, A (via Mendeley Data)
core +1 more source
Recent Progress in Functional Nanomaterials towards the Storage, Separation, and Removal of Tritium
Advanced Materials, Volume 35, Issue 48, November 28, 2023., 2023 Tritium is a prime fuel to generate fusion power, but its storage and separation in pure form are major challenges in nuclear industries. This review discusses recent progress and main research trends in hydrogen isotope storage and separation while emphasizing tritium using metal hydrides, nanoporous zeolites, and metal organic frameworks (MOFs) and 2‐
Muruganantham Rethinasabapathy +5 more
wiley +1 more source
A methodology to designate radiation‐controlled areas in decommissioning nuclear power plants
Energy Science &Engineering, Volume 11, Issue 9, Page 3204-3214, September 2023., 2023 Five steps for designating decommissioning radiation‐controlled areas in decommissioning nuclear power plants. Abstract Kori Unit 1, which was permanently shut down in 2017, is expected to be the first decommissioned commercial nuclear power plant (NPP) in Korea.
Seongjun Kim +9 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023 In CANDU reactors, shim operation is used when the online refuelling capability becomes temporarily unavailable. Adjuster rods, normally in‐core to provide flux flattening, are withdrawn in sequence to provide additional reactivity as the fuel is depleted.
Simon Younan +2 more
wiley +1 more source
Conceptual Design of a Novel Megawatt Molten Salt Reactor Cooled by He‐Xe Gas
International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023 He‐Xe gas‐cooled micro‐molten salt reactor (HX‐micro‐MSR) is a novel reactor concept that integrates the technologies of molten salt reactor and closed Brayton cycle (CBC), which has a more compact structure compared with the other types of micro‐MSRs.
Hongkai Zhao +6 more
wiley +1 more source
Comparative analysis of occupational radiation doses when decommissioning nuclear power plants
Energy Science &Engineering, Volume 10, Issue 12, Page 4358-4365, December 2022., 2022 Radiation doses from precedent decommissioning nuclear power plants worldwide are compared with radiation doses estimated from Kori 1, the first decommissioning‐planned reactor in Korea, to determine dose reduction measures that can achieve radiation exposure that is as low as reasonably achievable to decommissioning workers. Abstract Kori 1, the first
Eun Ji Lee +9 more
wiley +1 more source
Uranium Recovery from Phosphates for Self‐Sufficient Nuclear Power in the Eastern Mediterranean
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 Production of phosphate fertilizers (PF), without uranium recovery, amounts to dispersing uranium compounds on agricultural fields. These compounds are naturally hidden in phosphate rock deposits prior to processing. Such a dispersion is a cumulative environmental damage, that may become rather catastrophic in few hundred years, under the current rates
Nassar H. S. Haidar, Guglielmo Lomonaco
wiley +1 more source
Effect of multiple-failure events on accident management strategy for CANDU-6 reactors
Nuclear Engineering and Technology, 2021 Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failures should be considered more seriously rather than single failure in the licensing bases and safety cases because attempts to take accident management ...
Seon Oh YU, Manwoong KIM
doaj +1 more source
Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis
Nuclear Engineering and Technology, 2017 This study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6 and Advanced Canada Deuterium Uranium Reactor-700 (ACR-700) fuel lattices using a Monte Carlo code.
Jinsu Park +4 more
doaj +1 more source
Numerical assessment of LOCA experiments of RD-14M using MARS-KS code
International Journal of Advanced Nuclear Reactor Design and Technology, 2020 The code assessment on the design basis events has been of fundamental importance to the safety analyses of the nuclear power plants. When a system analysis code is released to the new version by improving the existing models and correcting the found ...
Seon Oh Yu, Min Ki Cho, Kyung Lok Baek
doaj +1 more source