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Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection
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M. Ashoor
Published/Copyright:
February 23, 2021
Abstract
The most important material for shielding is concrete in nuclear facilities which performance can be improved by addition some Nanoparticles (NP) at the various concentrations. Nanoparticles, which have a distinctive potential for bio-radiation and shielding of nuclear reactors, are used in many areas due to their special characteristics, which lead to an improvement in the mechanical properties and the pore structure of the concrete shield. The aim of this research was to initiate a novel coefficient (n), experiment to theory density ratio for integrated NP at different nanoparticle concentrations (xnano), established upon purely mathematical viewpoints and some appropriate physical objectives.
Online erschienen: 2021-02-23
Erschienen im Druck: 2020-01-01
© 2020 by Walter de Gruyter Berlin/Boston
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- CONTENTS
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Verification of the stationary module of the ShIPR software system for modelling experiments of the ASTRA HTGR type critical facility
- Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection
- Comparison of back propagation network and radial basis function network in Departure from Nucleate Boiling Ratio (DNBR) calculation
- Developing a futuristic multi-objective optimization of the fuel management problems for the nuclear research reactors
- Sensitivity of the neutron multiplication factor to water ingress into a spent fuel cask
- Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)
- Note · Imprint
Articles in the same Issue
- CONTENTS
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Verification of the stationary module of the ShIPR software system for modelling experiments of the ASTRA HTGR type critical facility
- Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection
- Comparison of back propagation network and radial basis function network in Departure from Nucleate Boiling Ratio (DNBR) calculation
- Developing a futuristic multi-objective optimization of the fuel management problems for the nuclear research reactors
- Sensitivity of the neutron multiplication factor to water ingress into a spent fuel cask
- Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)
- Note · Imprint
