Results 51 to 60 of about 261 (180)

Systems analysis of the CANDU 3 Reactor [PDF]

open access: yes, 1993
This report presents the results of a systems failure analysis study of the CANDU 3 reactor design; the study was performed for the US Nuclear Regulatory Commission. As part of the study a review of the CANDU 3 design documentation was performed, a plant assessment methodology was developed, representative plant initiating events were identified for ...
Wolfgong, J. R.   +4 more
openaire   +2 more sources

Nuclear Decommissioning and Sustainable Environment: Insights on Decontamination Processes

open access: yesAdvanced Energy and Sustainability Research, Volume 6, Issue 1, January 2025.
The sequence of nuclear decommissioning and its role in promoting a sustainable environment are elucidated. Insights on strategy of nuclear decontamination technologies are highlighted, and techniques for radioactive waste treatment are discussed.
Miguta Faustine Ngulimi   +4 more
wiley   +1 more source

Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors

open access: yesEPJ Nuclear Sciences & Technologies, 2016
This paper discusses concepts for three-component fuel bundles containing plutonium, uranium and thorium for use in pressurised heavy water reactors, and cases for and against implementation of such a nuclear energy system in the United Kingdom.
Peel Ross   +3 more
doaj   +1 more source

Investigation of CANDU reactors as a thorium burner

open access: yesEnergy Conversion and Management, 2006
Abstract Large quantities of plutonium have been accumulated in the nuclear waste of civilian LWRs and CANDU reactors. Reactor grade plutonium can be used as a booster fissile fuel material in the form of mixed ThO2/PuO2 fuel in a CANDU fuel bundle in order to assure reactor criticality.
Şahín, Sümer   +3 more
openaire   +2 more sources

Development and Verification of Activated Source Term Library Based on ENDF/B‐VIII.0

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
Developed by the Oak Ridge National Laboratory (ORNL) in the United States, the ORIGEN code for computing irradiation and decay processes is one of the most widely used point depletion programs. However, the nuclear data that accompanies it, crucial for its application, has been measured and evaluated a long time ago.
Xirui Zhang   +6 more
wiley   +1 more source

Recycling option search for a 600-MWe sodium-cooled transmutation fast reactor

open access: yesNuclear Engineering and Technology, 2015
Four recycling scenarios involving pyroprocessing of spent fuel (SF) have been investigated for a 600-MWe transmutation sodium-cooled fast reactor (SFR), KALIMER.
Yong Kyo Lee, Myung Hyun Kim
doaj   +1 more source

Analysis of carbon‐14 discharges from Korean nuclear power plants

open access: yesEnergy Science &Engineering, Volume 12, Issue 9, Page 3576-3588, September 2024.
Comparison of radioactive effluent discharges from Korean nuclear power plants before and after carbon‐14 discharge monitoring in Korean pressurized water reactors. Abstract The routine practice accompanying the operation of nuclear facilities involves the discharge of radioactive effluents from nuclear power plants (NPPs). Regulation of this discharge
Hwapyoung Kim   +6 more
wiley   +1 more source

Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics

open access: yesScience and Technology of Nuclear Installations, 2018
The Canadian Supercritical Water-cooled Reactor (SCWR), a GEN IV reactor design, is a hybrid design of the well-established CANDU™ and Boiling Water Reactor with water above its thermodynamic critical point.
Frederic Salaun, David R. Novog
doaj   +1 more source

A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters

open access: yesNuclear Engineering and Technology, 2016
Important safety parameters such as the fuel temperature coefficient (FTC) and the power coefficient of reactivity (PCR) of the CANada Deuterium Uranium (CANDU-6) reactor have been evaluated using the Monte Carlo method.
Yonghee Kim, Donny Hartanto, Woosong Kim
doaj   +1 more source

Critical heat flux in a CANDU end shield – Influence of shielding ball diameter

open access: yesNuclear Engineering and Technology, 2022
Experiments were performed to measure the critical heat flux (CHF) on a vertical surface abutting a coarse packed bed of spherical particles. This geometry is representative of a CANDU reactor calandria tubesheet facing the end shield cavity during the ...
Justin Spencer
doaj   +1 more source

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