Results 41 to 50 of about 3,636 (213)
A Comparison in Thermal-hydraulics Analysis of Pwr1000 Using Fixed and Temperature Function of Thermal Conductivity [PDF]
, 2016 A COMPARISON IN THERMAL-HYDRAULICS ANALYSIS OF PWR-1000 USING FIXEDAND TEMPERATURE FUNCTION OF THERMAL CONDUCTIVITY. A study to analyze theinfluence of the fuel-cladding's thermal conductivity on the sub-channel of pressurized waterreactor 1000 (PWR-1000)
Isnaini, M. D. (Muhammad) +1 more
core +2 more sources
EPJ Web of Conferences, 2016 Usually the synthesis of two-dimensional and one-dimensional discrete ordinate calculations is used to evaluate neutron fluence on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation embrittlement.
Dzhalandinov A. +8 more
doaj +1 more source
EPJ Web of Conferences, 2016 The broad-group library BGL1000_B7 for neutron and gamma transport calculations in VVER-1000 internals, RPV and shielding was carried out on a base of fine-group library v7-200n47g from SCALE-6 system.
Voloschenko Andrey +3 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2010 The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of coupled codes for reactor safety evaluations, aiming to improve their prediction capability and acceptability.
V. Sánchez +3 more
doaj +1 more source
Brittle fracture resistance of reactor pressure vessel steels in the initial state [PDF]
Nuclear Energy and Technology, 2018 The authors investigate the influence of chemical and structural inhomogeneity on the brittle fracture resistance (BFR) of VVER vessel materials in the initial state (without irradiation).
Nikolay P. Anosov +5 more
doaj +3 more sources
Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis
Nuclear Engineering and Technology, 2022 This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo–vodyanoi energetichesky reactor) analysis.
Jaerim Jang +2 more
doaj +1 more source
Про создание конечно-элементной модели корпуса главного циркуляционного насоса блока АЭС типа ВВЭР-1000 [PDF]
, 2010 Розглянуто проблеми створення скінченно-елементної моделі корпуса головного циркуляційного насоса блоку АЕС типу ВВЕР-1000, виявлені причини їхньої появи, запропоновані підходи, що дозволяють успішно їх перебороти.
Рудаков, К. Н.
core +1 more source
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 +5 more
doaj +1 more source
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 +3 more
wiley +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 +7 more
wiley +1 more source