Results 11 to 20 of about 219 (116)

Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors

International Journal of Energy Research, Volume 2025, Issue 1, 2025.
A neutronics/thermal‐hydraulics (TH) coupled spatial dynamics code, reactor system transient analysis‐three dimensional (RESTA‐3D), has been developed for both static and transient analysis of large advanced light water reactors (LWRs), with a focus on control rod (CR) ejection accidents.
Yong Cui, Jing Shang, Longwei Mei, Jianfei Tong, Yashwant Sawle   +4 more
wiley   +1 more source

Assessment of Different Turbulence Models on Melt Pool Natural Convection Simulations With Internal Heat Source

International Journal of Energy Research, Volume 2025, Issue 1, 2025.
In the context of severe nuclear accidents, the migration of corium into the reactor pressure vessel (RPV) poses significant hazards, prompting the proposal of the in‐vessel melt retention (IVR) strategy, particularly the external reactor vessel cooling (ERVC) approach.
Pengya Guo, Peng Yu, Fengyang Quan, Yidan Yuan, Jiyang Yu, Weimin Ma, Geng Chen   +6 more
wiley   +1 more source

Numerical Simulation of Entrained Bubbles Flow in the Shell‐Tube Heat Exchanger of MSRs Based on Population Balance Model

International Journal of Energy Research, Volume 2025, Issue 1, 2025.
In molten salt reactors (MSRs), a small amount of inert gas could be entrained from the free liquid surface to the primary loop, which may have obvious impacts on the heat transfer performance of the heat exchanger, the reactivity of the core, and the migration of insoluble fission products.
Ziye Wang, Guifeng Zhu, Yang Zou, Xiaolin Liang, Liang Chen, Hongjie Xu, Maria Anna Murmura   +6 more
wiley   +1 more source

Assessment of the Drift‐Flux Parameter Correlations Implemented in the Nuclear Thermal‐Hydraulic Analysis Code TRACE

International Journal of Energy Research, Volume 2025, Issue 1, 2025.
The present study assessed the drift‐flux parameter correlations implemented in the TRACE code, the flagship thermal‐hydraulic analysis code developed by the United States Nuclear Regulatory Commission (US NRC). The code is architected on the basis of a two‐fluid model.
Takashi Hibiki, Naofumi Tsukamoto, Nagaraj Nandihalli   +2 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

A Study on Radiological Evaluation According to Exposure Conditions in Mobile Radiochemistry Analysis Facilities Using Worker’s Dose Evaluation Code

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
The decommissioning of a nuclear power plant generates a large amount of radioactive waste that requires significant disposal costs. Consequently, it is an important factor in assessing decommissioning costs. The most effective approach to minimizing decommissioning waste is rapid classification based on radioactivity levels.
Minho Lee, Sangheon Lee, Woobeom Ha, Hyunjin Yu, Jongsoon Song, Arkady Serikov   +5 more
wiley   +1 more source

Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
Nuclear reactors are subject to strict safety standards due to the critical nature of operational safety. Detecting transients as fast and accurately as possible is essential to reactor safety especially to reduce the human error of operators. In order to enhance this process, artificial intelligence (AI) offers strong opportunities.
Ceyhun Yavuz, Senem Şentürk Lüle, Han Zhang   +2 more
wiley   +1 more source

Bayesian Uncertainty Quantification of Reflooding Model With PSO–Kriging and PCA Approach

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
To improve the process of best estimate plus uncertainty (BEPU) for nuclear safety assessment and calibration of thermal–hydraulic models for error reduction, inverse uncertainty quantification (IUQ) is proposed in recent years to quantify the uncertainty of model parameters in reactor program.
Ziyue Zhang, Dong Li, Nianfeng Wang, Meng Lei, Hesham M.H. Zakaly   +4 more
wiley   +1 more source

Exploring Nuclear Energy Potential for Sustainable Development and Energy Security in Ghana: Challenges, Opportunities and Strategic Imperatives

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
This review paper delves into Ghana’s pursuit of nuclear energy as a pivotal component for sustainable development. It highlights the potential benefits of nuclear power in bolstering energy security, stimulating economic growth and advancing environmental sustainability, framed around three core development pillars: economic progress, social ...
Rex G. Abrefah, Suleman A. Zakaria, F. Ameyaw, Mohamed Hanfi   +3 more
wiley   +1 more source

Development of Emergency Planning Zones for Ghana’s Proposed Nuclear Plant Based on Radioactivity Releases From Hypothetical Accident Scenarios

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
Emergency planning zones (EPZs) for Ghana’s potential reactor site have been determined based on an assessment of atmospheric dispersion and dose calculations for multiple accident scenarios involving a VVER‐1200 reactor. The analysis was performed using the Radiological Assessment System for Consequence Analysis (RASCAL) 4.3.4 code to calculate doses ...
Alberta Blay, Sylvester Attakorah-Birikorang, Esi Awuah, Manish Sharma   +3 more
wiley   +1 more source