Nuclear characteristics of epoxy resin as a space environment neutron shielding
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R. Adeli
Abstract
In recent years many investigations have been done for choosing applicable light neutron shielding in space environmental applications. In this study, we have considered the neutron radiation-protective characteristics of neat epoxy resin, a thermoplastic polymer material and have compared it with various candidate materials in neutron radiation protection such as Al 6061 alloy and Polyethylene. The aim of this investigation is the effect of type of moderator for fast neutron, notwithstanding neutron absorbers fillers. The nuclear interactions and the effective dose at shields have been studied with the Monte Carlo N-Particle transport code (MCNP), using variance reductions to reduce the relative error. Among the candidates, polymer matrix showed a better performance in attenuating fast neutrons and caused a lower neutron and secondary photon effective dose.
Kurzfassung
In den vergangenen Jahren wurden viele Untersuchungen durchgeführt in Bezug auf geeignete leichte Materialien zur Neutronenabschirmung im Weltraum. In der vorliegenden Studie wurden die Schutzeigenschaften von Epoxidharz, einem thermoplastischen Kunststoffmaterial, in Bezug auf Neutronen untersucht und verglichen mit verschiedenen anderen in Frage kommenden Materialien wie z. B. die Aluminiumlegierung AW-6061 und Polyäthylen. Die Kernwechselwirkungen und die effektive Dosis an den Abschirmungen wurden mit Hilfe des Monte-Carlo-Neutronentransport-Codes (MCNP) untersucht, unter Anwendung von Varianzreduktionen zur Effizienzsteigerung der Simulation. Unter den in Frage kommenden Materialien zeigt die Polymermatrix ein besseres Verhalten bei der Schwächung der Neutronen und führte zu einer niedrigeren effektiven Dosis durch Neutronen und Sekundärphotonen.
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© 2017, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- CANDU pressure tube leak detection by annulus gas dew point measurement: a critical review
- Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant
- 10.3139/124.110675
- Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor
- Simulation of protected and unprotected loss of flow transients in a WWER-1000 reactor based on the Drift-Flux Model
- Sensitivity analysis for CORSOR models simulating fission product release in LOFT-LP-FP-2 severe accident experiment
- Analysis of the optimal fuel composition for the Indonesian experimental power reactor
- Radiogenic lead from poly-metallic thorium ores as a valuable material for advanced nuclear facilities
- The effects of applying silicon carbide coating on core reactivity of pebble-bed HTR in water ingress accident
- Font Attributes based Text Steganographic algorithm (FATS) for communicating images: A nuclear power plant perspective
- Size control synthesis and characterization of ZnO nanoparticles and its application as ZnO-water based nanofluid in heat transfer enhancement in light water nuclear reactor
- Nuclear characteristics of epoxy resin as a space environment neutron shielding
- Exact solution of the neutron transport equation in spherical geometry
- Technical Notes/Technische Mitteilungen
- Determination of self-attenuation correction factor for lichen samples by using gamma-ray spectrometry
