Results 51 to 60 of about 4,383 (200)

NNSA / IAEA VVER reactor safety workshops. May 2002 - April 2003. Executive summary. [PDF]

, 2003
Over the past year, the U.S. National Nuclear Security Administration (NNSA) has sponsored four workshops to compare the probabilistic risk assessments (PRAs) of Soviet-designed VVER power plants.
Petri, M. C., Evans, M.
core   +1 more source

Development of a three-dimensional model of the vver-1000 reactor using serpent monte carlo code for neutron-physical modeling

Trudy Odesskogo Politehničeskogo Universiteta, 2019
The VVER reactor investigation is an important goal for Ukrainian nuclear energy. Different deterministic and stochastic codes are using for this purpose.
Володимир Іванович Гулік, Віталій Володимирович Гальченко, Ігор Ігоревич Шлапак, Дмитро Володимирович Будік   +3 more
doaj   +5 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

Assessing the Performance of Point and Two‐Point Kinetics Models in Simulating the Control Rod Drop Accident in VVER‐1000 Reactors

International Journal of Energy Research, Volume 2025, Issue 1, 2025.
Reactivity‐initiated accidents (RIAs), such as the control rod drop accident (CRDA), are classified as design‐basis accidents (DBAs) in the final safety analysis report (FSAR) of a nuclear power plant (NPP), and investigating these events is crucial.
Seyed Mohammad Hossein Mousakazemi, Rajashik Paul   +1 more
wiley   +1 more source

CFD analysis of coolant mixing in VVER-1000/V320 reactor pressure vessel [PDF]

This study presents a code-to-code and model-to-model comparison of coolant mixing in the VVER-1000/V320 Kozloduy Unit 6 nuclear power plant using Computational Fluid Dynamics (CFD).
Pucciarelli, Andreas, Nop, R, Bourcier, C, Hashymov, A, Böttcher, M, Halim, Ossama, Belaunde, François, Forgione, Nicola, Sanchez, Victor, Böttcher, Michael, Nop, Raksmy, Sanchez, V, Mas, Alexandre, Halim, O, Bourcier, Christophe, Forgione, N, Bernard, Olivier, Ruban, D, Bernard, O, Mas, A, Belaunde, F, Pucciarelli, A   +21 more
core   +1 more source

Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
Nuclear reactors are subject to strict safety standards due to the critical nature of operational safety. Detecting transients as fast and accurately as possible is essential to reactor safety especially to reduce the human error of operators. In order to enhance this process, artificial intelligence (AI) offers strong opportunities.
Ceyhun Yavuz, Senem Şentürk Lüle, Han Zhang   +2 more
wiley   +1 more source

Investigation of functionals of neutron flux influencing onto VVER-440 reactor pressure vessel [PDF]

Ядерна фізика та енергетика, 2008
The calculational procedure for determination of irradiation conditions of VVER-440 reactor internals is presented. Using the developed procedure, irradiation conditions of Rovno NPP Unit1&2 VVER-440 reactor internals – baffle, basket and barrel – are ...
S. M. Pugach, O. V. Grytsenko, V. L. Diemokhin, V. N. Bukanov   +3 more
doaj  

Development of Emergency Planning Zones for Ghana’s Proposed Nuclear Plant Based on Radioactivity Releases From Hypothetical Accident Scenarios

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
Emergency planning zones (EPZs) for Ghana’s potential reactor site have been determined based on an assessment of atmospheric dispersion and dose calculations for multiple accident scenarios involving a VVER‐1200 reactor. The analysis was performed using the Radiological Assessment System for Consequence Analysis (RASCAL) 4.3.4 code to calculate doses ...
Alberta Blay, Sylvester Attakorah-Birikorang, Esi Awuah, Manish Sharma   +3 more
wiley   +1 more source

Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project

, 2021
CAMIVVER (Codes And Methods Improvements for VVER comprehensive safety assessment) is a three years project launched under the European Union research program HORIZON 2020.
Paci, S., Willien, A., Bieder, Ulrich, Groudev, P., Denis Verrier, Pietro Mosca, Barbara Calgaro, Vezzoni, Barbara, Antoaneta Stefanova, Mercatali, L., Sanchez-Espinoza, V. H., Nicolas Dos Santos, Tomatis, Daniele, Sanchez-Espinoza, Victor Hugo, Artur Hashymov, Ulrich Bieder, Bieder, U., Alberto Previti, Adrien Willien, Lafaurie, C., Mosca, P., Groudev, Pavlin, Dos Santos, Nicolas, Pavlin Groudev, Sandro Paci, Verrier, D., Stefanova, A., Nicola Forgione, Zaharieva, Neli, Neli Zaharieva, Barbara Vezzoni, Mercatali, Luigi, Mosca, Pietro, Zaharieva, N., Bernard, O., Stefanova, Antoaneta, Vezzoni, B., Luigi Mercatali, Victor Hugo Sanchez-Espinoza, Paci, Sandro, Forgione, Nicola, Clément Lafaurie, Forgione, N., Daniele Tomatis, Damian, Frédéric, Olivier Bernard, Calgaro, Barbara, Previti, A., Damian, F., Dos Santos, N., Previti, Alberto, Tomatis, D., Hashymov, A., Hashymov, Artur, Bernard, Olivier, Frédéric Damian, Lafaurie, Clément, Calgaro, B., Verrier, Denis, Willien, Adrien   +59 more
core   +1 more source

Improved Heat Transfer Capabilities of Nanofluids—An Assessment Through CFD Analysis

Chemical Engineering &Technology, Volume 47, Issue 11, November 2024.
Conventional fluids used in fission‐based water‐cooled nuclear reactors have lower heat transfer coefficients and thermal conductivity, prompting researchers to explore high‐performance fluids to enhance heat transfer and prevent core meltdown during accidents. It is crucial to investigate fluids that can improve thermal hydraulic characteristics, such
Rehan Zubair Khalid, Mehmood Iqbal, Aitazaz Hassan, Syed Muhammad Haris, Atta Ullah   +4 more
wiley   +1 more source