Results 41 to 50 of about 354,480 (157)
ABSTRACT Radioactive effluents discharged by nuclear power plants (NPPs) are classified into two categories: gas and liquid effluents, based on their source and discharge pathways. During the operation of these facilities, both types of effluents are released into the environment.
Hwapyoung Kim +2 more
wiley +1 more source
EVALUATION OF THE APPLICABLE REACTIVITY RANGE OF A REACTIVITY COMPUTER FOR A CANDU-6 REACTOR
Recently, a CANDU digital reactivity computer system (CDRCS) to measure the worth of the liquid zone controller in a CANDU-6 was developed and successfully applied to a physics test of refurbished Wolsong Unit 1.
EUN KI LEE, DONG HWAN PARK, WHAN SOO LEE
doaj +1 more source
En 2014 Argentina firmó con China un convenio para construir nuevos reactores nucleares en el país. En ese marco, se planificó la construcción de un reactor CANDU en manos de una empresa local.
Ana Spivak
doaj +1 more source
ABSTRACT The steam generator plays a crucial role as a safety component and protective barrier in nuclear power plants. Regular inspection and repair of heat transfer tubes, which operate in high‐temperature, high‐pressure, corrosive, and abrasive environments for extended periods, are essential.
Zhaojin Liu +8 more
wiley +1 more source
Nuclear Decommissioning and Sustainable Environment: Insights on Decontamination Processes
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
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
Development and Verification of Activated Source Term Library Based on ENDF/B‐VIII.0
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
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
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
Qualification of Reactor Physics Toolset for a Thorium-Fuelled CANDU Reactor
AECL has developed enhanced versions of the reactor physics computer codes for analysis of CANDU® reactors and the ACR-1000™. The central codes that comprise the analysis toolset are WIMS-AECL (a lattice code), RFSP (a core code) and MCNP5 (a Monte Carlo
Bronwyn Hyland +2 more
core +1 more source

