Results 61 to 70 of about 668 (181)

Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors

open access: yesInternational 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   +4 more
wiley   +1 more source

Dynamic Analysis of Emergency Reset of Topaz Type Space Nuclear Reactor Safety Rod

open access: yesYuanzineng kexue jishu
The safety rod system is the actuator for reactivity control and nuclear safety protection in Topaz type space nuclear reactors. Due to the uneven distribution of reactor core temperature field during the operation of a Topaz type space nuclear reactor ...
LI Jingwei, LIU Shihang, ZHANG Guanhua, YAO Chengzhi, PENG Zhaohui, GUO Zhijia
doaj   +1 more source

Assessment of Different Turbulence Models on Melt Pool Natural Convection Simulations With Internal Heat Source

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
In the context of severe nuclear accidents, the migration of corium into the reactor pressure vessel (RPV) poses significant hazards, prompting the proposal of the in‐vessel melt retention (IVR) strategy, particularly the external reactor vessel cooling (ERVC) approach.
Pengya Guo   +6 more
wiley   +1 more source

SUBCHANNEL ANALYSIS OF LARGE POWER PWR ICONE22-30428 [PDF]

open access: yes, 2020
Researches of steady-state thermal hydraulic performance of a large power PWR had been made using the COBRA III C/MIT-2 code. The basic thermal hydraulic parameters and characteristics of the core channels were studied.
Fei Xie
core  

Geometrical optimization of PWR spacer grids using GeN-Foam and Genetic Algorithms

open access: yesBrazilian Journal of Radiation Sciences
This paper presents the results of Computational Fluid Dynamics (CFD) oriented geometrical optimization using the GeN-Foam solver applied to subchannels of the fuel assembly in a PWR-type nuclear reactor.
Carlos Rodrigo Dias   +8 more
doaj   +1 more source

ACOUSTIC MODELING AND PREVENTION OF VIBROACOUSTIC RESONANCES IN THE PRIMARY CIRCUIT OF NUCLEAR POWER PLANTS WITH WWER-1200 REACTORS

open access: yesНадежность и качество сложных систем
Background. The commissioning of new nuclear power plants with WWER-1200 water-water energetic reactors, including the Akkuyu Nuclear Power Plant, requires a high level of operational safety and seismic resistance.
Konstantin N. Proskuryakov   +2 more
doaj   +1 more source

Nuclear power plants: structure and function [PDF]

open access: yes, 1983
Topics discussed include: steam electric plants; BWR type reactors; PWR type reactors; thermal efficiency of light water reactors; other types of nuclear power plants; the fission process and nuclear fuel; fission products and reactor afterheat; and ...
Hendrie, J. M.
core  

Load control of the point model of a PWR-type nuclear reactor using a tuned controller with the DE algorithm

open access: yesمجله علوم و فنون هسته‌ای, 2023
The load control of a nuclear reactor is important due to the nonlinear nature of its dynamics and the dependence of some parameters on the output power. the Proportional-Integral-Derivative controller (PID) is commonly regarded as an easy choice for reliable control.
openaire   +1 more source

Swelling Characteristics of a Type 304SS Baffle Plate Irradiated up to 50 DPA in PWR and Validation of a Swelling Equation [PDF]

open access: yes, 2017
When austenitic stainless steel is highly irradiated in a reactor under high temperature, voids will be created in the material, leading to volumetric expansion of structures. This phenomenon is known as void swelling.
Yuichi Mogami   +4 more
core   +1 more source

DESAIN KONSEPTUAL BEJANA TEKAN REAKTOR PLTN TIPE PWR MODEL IPR1000 [PDF]

open access: yes, 2013
A CONCEPTUAL DESIGN OF REACTOR PRESSURE VESSEL FOR NPP PWR TYPE IPR 1000 MODEL. A conceptual design of reactor pressure vessel as one of the main components in nuclear power plants has been performed.
Pongtuluran, Mairing Manutu
core  

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