Results 51 to 60 of about 248 (163)

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

High-Temperature Tensile Properties and Serrated Flow Behavior of FeCrAl Alloy for Accident-Tolerant Fuel Cladding

Applied Sciences
The development of FeCrAl alloys has commenced for use as nuclear fuel cladding material, intended to serve as an enhanced accident-tolerant alternative to Zr-based alloys. In this study, the Fe-13Cr-4Al alloy, specifically designed for advanced accident-
Mengyu Chai, Zelin Han, Hao Su, Hao Li, Pan Liu, Yan Song   +5 more
doaj   +1 more source

Analysis of Ex‐Vessel Debris Coolability of Boiling Water Reactors

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
To evaluate the effectiveness of the wet cavity strategy, the authors developed a stochastic evaluation method that considers the uncertainties of the molten material conditions ejected from reactor pressure vessels. This study analyzed the probability of ex‐vessel debris coolability under the wet cavity strategy.
Toshinori Matsumoto, Takashi Hibiki, Yu Maruyama, Hamza Faraji   +3 more
wiley   +1 more source

Bi-objective optimization of compressive strength and thermal conductivity for UN-U3Si2 composite fuel based on AI techniques

Journal of Materials Research and Technology
The UN-U3Si2 composite fuel has been developed as a promising accident-tolerant fuel (ATF) due to its superior thermal conductivity and higher uranium density compared to conventional UO2.
Tianyu Song, Junkai Deng, Rui Tang, Hongxing Xiao, Xiangdong Ding, Jun Sun   +5 more
doaj   +1 more source

Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma, Maria Hendrina du Toit, Martin van Eldik, Guojun Yu   +3 more
wiley   +1 more source

Development of FEMAXI-ATF for fuel performance modeling of SiC cladded fuel involving PCMI

Nuclear Engineering and Technology
The SiC cladded fuel is being developed as a candidate for the accident tolerant fuel of light water reactors, in which the cladding wall consists of the inner SiC/SiC layer and the outer monolithic (mSiC) layer.
Yoshihiro Kubo, Akifumi Yamaji
doaj   +1 more source

Comparative analysis of accidental sequences with conventional and Accident Tolerant Fuels (ATF) in VVER-1000 reactors

Nuclear Engineering and Design
A significant percentage of reactors in operation, under construction or recently commissioned are VVER reactors. In parallel, there is a growing interest in analyzing the behavior of Accident Tolerant Fuels (ATF), also known as Advanced Technology Fuels, under development in different nuclear reactor designs.
Elena Redondo-Valero, Cesar Queral, Kevin Fernandez-Cosials, Jorge Sanchez-Torrijos, David Canal, Emilio Castro-Gonzalez, Victor Hugo Sanchez-Espinoza   +6 more
openaire   +2 more sources

Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl

Science and Technology of Nuclear Installations, 2017
Neutronic performance is investigated for a potential accident tolerant fuel (ATF), which consists of U3Si2 fuel and FeCrAl cladding. In comparison with current UO2-Zr system, FeCrAl has a better oxidation resistance but a larger thermal neutron ...
Shengli Chen, Cenxi Yuan
doaj   +1 more source

Benchmarking SiCf/SiC, FeCrAl, and Cr-coated Zr alloy claddings: evaluating thermomechanical properties and high-temperature oxidation resistance of next-generation nuclear claddings

Advances in Physics: X
Although nuclear energy is a clean and sustainable source, inherent safety concerns have long been recognized and were critically highlighted by the Chernobyl and Fukushima accidents.
Ghadeer Hegab Mohamed, Fatima Alzaabi, Mohammad Alrwashdeh, K. Karuppasamy, Saeed Alameri, Akram Alfantazi   +5 more
doaj   +1 more source

Fuel Performance Comparison of Uranium Nitride and Uranium Carbide in VVER-1200 using OpenMC [PDF]

MATEC Web of Conferences
Nuclear power is a reliable and large-scale source of GHG-free electricity. This study asses the viability of ATF fuel of uranium nitride (UN) and uranium carbide (UC) as fuel for the VVER-1200 reactor.
Jamil Meekal, Ali Majid
doaj   +1 more source