Science and Technology of Nuclear Installations, 2016 Maintaining the structural integrity of the reactor pressure vessel (RPV) is a critical concern related to the safe operation of nuclear power plants. To estimate the structural integrity over the designed lifetime and to support analyses for a potential
Junxiao Zheng +3 more
doaj +1 more source
An educational initiative between the Universidad Politécnica de Madrid and Spanish Young Generation in Nuclear (Jóvenes Nucleares): The Seminar of Nuclear Safety in Advanced Reactors [PDF]
, 2011 Jóvenes Nucleares (Spanish Young Generation in Nuclear, JJNN) is a non-profit organization and a commission of the Spanish Nuclear Society (SNE). The Universidad Politécnica de Madrid (Technical University of Madrid, UPM) is one of the most prestigious ...
Jiménez Varas, Gonzalo +2 more
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Accident Management Actions In An Upper-Head Small-Break Loss-Of-Coolant Accident With High-Pressure Safety Injection Failed [PDF]
, 2011 Since the Three Mile Island accident, an important focus of pressurized water reactor (PWR) transient analyses has been a small-break loss-of-coolant accident (SBLOCA). In 2002, the discovery of thinning of the vessel head wall at the Davis Besse nuclear
Gonzalez Cadelo, Juan +3 more
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Landscape, environment and community impacts of nuclear power [PDF]
, 2012 This paper is the third in a series of 8 that make up the evidence base for SDC report 'The role of nuclear power in a low carbon economy'.This document investigates the landscape impacts of all the processes involved in nuclear power from mining the ...
Sustainable Development Commission
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Analysis of the SWOT matrix as a strategy for implementing the Ap-Th1000 Reactor in Brazil
Brazilian Journal of Radiation SciencesThis article analyzes the SWOT Matrix for the implementation of the AP-Th1000 reactor with thorium fuel, aiming at a future replacement of the current nuclear reactors that use uranium as fuel by thorium.
Francky Roger Araujo da Silva +2 more
doaj +1 more source
Analysis on Phenomena of HPR1000 Large Break Loss of Coolant Accident Based on TRACE Code
Yuanzineng kexue jishu, 2022 HPR1000 is the Generation Ⅲ pressurized water reactor (PWR)technology independently developed by China. In order to deal with the steam generator tube rupture (SGTR) accident and prevent pressurizer overflow, HPR1000 adopts some new features such as the
SUN Wei;XU Chao;FU Hao;LIU Yusheng
doaj
Assessment of radiation exposure and public health before and after the operation of Sanmen nuclear power plant. [PDF]
Front Public Health, 2023 Ren H +14 more
europepmc +1 more source
First Experience with the Consolidation of WWER Reactor Pressure Vessel Knowledge through a New Method [PDF]
, 2008 One of today¿s activities of the Joint Research Centre¿s (JRC) Institute for Energy (IE) concerns data management and dissemination in nuclear safety. An ¿Online Data & Information Network¿ (ODIN) is set-up, which maintains one document database and four
BRUMOVSKY Milan +3 more
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, 2014 The paper presents an application of a variance decomposition method for the sensitivity analysis of the thermal hydraulic (TH) model of the Passive Containment Cooling System (PCCS) of an Advanced Pressurized Reactor (AP1000). The Loss Of Coolant Accident (LOCA) is considered as the most representative accident for identifying the Failure Damage ...
DI MAIO, FRANCESCO +3 more
openaire +2 more sources
Effects of porous superhydrophilic surfaces on flow boiling critical heat flux in IVR accident scenarios [PDF]
, 2015 Critical Heat Flux (CHF) plays a key role in nuclear reactor safety both during normal operation as well as in accident scenarios. In particular,when an in-vessel retention (IVR) strategy is used as a severe accident management strategy, the reactor ...
Atkhen, Kresna +3 more
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