Results 21 to 30 of about 176 (127)

Seismic response prediction using intensity measures: Graphite nuclear reactor core model case study

Earthquake Spectra, Volume 39, Issue 4, Page 1992-2018, November 2023., 2023
Seismic response analyses of structures have conventionally used the peak ground acceleration or spectral acceleration as an intensity measure to estimate the engineering demand parameters. An extensive shaking table test program was carried out on a quarter‐sized advanced gas‐cooled reactor (AGR) core model to investigate the global dynamic behavior ...
Tansu Gokce, Rory E White, Adam J Crewe, Matt Dietz, Tony Horseman, Luiza Dihoru   +5 more
wiley   +1 more source

Daily Load‐Follow Operation in LEU+‐Loaded APR1400 Using Mode‐K+ Control Logic

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
This study evaluates the efficacy of the mode‐K+ control logic for daily load‐follow operation (DLFO) in a two‐batch LEU+ fuel‐loaded APR1400 reactor with an accident tolerant fuel (ATF) cladding. The objective is to assess the performance of the control strategy under various operational conditions including high burnup.
Husam Khalefih, Yunseok Jeong, Yonghee Kim, Koteswara Raju Dhenuvakonda   +3 more
wiley   +1 more source

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal‐Hydraulic System Analysis Code

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
The external reactor vessel cooling provides a means to stabilize the molten core inside the reactor vessel during the severe accident in nuclear power plants. For a credible evaluation of the chances of success of in‐vessel melt retention, one requires high‐fidelity predictions on the natural circulation flow around the reactor vessel and, in ...
Yeon-Gun Lee, Il Woong Park, Geng Chen
wiley   +1 more source

The Role of Nuclear Energy in Reducing Greenhouse Gas (GHG) Emissions and Energy Security: A Systematic Review

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
The energy sector accounts for about two‐thirds of all human‐related greenhouse gas (GHG) emissions due to the reliance on fossil‐based fuels. This is a significant concern as it can have dire consequences on the survival of humankind and disrupt other natural processes.
Emmanuel Kusi Addo, Amos Tiereyangn Kabo-bah, Felix Amankwah Diawuo, Seth Kofi Debrah, Pawan Kumar Kulriya   +4 more
wiley   +1 more source

Assessment of Realistic Departure from Nucleate Boiling Ratio (DNBR) Considering Uncertainty Quantification of Core Flow Asymmetry

Energies, 2021
Concern over the asymmetric phenomena in the core region has increased considering safety issues that are highly possible to reduce the thermal margin significantly in nuclear power plants.
Il Suk Lee, Dong Hyeog Yoon, Young Seok Bang, Tae Hoon Kim, Yong Chan Kim   +4 more
doaj   +1 more source

Comparative analysis of occupational radiation doses when decommissioning nuclear power plants

Energy Science &Engineering, Volume 10, Issue 12, Page 4358-4365, December 2022., 2022
Radiation doses from precedent decommissioning nuclear power plants worldwide are compared with radiation doses estimated from Kori 1, the first decommissioning‐planned reactor in Korea, to determine dose reduction measures that can achieve radiation exposure that is as low as reasonably achievable to decommissioning workers. Abstract Kori 1, the first
Eun Ji Lee, Tae Young Kong, Seong Jun Kim, Wo Suk Choi, Jin Ho Son, Chang Ju Song, Hwa Pyoung Kim, Si Young Kim, Moonhyung Cho, Hee Geun Kim   +9 more
wiley   +1 more source

DESIGN OF A VIBRATION AND STRESS MEASUREMENT SYSTEM FOR AN ADVANCED POWER REACTOR 1400 REACTOR VESSEL INTERNALS COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM

Nuclear Engineering and Technology, 2013
In accordance with the US Nuclear Regulatory Commission (US NRC), Regulatory Guide 1.20, the reactor vessel internals comprehensive vibration assessment program (RVI CVAP) has been developed for an Advanced Power Reactor 1400 (APR1400).
DO-YOUNG KO, KYU-HYUNG KIM
doaj   +1 more source

Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions

Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022
In‐vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants. The most influential issues on the IVR strategy are in‐vessel core melt evolution, the heat fluxes imposed on the lower head, and the external cooling of reactor pressurized vessel (RPV).
Shilei Han, Pengfei Liu, Bo Kuang, Yanhua Yang, Arkady Serikov   +4 more
wiley   +1 more source

Optimization and Exergy Analysis of Nuclear Heat Storage and Recovery

Energies, 2019
The APR1400 Nuclear Heat Storage and Recovery (NHS&R) System described here represents the conceptual design and interface of a tertiary cycle with the secondary system of the Korean nuclear reactor plant APR1400.
Anna Kluba, Robert Field
doaj   +1 more source

Investigation of Loss of Feedwater (LOFW) Accident in the APR‐1400 Using Fault Tree Analysis

Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022
Nuclear power plants play a significant role in the contribution of electricity generation on a global scale. Various reactor designs have advantages over others in different aspects. APR‐1400 is a pressurized water reactor that is deemed safe due to the redundancy and independence of the multiple safety systems.
Muhammad Zubair, Raffaella Testoni
wiley   +1 more source