Neutron and gamma-ray transport calculations in support of the design of the radiation shielding for the TOFED neutron spectrometer at LHD

2021 ◽  
Vol 166 ◽  
pp. 112296
Author(s):  
S. Sangaroon ◽  
K. Ogawa ◽  
M. Isobe ◽  
M.I. Kobayashi ◽  
S. Conroy ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Radiation Shielding ◽  
Neutron Spectrometer

The MESSENGER Gamma-Ray and Neutron Spectrometer

2007 ◽  
Vol 131 (1-4) ◽  
pp. 339-391 ◽  
Author(s):  
John O. Goldsten ◽  
Edgar A. Rhodes ◽  
William V. Boynton ◽  
William C. Feldman ◽  
David J. Lawrence ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Neutron Spectrometer

scholarly journals Conceptual Shield Design for Boron Neutron Capture Therapy Facility Using Monte Carlo N-Particle Extended Simulator with Kartini Research Reactor as Neutron Source

2020 ◽  
Vol 35 (3) ◽  
pp. 177-181
Author(s):  
Afifah Hana Tsurayya ◽  
Azzam Zukhrofani Iman ◽  
R. Yosi Aprian Sari ◽  
Arief Fauzi ◽  
Gede Sutresna Wijaya
Keyword(s):  
Monte Carlo ◽  
Radiation Dose ◽  
Dose Rate ◽  
Neutron Source ◽  
Gamma Ray ◽  
Outer Part ◽  
Radiation Shielding ◽  
Radiation Dose Rate ◽  
Boron Neutron Capture ◽  
Radiation Workers

The research aims to measure the radiation dose rate over the radiation shielding which is made of paraffin and aluminium and to determine the best shield material for the safety of radiation workers. The examination used MCNP (Monte Carlo N-Particle) simulator to model the BNCT neutron source and the shield. The shield should reduce radiation to less than the dose limit of 10.42 µSv/h, which is assumed to be the most conservative limit when the duration of workers is 1920 h. The first design resulted in a radiation dose rate which was still greater than the limit. Therefore, optimization was done by adding the lead on the outer part of the shield. After optimization by adding the lead with certain layers, the radiation dose rate decreased, with the largest dose being 57.60 µSv/h. Some locations over the limit could be overcome by other radiation protection aspects such as distance and time. The paraffin blocks were covered by aluminium to keep the shield structure. The lead was used to absorb the gamma ray which resulted from the interaction between the neutrons and aluminium.

scholarly journals Gamma Ray and FTIR Studies in Zinc Doped Lead Borate Glasses for Radiation Shielding Application

2018 ◽  
Vol 22 (1) ◽  
Author(s):  
Zakiyyu Ibrahim Takai ◽  
Rajinder Singh Kaundal ◽  
Mohd Kamarulzaki Mustafa ◽  
Saliza Asman ◽  
Aisha Idris ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Radiation Shielding ◽  
Borate Glasses ◽  
Lead Borate ◽  
Lead Borate Glasses ◽  
Ftir Studies

The MESSENGER Gamma-Ray and Neutron Spectrometer

2007 ◽  
pp. 339-391
Author(s):  
John O. Goldsten ◽  
Edgar A. Rhodes ◽  
William V. Boynton ◽  
William C. Feldman ◽  
David J. Lawrence ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Neutron Spectrometer

scholarly journals Mechanical Properties and Gamma-Ray Shielding Performance of 3D-Printed Poly-Ether-Ether-Ketone/Tungsten Composites

Materials ◽  
2020 ◽  
Vol 13 (20) ◽  
pp. 4475
Author(s):  
Yin Wu ◽  
Yi Cao ◽  
Ying Wu ◽  
Dichen Li
Keyword(s):  
Composite Materials ◽  
Nuclear Energy ◽  
Gamma Ray ◽  
Radiation Shielding ◽  
Shielding Effect ◽  
Tungsten Content ◽  
Metal Composites ◽  
Ether Ether Ketone ◽  
Poly Ether Ether Ketone ◽  
Ether Ketone

