Accident Analysis in Research Reactors [PDF]
The first Research Reactor reaches its criticality on 2nd December 1942. Nowadays, more than 300 research reactors are currently in operation. Over the past fifty years, research reactors have progressed through a variety of tasks.
Adorni, Martina
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Analisis Perbandingan Kinerja Perangkat Bahan Bakar Pltn Tipe Pwr Ap 1000 Dan Pwr 1000 Mwe Tipikal Dengan Menggunakan Program Komputer [PDF]
, 2014 Investigation of fuel element thermal-hydraulic characteristic is important step related to aspect of fuel bundle reactor design. This paper analyzes of the PWR AP1000 and PWR 1000 MWe Typical of fuel bundle thermal-hydraulic using RELAP5 code.
Nurmawan, A. (Arif) +2 more
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An approach based on Support Vector Machines and a K-D Tree search algorithm for identification of the failure domain and safest operating conditions in nuclear systems [PDF]
, 2016 The safety of a Nuclear Power Plant (NPP) is verified by analyzing the system responses under normal and accidental conditions. This is done by resorting to a Best-Estimate (BE) Thermal-Hydraulic (TH) code, whose outcomes are compared to given safety ...
Alfonsi, Andrea +4 more
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Improved technique of a complex analysis of crack resistance of wwer-1000 nuclear reactor cold leg nozzle under termal shock. Report 2. Brittle strength [PDF]
, 2014 В Україні для тепло-гідравлічних розрахунків різних сценаріїв, можливих на реакторних установках АЕС,використовується розрахунковий комплекс RELAP5. Проблема полягає в тому, що ці розрахунки в районі патрубка корпуса реактора зазвичай проводять на грубій
Iakovliev, A. +3 more
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Analisi dello shock termico in un RPV tipo WWER100 in condizioni di DEGB [PDF]
, 2005 Nel settore dell'Ingegneria nucleare, è di importanza fondamentale l'analisi di problemi relativi alla sicurezza degli impianti già esistenti od in fase di progettazione.
Frustaci, Luca
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RELAP5/MOD3.3 Code Validation with Plant Abnormal Event
Science and Technology of Nuclear Installations, 2008 Measured plant data from various abnormal events are of great importance for code validation. The purpose of the study was to validate the RELAP5/MOD3.3 Patch 03 computer code with the abnormal event which occurred at Krško Nuclear Power Plant (NPP) on ...
Andrej Prošek, Borut Mavko
doaj +1 more source
A review of the application of artificial intelligence to nuclear reactors: Where we are and what's next. [PDF]
Heliyon, 2023 Huang Q +6 more
europepmc +1 more source
Forced boiling of nanofluids, effects of contact angle and surface wettability [PDF]
, 2011 This paper was presented at the 3rd Micro and Nano Flows Conference (MNF2011), which was held at the Makedonia Palace Hotel, Thessaloniki in Greece.
3rd Micro and Nano Flows Conference (MNF2011) +4 more
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Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000
Ядерна фізика та енергетика, 2019 The research presents an analysis of the known results in modeling the maximum design accident (MDA) using the code RELAP5/V3.2 with Westinghouse fuel assemblies’ (WFA) diversification in WWER-1000 reactors.
V. I. Skalozubov +4 more
doaj +1 more source
Application target image of a small modular fluoride salt-cooled high temperature reactor based on the analysis of energy demand and environmental conditions in western China. [PDF]
Heliyon, 2022 Guo Y, Dai Y, Zhang J, Jiang D, Fu Y.
europepmc +1 more source