Results 1 to 10 of about 8,801 (168)

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   +3 more sources

Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor [PDF]

open access: yesNuclear Technology and Radiation Protection, 2022
The study presents the analysis of the reusability of ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. The spent UO2 fuels are taken out from pressurized water reactor and CANDU spent fuels.
Durmaz Busra   +3 more
doaj   +1 more source

EVALUATION OF NEUTRON SHIELDING PERFORMANCE OF CD-SS 316L AS A CANDIDATE ALLOY FOR DRY CASK OF RESEARCH REACTOR SPENT FUEL

open access: yesUrania, 2021
EVALUATION OF NEUTRON SHIELDING PERFORMANCE OF CD-SS 316L AS A CANDIDATE ALLOY FOR DRY CASK OF RESEARCH REACTOR SPENT FUEL Development of dry casks is necessary to support the national strategy for management of spent fuels.
Kuat Heriyanto   +5 more
doaj   +1 more source

Analysis of loss of cooling accident in VVER-1000/V446 spent fuel pool using RELAP5 and MELCOR codes

open access: yesNuclear Engineering and Technology, 2023
Following the Fukushima nuclear disaster, the simulation of accidents in the spent fuel pool has become more noticeable. Despite the low amount of decay heat power, the consequences of the accidents in a spent fuel pool (SFP) can be severe due to the ...
Seyed Khalil Mousavian   +2 more
doaj   +1 more source

Neutron Tomography of Spent Fuel Casks [PDF]

open access: yesJournal of Signal Processing Systems, 2021
Dry casks for spent nuclear fuel (SNF) ensure the safe storage of SNF and provide radiation shielding. However, the presence of the thick casks encompassing several layers of steel and concrete makes inspection of the SNF a challenging task. Fast neutron interrogation is a viable method for the nondestructive assay of dry storage casks.
Zhihua Liu   +4 more
openaire   +3 more sources

Long-Term Radiotoxicity Evaluation of PWR Spent Uranium and MOX Fuel and Highly Active Waste [PDF]

open access: yesE3S Web of Conferences, 2020
One of the main concerns related to nuclear power production is the generation and accumulation of spent nuclear fuel. Currently most of the spent fuel is stored in interim storage facilities awaiting final disposal or reprocessing.
Paunov Petar, Naydenov Ivaylo
doaj   +1 more source

Thermal Evaluation of a Dual Purpose Cask for Bushehr Nuclear Reactor Spent Fuels Under Normal Conditions [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2019
Dual purpose cask system is one of the most important developing systems of dry interim storage of nuclear spent fuels. Thermal evaluation of a dual purpose cask designed for transport and interim storage of spent fuels of Bushehr Nuclear Power Plant is ...
M Rezaeian, J Kamali, S.J Ahmadi
doaj   +1 more source

A STUDY ON THE INITIAL CHARACTERISTICS OF DOMESTIC SPENT NUCLEAR FUELS FOR LONG TERM DRY STORAGE

open access: yesNuclear Engineering and Technology, 2013
During the last three decades, South Korean nuclear power plants have discharged about 5,950 tons of spent fuel and the maximum bum-up reached 55 GWd/MTU in 2002.
JUSEONG KIM   +3 more
doaj   +1 more source

Heat transfer in a simulated spent fuel pool for different types of spent fuels

open access: yesBrazilian Journal of Development, 2023
Historically, the Spent Fuel Pool (SFP) of Angra II, from Brazil, has received standard spent fuel (SF) assemblies of uranium dioxide (UO2) discharged from Pressurized Water Reactors (PWR) of the Nuclear Power Plants (NPP) of Angra. However, in case of using Mixed Oxide (MOX) or thorium-based fuels at a proportion of 1/3 or 1/4 of the total of fuel ...
de Faria, Fernando Pereira   +5 more
openaire   +2 more sources

Physics analysis of new TRU recycling options using FCM and MOX fueled PWR assemblies

open access: yesNuclear Engineering and Technology, 2020
In this work, new multi-recycling options of TRU nuclides using PWR fuel assemblies comprised of MOX and FCM (Fully Ceramic Micro Encapsulated) fuels are suggested and neutronically analyzed.
Ye Seul Cho, Ser Gi Hong
doaj   +1 more source

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