Nuclear energy provides enduring power to space vehicles, but special attention should be paid to radiation shielding during the development and use of nuclear energy systems. In this paper, novel composite materials containing poly-ether-ether-ketone (PEEK) as a substrate and different tungsten contents as a reinforcing agent were developed and tested as shielding for gamma-ray radiation. Shielding test bodies were quickly processed by fused deposition modeling (FDM) 3D printing, and their mechanical, shielding properties of composite materials were evaluated. The results revealed shielding materials with excellent mechanical properties which can further be improved by heat treatment. Under 0.45 MPa load, the heat deflection temperature of PEEK/tungsten (metal) composites was significantly lower than that of PEEK/boron carbide (non-metal) composites. The new shielding materials also demonstrated better shielding of low-energy 137Cs than high-energy 60Co. The gamma-ray shielding rates of test pieces shielding materials made of the same thickness changed exponentially with the tungsten content present in the composite materials. More tungsten led to a better shielding effect. At the same tungsten content, the gamma-ray shielding effect showed a proportional relationship with the thickness of the shielding test bodies, in which thicker test bodies induced better shielding effects. In sum, the integration of 3D printing in the mechanical design and manufacturing of shielding bodies is an effective and promising way for quick processing when considering diverse rays and complex environments. Lighter shielding bodies, at lower costs, can be achieved by structural design in limited space to maximize the material utilization rate and reduce waste.

New high temperature resistant heavy concretes for fast neutron and gamma radiation shielding

2019 ◽  
Vol 107 (4) ◽  
pp. 359-367 ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Turgay Korkut ◽  
Mohammed Ibrahim Sayyed ◽  
Abdülhalik Karabulut
Keyword(s):  
High Temperature ◽  
Cross Sections ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Normal Weight ◽  
Radiation Shielding ◽  
Equivalent Dose Rate ◽  
Normal Weight Concrete ◽  
Geant4 Code

Abstract In the present work, we developed three new high temperature resistant heavy concretes as novel radiation shielding materials. For this purpose, chrome ore (FeCr2O4), hematite (Fe2O3), titanium oxide (TiO2), aluminum oxide (Al2O3), limonite [FeO (OH) nH2O], siderite (FeCO3), barite (BaSO4), nickel oxide (NiO) materials and alumina cement were used. Mass combination ratios of components and total macroscopic cross sections (scattering, absorption, capture, fission) of the samples were calculated by using GEANT4 code. The resistances of the prepared samples were evaluated in terms of compression strength after exposure at the 1000 °C temperature. Neutron equivalent dose rate measurements were carried out by using 4.5 MeV 241Am-Be neutron source and BF3 detector. All results were compared with normal weight concrete and paraffin. The results of neutron dose indicate that neutron absorption ability of the new heavy concretes is higher than normal weight concrete and paraffin. In addition to neutron measurements, different γ-ray shielding parameters such as mass attenuation coefficient (MAC), effective atom numbers (Zeff), half value layer (HVL) and mean free path (MFP) have been calculated using WinXCOM software in order to investigate the effectiveness of using the prepared concretes as a radiation shielding materials. Gamma-ray results were compared with concretes and Pb-based glass.

Effect of different size of PbWO4 particles on EPDM composite for gamma-ray shielding

2020 ◽  
Vol 34 (07) ◽  
pp. 2050046
Author(s):  
Jinghui Fan ◽  
Juying Wu ◽  
Yan Ma
Keyword(s):  
Gamma Rays ◽  
Gamma Ray ◽  
Mechanical Test ◽  
Radiation Shielding ◽  
Reinforced Composites ◽  
Sem Images ◽  
Elongation At Break ◽  
Roll Mill ◽  
The Matrix ◽  
Shielding Properties

Ethylene Propylene Diene Monomer (EPDM) composites filled with 0–400 phr [Formula: see text] (PWO) were prepared by conventional process using a two-roll mill. Surface treatment of the fillers coated with KH570 was conducted to enhance the wettability and lubrication of fillers in the polymer matrix. According to SEM images and mechanical test, both micro- and submicro-fillers disperse homogeneously in the matrix, and adhesion of submicro-fillers to the matrix is stronger than that of micro-fillers. The submicro-PWO composites had better tensile strength and elongation at break than those composites containing micro-PWO powder, but a relatively higher hardness. The photon shielding test was performed to determine the radiation shielding properties of these composites, which showed that attenuation of gamma-rays for the submicro-PWO composites was substantially enhanced compared to micro-PWO reinforced composites.

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