Results 71 to 80 of about 176 (127)

AI-Assisted Forecasting of a Mitigated Multiple Steam Generator Tube Rupture Scenario in a Typical Nuclear Power Plant

Energies
This study is focused on developing a machine learning (ML) meta-model to predict the progression of a multiple steam generator tube rupture (MSGTR) accident in the APR1400 reactor.
Sonia Spisak, Aya Diab
doaj   +1 more source

In-Vessel Melt Retention of Pressurized Water Reactors: Historical Review and Future Research Needs

Engineering, 2016
A historical review of in-vessel melt retention (IVR) is given, which is a severe accident mitigation measure extensively applied in Generation III pressurized water reactors (PWRs).
Weimin Ma, Yidan Yuan, Bal Raj Sehgal
doaj   +1 more source

Combined Heat and Power Design Considerations for the APR1400 [PDF]

Journal of Energy and Power Engineering, 2017
null Michał Wierzchowski, null Robert M. Field   +1 more
openaire   +1 more source

Improvement of DeCART2D multigroup cross section library correction system and APR-1400 benchmarking

Nuclear Engineering and Technology
In this study, an improved multigroup (MG) cross section library correction system for the DeCART2D transport lattice code was developed by introducing group-wise correction factors for absorption, fission reactions, and the scattering matrix.
Chiheon Kim, Ho Jin Park
doaj   +1 more source

Dynamic Multiphysics Simulation of the Load-Following Behavior in a Typical Pressurized Water Reactor Power Plant

Energies
Most Nuclear Power Plants (NPPs) are designed for baseload operations, maintaining a steady power output at 100%, except during planned maintenance and refueling.
Ivan Panciak, Aya Diab
doaj   +1 more source

Excess reactivity control using innovative burnable absorber configuration for a 24-month cycle APR-1400

Alexandria Engineering Journal
Extending the fuel cycle from 18 to 24 months in Pressurized Water Reactors (PWRs) using LEU+ fuel (5 % ≤ U-235 ≤ 10 %) increases excess reactivity, requiring effective control to ensure safety and performance.
Khurrum Saleem Chaudri, Mohammad Alrwashdeh, Saeed A. Alameri   +2 more
doaj   +1 more source

Simulation of shockwave propagation characteristics in nuclear reactor cavity during external steam explosion using unified SPH

Nuclear Engineering and Technology
Steam explosions in nuclear reactors pose significant risks to reactor safety and containment integrity during severe accidents. This study addresses the challenges of accurately simulating shockwave propagation and structural impact in such events by ...
JinHyun Kim, Hee Sang Yoo, Young Beom Jo, Eung Soo Kim   +3 more
doaj   +1 more source

EMBRACEing HuREX data: A fundamental approach to develop a plant-specific human reliability analysis method

Nuclear Engineering and Technology
Plant-specific human reliability analysis (HRA) tailors human error probabilities (HEPs) to a facility's unique contexts. The diversity of digital human-machine interfaces and operational cultures necessitates methods grounded in empirical data rather ...
Yochan Kim, Jaewhan Kim
doaj   +1 more source

Validation and Application of a Code for Three-Dimensional Analysis of Hydrogen–Steam Behavior in a Nuclear Reactor Containment during Severe Accidents

Applied Sciences
In a pressurized water reactor (PWR) during a loss of coolant accident (LOCA) or a station blackout (SBO) accident, water and steam are released into the containment building.
Jongtae Kim, Kukhee Lim
doaj   +1 more source

Critical evaluation of accident tolerant fuel selection criteria for APR-1400 nuclear reactors

Advances in Physics: X
The United Arab Emirates (UAE) launched its nuclear energy program in 2008, achieving notable outcomes with the ‘UAE Policy on the Peaceful Use of Nuclear Energy’ program.
Mohammad Alrwashdeh, Asma Alzarooni, Khurrum Saleem Chaudri, Maithah Alaleeli, K. Karuppasamy, Andreas Schiffer, Imran Afgan, Daniel Choi, Saeed A. Alameri   +8 more
doaj   +1 more source