Results 61 to 70 of about 261 (180)

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

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

Review of Irradiation Programs to Study Long-Term Behaviour of In-Core Components in CANDU Reactors

Journal of Nuclear Engineering
During the life of a nuclear reactor, there are changes to the in-core components that are a function of operating environment and time. It is important to know how the properties of critical core components change, which can be assessed through ...
Lori Walters, Grant Bickel, Derek Cappon, Lucile Cogez, Robert DeAbreu, Ryan Matthews, Mitchell Mattucci, Heidi Nordin, Carol Song, Zahra Yamani   +9 more
doaj   +1 more source

Some questions on nuclear safety of heavy-water power reactor operating in self-sufficient thorium cycle [PDF]

Nuclear Technology and Radiation Protection, 2008
In this paper the comparative calculations of the void coefficient have been made for different types of channel reactors for the coolant density interval 0.8-0.01 g/cm3. These results demonstrate the following.
Bergelson Boris R., Gerasimov Alexander S., Tikhomirov Georgy V.   +2 more
doaj   +1 more source

Dynamic Xenon Response in a CANDU-600 Reactor: A Simulation Study of Power Variations

Annals of West University of Timisoara: Physics
This paper presents a comparative simulation study of xenon and fission product behavior in a CANDU-600 reactor core operating at nominal full power (100%) and an aging CANDU-600 core limited to 90% power due to end-of-life constraints.
Stan Andrei, Ferat Geoșchun
doaj   +1 more source

CENTRAL NUCLEAR ELECTRIC, A FUTURE OF ROMANIAN ENERGY [PDF]

Annals: Series on engineering sciences (Academy of Romanian Scientists), 2010
Official statistics show the year increasing the share of electricity produced in nuclear power plants. The most developed nuclear energy programs are: the United States, France, Japan, Germany and Canada.
Gabriel I. NĂSTASE, Dragoş Ionuţ NĂSTASE   +1 more
doaj  

The Feasibility of Multidimensional CFD Applied to Calandria System in the Moderator of CANDU-6 PHWR Using Commercial and Open-Source Codes

Science and Technology of Nuclear Installations, 2016
The moderator system of CANDU, a prototype of PHWR (pressurized heavy-water reactor), has been modeled in multidimension for the computation based on CFD (computational fluid dynamics) technique. Three CFD codes are tested in modeled hydrothermal systems
Hyoung Tae Kim, Se-Myong Chang, Jong-Hyeon Shin, Yong Gwon Kim   +3 more
doaj   +1 more source

Searching for incinerating the accumulated plutonium around the world by mixing it with thorium and using this mixture as a nuclear fuel in the CANDU-6

Nuclear Engineering and Technology
This work investigates the possibility of getting rid of the accumulated plutonium around the world by mixing it with fertile materials and using it as a nuclear fuel for CANDU-6.
A. Abdelghafar Galahom, Nassar Alnassar, Amr Ibrahim   +2 more
doaj   +1 more source

A Study on the Application of CRUDTRAN Code in Primary Systems of Domestic Pressurized Heavy-Water Reactors for Prediction of Radiation Source Term

Nuclear Engineering and Technology, 2017
The importance of developing a source-term assessment technology has been emphasized owing to the decommissioning of Kori nuclear power plant (NPP) Unit 1 and the increase of deteriorated NPPs.
Jong Soon Song, Hoon Jo Cho, Min Young Jung, Sang Heon Lee   +3 more
doaj   +1 more source