Results 21 to 30 of about 3,636 (213)

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

Наближена оцінка температурного стану керамічного ядерного палива в циліндричних твелах та впливу на нього процесів і параметрів конструкцій активної зони реактора [PDF]

, 2008
The approximate mathematical model of the temperature state of ceramic nuclear fuels in cylindrical fuel elements was proposed in the form of linear ordinary differential equation and the boundary conditions. The theory of heat conduction and assumptions
Chibisov, Dmytro, Romashov, Yury
core   +2 more sources

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

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

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

LBLOCA accident investigation using TRACE code in a VVER-1000 reactor [PDF]

مجله علوم و فنون هسته‌ای, 2020
The loss of coolant accident is due to the reduction of the coolant fluid volume in the first circuit. The direct cause of this accident is the mechanical failure or fatigue in the material of the first circuit components during the power plant operation.
S. Ekbatani-Amlashi, O. Safarzadeh, A.S. Shirani   +2 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

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

Investigation of the impact of steady-state VVER-1000 (1200) core characteristics on the reactor stability with respect to xenon oscillations [PDF]

Nuclear Energy and Technology, 2020
The article presents a method for obtaining an analytical expression for the criterion of stability of a VVER-1000 (1200) reactor with respect to xenon oscillations of the local power in the core, containing an explicit dependence of the criterion ratio ...
Rashdan Talal Al Malkawi, Sergey B. Vygovsky, Osama Wasef Batayneh   +2 more
doaj   +3 more sources