Results 21 to 30 of about 21,036 (237)

Clinical significance of Platelet-to-White Blood Cell Ratio (PWR) and National Institute of Health Stroke Scale (NIHSS) in acute ischemic stroke

open access: yesHeliyon, 2020
Introduction: Ischemic stroke can occur due to disruption of blood and oxygen supply to brain tissue. White blood cells and platelets play an important role in the pathogenesis of ischemic stroke.
Lisda Amalia, Nadjwa Zamalek Dalimonthe
doaj   +1 more source

Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water [PDF]

open access: yes, 2012
The corrosion behavior of 304L grade stainless steel (SS) in high-temperature steam and in a simulated Pressurized Water Reactor (PWR) is studied. The goal was to characterize the nature of the oxide coating generated during 500 h exposure of samples in ...
Cissé, Sarata   +4 more
core   +1 more source

SERPENT2-SUBCHANFLOW-TRANSURANUS PIN-BY-PIN DEPLETION CALCULATIONS FOR A PWR FUEL ASSEMBLY [PDF]

open access: yesEPJ Web of Conferences, 2021
This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOW-TRANSURANUS.
García Manuel   +10 more
doaj   +1 more source

Comportamiento del acero de baja aleación SA-508 y del acero al carbono A-410b en las condiciones de operación y parada del circuito primario de los reactores de agua ligera tipo PWR

open access: yesRevista de Metalurgia, 2000
En este trabajo se ha determinado la cinética de corrosión del acero de baja aleación SA-508 y del acero al carbono A-410b en condiciones que simulan la operación y la parada de los reactores de agua ligera a presión.
María del Sol García-Redondo   +2 more
doaj   +1 more source

VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS [PDF]

open access: yesEPJ Web of Conferences, 2021
The WIMS (Winfrith Improved Multigroup Scheme) reactor physics code is actively being developed for whole core modelling of a range of Small Modular Reactor types including the Pressurized Water Reactor (PWR), High Temperature Reactor (HTR), and Liquid ...
Smith Peter   +8 more
doaj   +1 more source

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

WRAP-PWR verification studies [PDF]

open access: yes, 1980
A modular computational system known as the Water Reactor Analysis Package - Evaluation Model (WRAP-EM) was developed for the Nuclear Regulatory Commission (NRC) to interpret and evaluate reactor vendor EM methods and computed results.
Ames, P L   +4 more
core   +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

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