Results 31 to 40 of about 178,999 (304)

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

Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants

open access: yesScience and Technology of Nuclear Installations, 2021
In the planning and management of the interim storage of spent nuclear fuel, the technical and economic parameters that are involved have a significant role in increasing the efficiency of the storage system.
Shadwan M. M. Esmail, Jae Hak Cheong
doaj   +1 more source

Impact of PSI-KIT Nitriding model on hypothetical Spent Fuel Pool accident simulation

open access: yesNuclear Engineering and Technology, 2023
In past years the Paul Scherrer Institute (PSI, Switzerland) and the Karlsruhe Institue of Technology (KIT, Germany)) collaborated to develop a model to account for the active role of nitrogen in the air oxidation of a Zircalloy cladding.
Mateusz Malicki, Terttaliisa Lind
doaj   +1 more source

ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION

open access: yesJournal of Energy : Energija, 2022
The Spent Fuel Pool (SFP) in a nuclear power plant is a robust structure designed to withstand large seismic loads. After the terrorist attacks on September 11 and the accident in the Fukushima nuclear power plant, special attention was focused on safety assessments and taking measures to mitigate possible accidents related to the spent fuel pool. This
ĐAKOVIĆ, JOSIP, GRGIĆ, DAVOR
openaire   +4 more sources

Experimental Study on Flow Characteristics of Coolant Film of Single Spent Fuel Rod in PWR

open access: yesYuanzineng kexue jishu, 2022
After the Fukushima nuclear accident, the safety of spent fuel pool has attracted much attention. Under extreme accident conditions, the spent fuel pool may lose make-up water and cooling for a long time, causing the water level in the spent fuel pool ...
CAO Qiong;JIANG Heyuan;DING Xiao;LU Daogang;LI Zhen;WANG Xiaotian
doaj  

Experimental validation of the seismic analysis methodology for free-standing spent fuel racks

open access: yesNuclear Engineering and Technology, 2019
Spent fuel racks are steel structures used in the storage of the spent fuel removed from the nuclear power reactor. Rack units are submerged in the depths of the spent fuel pool to keep the fuel cool.
Alberto González Merino   +2 more
doaj   +1 more source

Evidence for anthropogenic 14C-enrichment in estuarine waters adjacent to the North Sea [PDF]

open access: yes, 2006
[1] The isotopic composition (d13C and D14C) of high molecular weight dissolved organic carbon (HMW DOC) was studied in the Tyne and Tweed estuaries, NE England.
Ahad, J.M.E.   +5 more
core   +1 more source

Lessons Learned in Protection of the Public for the Accident at the Fukushima Daiichi Nuclear Power Plant [PDF]

open access: yes, 2017
What insights can the accident at the Fukushima Daiichi nuclear power plant provide in the reality of decision making on actions to protect the public during a severe reactor and spent fuel pool emergency?
Callen, J., Homma, T.
core   +1 more source

Study of corrosion of aluminum alloys of nuclear purity in ordinary water: Part two [PDF]

open access: yesNuclear Technology and Radiation Protection, 2005
Since 2002, the effects of corrosion on aluminum alloys of nuclear purity in ordinary water of the spent fuel storage pool of the RA re search reactor at VINČA Institute of Nuclear Sciences have been examined in the frame work of the International Atomic
Pešić Milan P.   +4 more
doaj   +1 more source

A STUDY FOR DOSE DISTRIBUTION IN SPENT FUEL STORAGE POOL INDUCED BY NEUTRON AND GAMMA���RAY EMITTED IN SPENT FUELS [PDF]

open access: yes, 2011
With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU, average power 34 MW/MTU for three periods burned time for 539.2 days per period and cooling time for 100 hours after shut down, to set up the condition ...
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core  

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