Results 31 to 40 of about 675,221 (193)

Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION

Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022
A typical 1100 MWe pressurized water reactor (PWR) is a second unit installed at the coastal site of Pakistan. In this paper, verification analysis of reactivity control worth by means of rod cluster control assemblies (RCCAs) for startup and operational conditions of this typical nuclear power plant (CNPP) has been performed.
Izza Shahid, Nadeem Shaukat, Amjad Ali, Meer Bacha, Ammar Ahmad, Muhammad Tariq Siddique, Rustam Khan, Sajjad Tahir, Zeeshan Jamil, Arkady Serikov   +9 more
wiley   +1 more source

Analysis of Hybrid Nanofluid Stagnation Point Flow over a Stretching Surface with Melting Heat Transfer

Mathematical Problems in Engineering, Volume 2022, Issue 1, 2022., 2022
The behavior of hybrid nanofluid and stagnation point flow toward a stretched surface along with melting heat transfer, second‐order slip, electric field, and magnetic field effect is investigated in this study. Hybrid nanoparticles alumina (Al2O3) and copper (Cu) are considered with the base fluids water (H2O).
Muhammad Jawad, Ziad Khan, Ebenezer Bonyah, Rashid Jan, Arshad Riaz   +4 more
wiley   +1 more source

Methodology for Establishing Segmentation Strategy for Large Metal Components from Nuclear Power Plants with Consideration of Packaging into Containers

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
A methodology for segmenting large metal components from nuclear power plants has been developed with a view to minimizing the number of containers to emplace segmented pieces. Spherocylinder‐type and rectangular prism‐type objects are modeled in shapes, and equations to calculate heights, widths, lengths, or angles for segmentation and the number of ...
Jae Min Lee, Jae Hak Cheong, Jooho Whang, Arkady Serikov   +3 more
wiley   +1 more source

Formation of proliferation-resistant nuclear fuel supplies based on reprocessed uranium for Russian nuclear technologies recipient countries

Nuclear Energy and Technology, 2015
The paper presents different strategies for the conversion of VVER-1000 reactors to reprocessed uranium fuel for estimating the time required to form a proliferation-resistant VVER-1000 fuel load based on uranium extracted from spent fuel of reactors of ...
M.I. Fedorov, A.I. Dyachenko, N.A. Balagurov, V.V. Artisyuk   +3 more
doaj   +1 more source

Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
An optimal long‐term electric power strategy for Saudi Arabia to adopt nuclear power was evaluated using the MESSAGE tool. Saudi Arabia is predicted to experience an electricity shortage by 2025 with the present energy system. This electricity shortage could be postponed until 2035 by rehabilitating the existing power plants. The MESSAGE model predicts
Shadwan M. M. Esmail, Jae Hak Cheong, Guglielmo Lomonaco   +2 more
wiley   +1 more source

3-D COUPLED SIMULATION OF A VVER 1000 WITH PARCS/ATHLET [PDF]

EPJ Web of Conferences, 2021
A new OECD/NEA benchmark entitled “Reactivity compensation with diluted boron by stepwise insertion of control rod cluster” is starting. This benchmark, based on high quality measurements performed at the NPP Rostov Unit 2, aims to validate and assess ...
Henry Romain, Périn Yann, Velkov Kiril, Nikonov Sergei Pavlovich   +3 more
doaj   +1 more source

Neutronic Performance of the VVER‐1000 Reactor Using Thorium Fuel with ENDF Library

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
In this paper, neutronic calculations and the core analysis of the VVER‐1000 reactor were performed using MCNP6 code together with both ENDF/B‐VII.1 and ENDF/B‐VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER‐1000 reactor was discussed.
Sonia M. Reda, Ibrahim M. Gomaa, Ibrahim I. Bashter, Esmat A. Amin, Arkady Serikov   +4 more
wiley   +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

Improving the accuracy of thermal power determination of VVER

Ядерна фізика та енергетика, 2019
In most algorithms for forming control signals, locks and protection of VVER, the value of the reactor’s thermal power (RTP) is used. This article is dedicated to the analysis of the problem of determining the RTP of VVER-1000.
V. I. Borysenko, D. V. Budyk, V. V. Goranchuk   +2 more
doaj   +1 more source

A study into the dependence of the cladding-fuel pellet gap conductance on burn-up and the effects on the reactor core neutronic performance [PDF]

Nuclear Energy and Technology, 2019
This paper presents the results of the research to study the dependence of the VVER-1000 (1200) cores neutronic characteristics on the cladding – fuel pellet gap conductance coefficient in the process of the fuel burn-up.
Sergey B. Vygovsky, Fedor V. Gruzdov, Rashdan T. Al Malkawi   +2 more
doaj   +3 more sources