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Laser-heating and Radiance Spectrometry for the Study of Nuclear Materials in Conditions Simulating a Nuclear Power Plant Accident
Published on: December 14, 2017
EXPERIMENTAL EVALUATION OF NEUTRON SHIELDING MATERIALS.
X Campo1,2, R Méndez1, M A S Lacerda3
1esearch Centre for Energy, Environment and Technology, Av. Complutense 40, Madrid, Spain.
Radiation Protection Dosimetry
|October 17, 2017
Summary
A new Borotron UH050 and Al(OH)3 composite shows comparable neutron shielding to NS4FR but reduced gamma shielding. Higher thicknesses are needed to match NS4FR
Area of Science:
- Nuclear Engineering
- Materials Science
- Radiation Protection
Background:
- Developing advanced neutron shielding materials is crucial for nuclear applications.
- Borotron UH050 is a commercial neutron shielding material.
- Aluminum hydroxide (Al(OH)3) is investigated as an additive to enhance shielding properties.
Purpose of the Study:
- To evaluate a new neutron shielding material composed of Borotron UH050 with Al(OH)3.
- To compare its neutron and gamma shielding performance against the reference material NS4FR.
- To validate Monte Carlo simulation models using experimental dosimetry and spectrometry data.
Main Methods:
- Experimental measurements including neutron and gamma dosimetry and neutron spectrometry.
- Monte Carlo simulations for material modeling and analysis.
- Comparative assessment of shielding properties between the proposed and reference materials.
Main Results:
- The proposed Borotron UH050 + Al(OH)3 material exhibits negligible differences in neutron shielding compared to NS4FR.
- Significant differences were observed in gamma shielding, with the new material being less efficient.
- Addition of Al(OH)3 decreased neutron shielding but improved gamma shielding capabilities.
Conclusions:
- The new composite material is effective for neutron shielding, matching NS4FR performance.
- Enhanced gamma shielding requires approximately 20% greater thickness compared to NS4FR.
- Validated Monte Carlo models provide a reliable tool for further shielding material design.
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