Results 61 to 70 of about 4,383 (200)

Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor

open access: yesEPJ Web of Conferences, 2016
A set of benchmark experiments was carried out in the full scale VVER-1000 mock-up on the reactor LR-0 in order to validate neutron transport calculation methodologies and to perform the optimization of the shape and locations of neutron flux operation ...
Košťál Michal   +8 more
doaj   +1 more source

Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants

open access: yesEnergy Science &Engineering, Volume 12, Issue 11, Page 4894-4903, November 2024.
Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants. Abstract This study investigates the impact of hybrid nanoparticles on the temperature of nuclear reactor coolant, with a focus on graphene nanoplatelet (GNP)‐based hybrid nanoparticles. Sixteen different hybrid nanofluids were analyzed, and their
Sinem Uzun, Yasin Genç, Adem Acır
wiley   +1 more source

Investigating the 17 March 2013 Geomagnetic Storm Impacts on the Wholly Coupled Solar Wind‐Magnetosphere‐Ionosphere‐Thermosphere System‐Of‐Systems

open access: yesJournal of Geophysical Research: Space Physics, Volume 129, Issue 9, September 2024.
Abstract In this study, we investigate the impacts of the 17 March 2013 strong geomagnetic storm on the wholly coupled Solar Wind‐Magnetosphere‐Ionosphere‐Thermosphere system‐of‐systems. Obtained from multipoint observations, our new results show (1) the solar‐wind Alfven waves propagating antisunward in the sheath region and (2) oscillating solar wind
Ildiko Horvath, Brian C. Lovell
wiley   +1 more source

The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology

open access: yesEPJ Nuclear Sciences & Technologies, 2016
This paper shows basic features of different fuel assembly (FA) application for VVER-1000 in a closed fuel cycle based on REMIX-technology. This investigation shows how the change in the water–fuel ratio in the VVER FA affects on the fuel characteristics
Bobrov Evgenii   +4 more
doaj   +1 more source

Vertical Crustal Deformation Due To Viscoelastic Earthquake Cycles at Subduction Zones: Implications for Nankai and Cascadia

open access: yesJournal of Geophysical Research: Solid Earth, Volume 129, Issue 8, August 2024.
Abstract Despite significant progress in studying subduction earthquake cycles, the vertical deformation is still not well understood. Here, we use a generic viscoelastic earthquake‐cycle model that has recently been validated by horizontal observations to explore the dynamics of vertical earthquake‐cycle deformation.
Shaoyang Li, Ling Chen
wiley   +1 more source

PTS analysis methodology for VVER-1000 RPV by coupled codes

open access: yes, 2004
Reactor Pressure Vessel integrity is one of the main concerns related to license renewals and plant-life extension. A research activity is conducted at the “Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione” - University of Pisa to ...
Frustaci L.   +4 more
core  

Response of Soviet VVER-440 accident localization systems to overpressurization [PDF]

open access: yes, 1989
The Soviet designed VVER-440 model V230 and VVER-440 model V213 reactors do not use full containments to mitigate the effects of accidents. Instead, these VVER-440 units employ a sealed set of interconnected compartments, collectively called the accident
Kulak, R. F., Sienicki, J. J., Fiala, C.
core  

Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site

open access: yesScience and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.
The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
wiley   +1 more source

PSB-VVER QLR, Test 15

open access: yes, 2006
The EC- (European Commission) EURATOM TACIS project 30303 aims at safety evaluation of VVER-1000 (Russian Design, Gidropress, pressurized water reactor) and of RBMK (Russian design, NIKIET, boiling water cooled, graphite moderated nuclear reactor ...
Lysenkov E., D’Auria F., Bykov M.
core  

PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants

open access: yesScience and Technology of Nuclear Installations, 2012
The PMK-2 facility is a full-pressure thermal-hydraulic model of the primary and partly the secondary circuit of the VVER-type units of Paks NPP. The facility was the first integral-type facility for VVERs. The PMK-2 was followed later by the PACTEL (for
Gy. Ézsöl   +3 more
doaj   +1 more source

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