Results 51 to 60 of about 354,480 (157)

Once-through CANDU reactor models for the ORIGEN2 computer code [PDF]

, 1980
Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2 computer code. The model CANDUs are based on (1) the existing once-through fuel cycle with feed comprised of natural uranium and (2) a projected slightly
Croff, A. G., Bjerke, M. A.
core   +1 more source

Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics

Science and Technology of Nuclear Installations, 2018
The Canadian Supercritical Water-cooled Reactor (SCWR), a GEN IV reactor design, is a hybrid design of the well-established CANDU™ and Boiling Water Reactor with water above its thermodynamic critical point.
Frederic Salaun, David R. Novog
doaj   +1 more source

A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters

Nuclear Engineering and Technology, 2016
Important safety parameters such as the fuel temperature coefficient (FTC) and the power coefficient of reactivity (PCR) of the CANada Deuterium Uranium (CANDU-6) reactor have been evaluated using the Monte Carlo method.
Yonghee Kim, Donny Hartanto, Woosong Kim
doaj   +1 more source

Critical heat flux in a CANDU end shield – Influence of shielding ball diameter

Nuclear Engineering and Technology, 2022
Experiments were performed to measure the critical heat flux (CHF) on a vertical surface abutting a coarse packed bed of spherical particles. This geometry is representative of a CANDU reactor calandria tubesheet facing the end shield cavity during the ...
Justin Spencer
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

Potential of a Catalyzed Fusion-Driven Hybrid Reactor for the Regeneration of Candu Spent Fuel

, 1991
The potential of a catalyzed fusion-driven fast hybrid blanket to regenerate Canada deuterium uranium (CANDU) spent fuel is investigated. The investigations are done to achieve enrichment grades of fissile isotopes (EGFIs) in four applications: 1 ...
YAPICI, H, Hüseyin Yapici, Sümer Şahin, BALTACIOGLU, E, SAHIN, S, Ertuğrul Baltacioğlu   +5 more
core   +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