Results 51 to 60 of about 3,373 (173)

Analysis of carbon‐14 discharges from Korean nuclear power plants

Energy 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, Tae Young Kong, Seongjun Kim, Jinho Son, Changju Song, Jiung Kim, Hee Geun Kim   +6 more
wiley   +1 more source

BACKUP AND ULTIMATE HEAT SINKS IN CANDU REACTORS FOR PROLONGED SBO ACCIDENTS

Nuclear Engineering and Technology, 2013
In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage would begin with the depletion of the liquid moderator, exposing the top row of internally-voided fuel channels to steam cooling conditions on the inside and ...
T. NITHEANANDAN, M.J. BROWN
doaj   +1 more source

Nickel‐based alloy corrosion in CANDU steam generators: E–pH diagrams of the Ni–NH3–H2O and Ni–CH3COO−–H2O ternary systems

Materials and Corrosion, Volume 75, Issue 4, Page 529-542, April 2024.
The simulated E–H diagrams of nickel could be used to predict the corrosion of steam generator tubes of Canadian Deuterium Uranium reactors. Abstract Nuclear power plant steam generator (SG) tubes contain nickel as the main alloying element and there is concern about their corrosion.
Mohammad Amin Razmjoo Khollari, Hamid Zebardast, Edouard Asselin   +2 more
wiley   +1 more source

Proposal and Validation of a Diagnosis Method of Fuel Failures in Pressurized Water Reactor Nuclear Power Plants

Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.
Based on research into the diagnosis methods for fuel failures in pressurized water reactor nuclear power plants and an analysis of existing problems, this paper proposes an enhanced fuel failure diagnosis method, addressing three key improvements: identification of the occurrence of fuel failure, diagnosis of the number of failed fuel rods, and the ...
Weifeng Lyu, Wenwang Ran, Runchun Guo, Yaoyi Gao, Jun Xiong, Arkady Serikov   +5 more
wiley   +1 more source

Systems analysis of the CANDU 3 Reactor

, 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
Wright, A. L., Fontana, M. H., Linn, M. A., Olszewski, M., Wolfgong, J. R.   +4 more
core   +1 more source

CANDU DAN MILITER KETERLIBATAN BADAN-BADAN PERJUANGAN DALAM PERDAGANGAN CANDU DI JAWA PADA MASA REVOLUSI

Jurnal Kawistara, 2016
During revolution era, Indonesian government used and traded opium for struggle funds. This decision was based on the fact that the social, economic and financial was shattered due to Japanese occupation. Whereas the government should provide substantial
Julianto Ibrahim
doaj   +1 more source

Neutronic Analysis of Accident‐Tolerant Cladding Materials in 3D Full Core BEAVRS PWR Benchmark Using OpenMC Code

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri, Meshari M. Alqahtani, Abdullah S. Alomari, Abdullah I. Almarshad, Andrey Kuzmin   +4 more
wiley   +1 more source

Radiation damage to Ni-based alloys in Wolsong CANDU reactor environments

Nuclear Engineering and Technology, 2019
Radiation damage due to neutrons has been calculated in Ni-based alloys in Wolsong CANDU reactor environments. Two damage parameters are considered: displacement damage, and transmutation gas production.
Junhyun Kwon, Hyung-Ha Jin, Gyeong-Geun Lee, Dong-Hwan Park   +3 more
doaj   +1 more source

Optimization of the self-sufficient thorium fuel cycle for CANDU power reactors [PDF]

Nuclear Technology and Radiation Protection, 2008
The results of optimization calculations for CANDU reactors operating in the thorium cycle are presented in this paper. Calculations were performed to validate the feasibility of operating a heavy-water thermal neutron power reactor in a self-sufficient ...
Bergelson Boris R., Gerasimov Alexander S., Tikhomirov Georgy V.   +2 more
doaj   +1 more source

Thermalhydraulics of advanced 37-element fuel bundle in crept pressure tubes

EPJ Nuclear Sciences & Technologies, 2016
A CANDU-6 reactor, which has 380 fuel channels of a pressure tube type, is suffering from aging or creep of the pressure tubes. Most of the aging effects for the CANDU primary heat transport system were originated from the horizontal crept pressure tubes.
Park Joo Hwan, Song Yong Mann
doaj   +1 more source