Results 31 to 40 of about 391 (181)

Iron and radioactivity transport code package for multiple CANDU designs

open access: yesNuclear Engineering and Technology
To ensure the safe and reliable operation of nuclear reactors, predictive modelling of iron and activity transport is a necessary tool for examining how changes to key chemistry parameters impact the distribution of corrosion products and corresponding ...
C. Perry, O. Palazhchenko
doaj   +1 more source

Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis

open access: yesScience and Technology of Nuclear Installations, 2015
The current neutronics design methodology of CANDU-PHWRs based on the two-step calculations requires determining not only homogenized two-group constants for ordinary fuel bundle lattice cells by the WIMS-AECL lattice cell code but also incremental two ...
Seung Yeol Yoo   +2 more
doaj   +1 more source

Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis

open access: yesNuclear 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

Quality of Local Rice Genotypes and Their Improvement With Urea and Fermented Rice Husk Ash

open access: yesAdvances in Agriculture, Volume 2026, Issue 1, 2026.
The quality and nutritional value of rice (Oryza sativa L.) are important for its economic value and for addressing malnutrition in developing countries. This study aims to identify local rice genotypes exhibiting high quality and high protein across various agroecosystems, and to increase rice protein content (PC) through the application of urea and ...
Nurhayati Nurhayati   +11 more
wiley   +1 more source

DEVELOPMENT OF GEOLOGICAL DISPOSAL SYSTEMS FOR SPENT FUELS AND HIGH-LEVEL RADIOACTIVE WASTES IN KOREA

open access: yesNuclear Engineering and Technology, 2013
Two different kinds of nuclear power plants produce a substantial amount of spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU ...
HEUI-JOO CHOI   +2 more
doaj   +1 more source

Transmuting the Arid: Fission‐Powered Visions—Unlocking Ghana’s Aquatic Destiny Through Nuclear Desalination

open access: yesScience and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.
Water scarcity poses a mounting constraint on Ghana’s socioeconomic development, intensified by climate‐driven hydrological variability, rapid urbanization, and industrial expansion. This study presents a Ghana‐specific techno‐economic and policy‐integrated assessment of nuclear‐powered seawater desalination, moving beyond generic applications of ...
Felix Ameyaw   +3 more
wiley   +1 more source

Mesh and turbulence model sensitivity analyses of computational fluid dynamic simulations of a 37M CANDU fuel bundle

open access: yesNuclear Engineering and Technology, 2022
Mesh and turbulence model sensitivity analyses have been performed on computational fluid dynamics simulations executed with Hydra and ANSYS Fluent for a single CANadian Deuterium Uranium (CANDU) 37M nuclear fuel bundle placed within a standard pressure ...
Z. Lu, M.H.A. Piro, M.A. Christon
doaj   +1 more source

Analysis of the Effective Dose to the Public Living Around Korean Nuclear Power Plants After the Monitoring of Carbon‐14 Discharge Was Implemented

open access: yesEnergy Science &Engineering, Volume 13, Issue 12, Page 5810-5820, December 2025.
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

A New Fuel Design for Two Different HW Type Reactors

open access: yesScience and Technology of Nuclear Installations, 2011
A new fuel element (called CARA) designed for two different heavy water reactors (HWRs) is presented. CARA could match fuel requirements of both (one CANDU and one unique Siemens's design) Argentine HW reactors. It keeps the heavier fuel mass density and
Daniel O. Brasnarof   +3 more
doaj   +1 more source

SARAPAN—A Simulated-Annealing-Based Tool to Generate Random Patterned-Channel-Age in CANDU Fuel Management Analyses

open access: yesNuclear Engineering and Technology, 2017
In any reactor physics analysis, the instantaneous power distribution in the core can be calculated when the actual bundle-wise burnup distribution is known.
Doddy Kastanya
doaj   +1 more source

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