Results 41 to 50 of about 272 (168)

The SG‐Climbot: An Adaptable, Efficient, Inspection and Repair Robot for Steam Generator Heat Transfer Tube Sheet

Journal of Field Robotics, Volume 42, Issue 4, Page 1080-1102, June 2025.
ABSTRACT The steam generator plays a crucial role as a safety component and protective barrier in nuclear power plants. Regular inspection and repair of heat transfer tubes, which operate in high‐temperature, high‐pressure, corrosive, and abrasive environments for extended periods, are essential.
Zhaojin Liu, Jiawei Li, Jian Chen, Sicen Li, Xin Gu, Jikai Jiang, Yuxiao Li, Shaoming Yao, Gang Wang   +8 more
wiley   +1 more source

Cooling the intact loop of primary heat transport system using Shutdown Cooling System in case of LOCA events

EPJ Nuclear Sciences & Technologies, 2015
The purpose of this paper is to model the operation of the Shutdown Cooling System (SDCS) for CANDU 6 nuclear power plants in case of LOCA accidents, using Flowmaster calculation code, by delimiting models and setting calculation assumptions, input data ...
Icleanu Diana Laura, Prisecaru Ilie, Jianu Iulia Nicoleta   +2 more
doaj   +1 more source

Nuclear Decommissioning and Sustainable Environment: Insights on Decontamination Processes

Advanced Energy and Sustainability Research, Volume 6, Issue 1, January 2025.
The sequence of nuclear decommissioning and its role in promoting a sustainable environment are elucidated. Insights on strategy of nuclear decontamination technologies are highlighted, and techniques for radioactive waste treatment are discussed.
Miguta Faustine Ngulimi, Sion Kim, Kamal Asghar, Bum Kyoung Seo, Changhyun Roh   +4 more
wiley   +1 more source

Development and Verification of Activated Source Term Library Based on ENDF/B‐VIII.0

International Journal of Energy Research, Volume 2025, Issue 1, 2025.
Developed by the Oak Ridge National Laboratory (ORNL) in the United States, the ORIGEN code for computing irradiation and decay processes is one of the most widely used point depletion programs. However, the nuclear data that accompanies it, crucial for its application, has been measured and evaluated a long time ago.
Xirui Zhang, Dacai Zhang, Hao Luo, Wenxiang Fang, Te Sheng, Ganglin Yu, Chaofan Sun   +6 more
wiley   +1 more source

Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors

EPJ Nuclear Sciences & Technologies, 2016
This paper discusses concepts for three-component fuel bundles containing plutonium, uranium and thorium for use in pressurised heavy water reactors, and cases for and against implementation of such a nuclear energy system in the United Kingdom.
Peel Ross, Van Den Durpel Luc, Ogden Mark Daniel, Whittle Karl Rhys   +3 more
doaj   +1 more source

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

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

Multiphysical Simulations for the IAEA/ISCP Benchmark Model on the Contact of Pressure Tube and Calandria Tube in the Moderator System of CANDU-6 PHWR

Science and Technology of Nuclear Installations, 2018
The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressurized heavy water reactor) as well as other nuclear facilities, and possible cause of LOCA can be counted on the ballooning of pressure tube (PT) contacted ...
Hyoung Tae Kim, Se-Myong Chang, Young Woo Son, Taegee Min   +3 more
doaj   +1 more source

CANDU-6 operation simulations using accident tolerant cladding candidates

Annals of Nuclear Energy, 2019
Abstract The 3D DRAGON-DONJON capabilities are exploited to simulate CANDU-6 (Canada Deuterium Uranium) core follow-up with alternate cladding materials. Aluminium-based alloys (FeCrAl and APMT), nickel-based alloys (304SS and 310SS) and silicon carbide (SiC) are compared with Zircaloy-II.
A. Naceur, G. Marleau
openaire   +2 more sources