Results 41 to 50 of about 17,249 (229)

Macroscopic cross section generation with WIMS-ANL for a PWR

open access: yesBrazilian Journal of Radiation Sciences, 2022
Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), it presents a model for obtaining ...
Wilmer Aruquipa Coloma   +3 more
doaj   +1 more source

METHODOLOGY FOR HIGH-FIDELITY DETERMINISTIC MODELLING OF SWISS LWR FUEL ASSEMBLIES [PDF]

open access: yesEPJ Web of Conferences, 2021
The main goal of this work is to perform pin-by-pin calculations of Swiss LWR fuel assemblies with neutron transport deterministic methods. At Paul Scherrer Institut (PSI), LWR calculations are performed with the core management system CMSYS, which is ...
Bernal A.   +4 more
doaj   +1 more source

Severe Accidents Management in PWRs

open access: yesProcedia Engineering, 2014
AbstractThis paper identifies severe accident management strategies developed for current evolutionary reactors and deals with implementation of some measures to existing nuclear power plants, which do not include severe accident mitigation measures in their original design projects.
Rajzrová, Jana, Jiřičková, Jana
openaire   +1 more source

Analysis of Possible Application of High-Temperature Nuclear Reactors to Contemporary Large-Output Steam Power Plants on Ships

open access: yesPolish Maritime Research, 2016
This paper is aimed at analysis of possible application of helium to cooling high-temperature nuclear reactor to be used for generating steam in contemporary ship steam-turbine power plants of a large output with taking into account in particular ...
Kowalczyk T., Głuch J., Ziółkowski P.
doaj   +1 more source

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

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.
S.M.H. Mousakazemi
doaj   +1 more source

Efficiency Upgrade in PWRs

open access: yesEnergy and Power Engineering, 2011
Most of the light water reactor power plants now operating or under construction use pressurized-water reactor (PWR). They are suffering of relatively low thermal efficiency which is around 33%. This would not only have a negative impact economically but also incurs environmental burden in terms of thermal pollution. In this paper, nuclear steam supply
Morteza Gharib   +2 more
openaire   +2 more sources

Analysis of critical heat flux under vertical subcooled flow boiling condition (Development and evaluation for prediction method of DNB heat flux under non-uniform axial heat flux condition)

open access: yesNihon Kikai Gakkai ronbunshu, 2014
From the viewpoint of safety design of nuclear reactor and economic terms, for PWR, it is important to clear the mechanism of DNB and predict accurately the critical heat flux under vertical subcooled flow boiling condition.
Mitsuru YAMADA, Shinichi MOROOKA
doaj   +1 more source

The Practical Use of White Cell Inflammatory Biomarkers in Prediction of Postoperative Delirium after Cardiac Surgery

open access: yesBrain Sciences, 2019
: Introduction: Postoperative delirium (POD) is associated with unfavorable outcomes. It may result from neuroinflammation and oxidative stress. The aim of this study was to evaluate the role of routinely available inflammatory markers derived from white
Katarzyna Kotfis   +4 more
doaj   +1 more source

HEXAGONAL PWR-CORE MODELING AND SIMULATION WITH APPLICATION OF NECP-BAMBOO [PDF]

open access: yesEPJ Web of Conferences, 2021
In this paper, the modeling and simulation of the PWRs loaded with hexagonal fuel assemblies has been implemented with the NECP-Bamboo code. NECP-Bamboo, consisting of a 2D lattice code named Bamboo-Lattice and a 3D steady-state core code named Bamboo ...
Zhang Cheng   +3 more
doaj   +1 more source

RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient

open access: yesMechanical Engineering Journal, 2014
RELAP5 code post-test analysis was performed on one of abnormal transient tests conducted with the ROSA/large scale test facility (LSTF) simulating a PWR station blackout (SBO) transient with the TMLB' scenario in 1995.
Takeshi TAKEDA, Hideo NAKAMURA
doaj   +1 more source

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