Results 1 to 10 of about 2,026 (295)

Monitoring and Leak testig of wwer-440 fuel assemblies in Slovak wet interim spent fuel storage facility [PDF]

open access: yesActa Montanistica Slovaca, 2007
An accelerated monitoring system designed for the Slovak wet interim spent fuel storage facility in NPP Jaslovské Bohunice bases on the newly designed “cesium detectors” is presented in the paper.
Miroslav Božik   +3 more
doaj   +2 more sources

Drop analysis of spent fuel assembly with screw prestress

open access: yesJournal of Physics: Conference Series
Abstract In this paper, the PWR spent fuel assembly is taken as the research object, and the finite element technology is used to carry out the structural integrity safety assessment of the spent fuel assembly under hoisting drop conditions.
Jing He, Feng Hou, Hehui Wang
openaire   +1 more source

Radiation shielding analysis and criticality safety calculation for spent fuel transportation cask [PDF]

open access: yesEPJ Web of Conferences
China anticipates a shortage in storage capacity for spent fuels at reactor sites for the AP1000 NPPs within the next 10 to 20 years. We proposed a conceptual design for a transportation cask capable of loading 21 spent fuel assemblies in AP1000 reactors
Chen Xiaosong   +3 more
doaj   +1 more source

Probabilistic safety assessment of Koeberg spent fuel pool

open access: yesActa Polytechnica CTU Proceedings, 2022
The effective management of spent fuel pool (SFP) safety has been raised as one of the emerging issues to further enhance nuclear installation safety after the Fukushima accident on March 11, 2011. SFP safety-related issues have been mainly focused on (a)
Sibongiseni Thabethe
doaj   +1 more source

A new shielding analysis method for used fuel transport and storage casks

open access: yesEPJ Web of Conferences, 2017
To provide a cask with the largest possible loading capacity of spent fuel assemblies with the largest practicable burnup and shortest cooling time within all safety requirements, AREVA TN has adapted its design process and developed a more elaborated ...
Léger Vincent, Kitsos Stavros
doaj   +1 more source

Criticality safety analysis of spent fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 fuels

open access: yesBrazilian Journal of Radiation Sciences, 2019
A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel ...
Claubia Pereira   +4 more
doaj   +1 more source

Design and characterization of a Muon tomography system for spent nuclear fuel monitoring

open access: yesNuclear Engineering and Technology, 2022
In recent years, monitoring of spent nuclear fuel inside dry cask storage has become an important area of national security. Muon tomography is a useful method for monitoring spent nuclear fuel because it uses high energy muons that penetrate deep into ...
Chanwoo Park   +5 more
doaj   +1 more source

A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

open access: yesScience and Technology of Nuclear Installations, 2019
The management of spent nuclear fuel assemblies of nuclear reactors is a priority subject among member states of the International Atomic Energy Agency.
Ian B. Gomes   +2 more
doaj   +1 more source

Natural Convection Heat Transfer of the Horizontal Rod-Bundle in a Semi-closed Rectangular Cavity

open access: yesFrontiers in Energy Research, 2020
During the refueling of PWR, the spent fuel assemblies are transferred from the reactor building to the fuel building through an underwater tube. The heat transfer characteristics of the spent fuel assembly in the top-corner area of the carrier with poor
Xi-dao Mao, Xi-dao Mao, Hong Xia
doaj   +1 more source

Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants

open access: yesNuclear Engineering and Technology, 2018
A criticality safety analysis was performed for the APR-1400 spent fuel pool region-II to ensure the safe storage of spent fuel, with credit taken for depletion and in-rack neutron absorbers (Metamic panels).
Abdulrahman S. Al Awad   +2 more
doaj   +1 more source

Home - About - Disclaimer - Privacy