Results 41 to 50 of about 1,019,583 (175)

Sorting of surveillance specimen halves relative to their location in the VVER-1000 reactor under irradiation

Ядерна фізика та енергетика, 2019
The paper presents the procedure developed at the Department of Radiation Material Science of INR NAS of Ukraine for longitudinal radiometric scanning of surveillance specimens of the Ukrainian reactor vessels and its joint application with ...
Yu. S. Gulchuk, L. I. Chyrko
doaj   +1 more source

Validation of the code package MCPV with continuous-energy data library [PDF]

Ядерна фізика та енергетика
The results of the validation of the code package MCPV for the calculation of radiation transport within VVER-1000 reactor type near-vessel space using a continuous-energy data library are presented.
О. M. Pugach, S. M. Pugach, V. L. Diemokhin, V. N. Bukanov, O. V. Grytsenko   +4 more
doaj   +1 more source

Transmuting the Arid: Fission‐Powered Visions—Unlocking Ghana’s Aquatic Destiny Through Nuclear Desalination

Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.
Water scarcity poses a mounting constraint on Ghana’s socioeconomic development, intensified by climate‐driven hydrological variability, rapid urbanization, and industrial expansion. This study presents a Ghana‐specific techno‐economic and policy‐integrated assessment of nuclear‐powered seawater desalination, moving beyond generic applications of ...
Felix Ameyaw, Etornam Akaho, Seth Debrah, Doddy Kastanya   +3 more
wiley   +1 more source

Development of an Analytic Nodal Diffusion Solver in Multigroups for 3D Reactor Cores with Rectangular or Hexagonal Assemblies. [PDF]

, 2009
More accurate modelling of physical phenomena involved in present and future nuclear reactors requires a multi-scale and multi-physics approach. This challenge can be accomplished by the coupling of best-estimate core-physics, thermal-hydraulics and ...
Aragonés Beltrán, José María, García Herranz, Nuria, Lozano Montero, Juan Andrés   +2 more
core  

Experimental studies into the fluid dynamic performance of the coolant flow in the mixed core of the Temelin NPP VVER-1000 reactor

Nuclear Energy and Technology, 2015
The paper presents the results of studies into the interassembly coolant interaction in the Temelin nuclear power plant (NPP) VVER-1000 reactor core.
S.M. Dmitriev, D.V. Doronkov, Ye.N. Polozkova, A.N. Pronin, V.D. Sorokin, A.Ye. Khrobostov   +5 more
doaj   +1 more source

Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident

Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.
In the design of nuclear power plant systems, the thermal–hydraulic response in the containment during a loss‐of‐coolant accident (LOCA) plays a crucial role. In this study, the advanced small modular reactor NHR200‐II is selected as the research object.
Yan Wang, Yifan Meng, Zixuan Wang, Mohammad Rezwan Habib   +3 more
wiley   +1 more source

Investigation of Thermal Performance of Aluminum Nanoparticle Coolant in VVER-1000 Reactor

, 2021
Thermal analysis is of great importance when examining the safety and design features of nuclear power reactors. The aim of this study is to examine the effect of pure water and coolant containing Al2O3 nanoparticles on thermal performance of VVER-1000 ...
ACIR, ADEM, Yasin GENÇ, Uzun, Sinem, Adem ACIR, Sinem UZUN, Genc, Yasin   +5 more
core   +1 more source

Global Fossil Methane Emissions Constrained by Multi‐Isotopic Atmospheric Methane Histories

Journal of Geophysical Research: Atmospheres, Volume 130, Issue 5, 16 March 2025.
Abstract The global CH4 budget of sources and sinks is highly uncertain, particularly the emissions from specific sources such as fossil fuels (FF) or agriculture. Here, we estimate plausible global CH4 source and sink scenarios using historical observations and simulations of atmospheric CH4 mole fraction and its stable isotopic (δ13C‐CH4, δD‐CH4) and
Ryo Fujita, Heather Graven, Giulia Zazzeri, Benjamin Hmiel, Vasilii V. Petrenko, Andrew M. Smith, Sylvia E. Michel, Shinji Morimoto   +7 more
wiley   +1 more source

Investigation of DPA in the reactor pressure vessel of VVER-1000/V320

Nuclear Science and Technology, 2017
The most important ageing effect on the reactor pressure vessel (RPV) is radiation embrittlement, which is mainly caused by fast neutrons during operation lifetime of nuclear reactors. The aim of this study was to investigate the DPA (displacement per atom) rate, an important parameter describing radiation damage to the RPV, and identify the position ...
Huu Tiep Nguyen, Viet Ha Pham Nhu, Minh Tuan Nguyen   +2 more
openaire   +2 more sources

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