Exploring innovative radiation shielding approaches in space: A material and design study for a wearable radiation protection spacesuit

2017 ◽  
Vol 15 ◽  
pp. 69-78 ◽  
Author(s):  
M. Vuolo ◽  
G. Baiocco ◽  
S. Barbieri ◽  
L. Bocchini ◽  
M. Giraudo ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Radiation Shielding ◽  
Design Study

scholarly journals Are Further Cross Section Measurements Necessary for Space Radiation Protection or Ion Therapy Applications? Helium Projectiles

2020 ◽  
Vol 8 ◽  
Author(s):  
John W. Norbury ◽  
Giuseppe Battistoni ◽  
Judith Besuglow ◽  
Luca Bocchini ◽  
Daria Boscolo ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Cross Section ◽  
Cross Sections ◽  
Nuclear Reactions ◽  
Production Cross ◽  
Cosmic Ray ◽  
Space Radiation ◽  
Radiation Shielding ◽  
Light Ions ◽  
Ion Therapy

The helium (4He) component of the primary particles in the galactic cosmic ray spectrum makes significant contributions to the total astronaut radiation exposure. 4He ions are also desirable for direct applications in ion therapy. They contribute smaller projectile fragmentation than carbon (12C) ions and smaller lateral beam spreading than protons. Space radiation protection and ion therapy applications need reliable nuclear reaction models and transport codes for energetic particles in matter. Neutrons and light ions (1H, 2H, 3H, 3He, and 4He) are the most important secondary particles produced in space radiation and ion therapy nuclear reactions; these particles penetrate deeply and make large contributions to dose equivalent. Since neutrons and light ions may scatter at large angles, double differential cross sections are required by transport codes that propagate radiation fields through radiation shielding and human tissue. This work will review the importance of 4He projectiles to space radiation and ion therapy, and outline the present status of neutron and light ion production cross section measurements and modeling, with recommendations for future needs.

The Radiation Protection Design of PWR Spent Fuel Dry Storage Facility

2018 ◽  
Author(s):  
Liming Huang ◽  
Shouhai Yang ◽  
Jie Liu
Keyword(s):  
Radiation Protection ◽  
Nuclear Power ◽  
Radiation Safety ◽  
Three Dimensional ◽  
Radiation Shielding ◽  
Storage Facility ◽  
Spent Fuel ◽  
Dry Storage ◽  
Spent Fuel Storage ◽  
Fuel Storage

Radiation safety is an important part of safety assessment of spent fuel dry storage technology. This paper describes the radiation protection design of PWR spent fuel dry storage facility for radiation safety completed by China General Nuclear Power Corporation. Considering the special site conditions, Monte Carlo method is used to complete the precise calculation of the three-dimensional radiation dose field in the spent fuel storage building. Through the spent fuel storage module and the storage building with shielding function, radiation shielding design is completed to meet China’s regulatory requirements, which ensures radiation safety for workers and the public during the transport and storage of spent fuel. It will provide a reference for construction of spent fuel dry storage facility of CPR1000 and HPR1000.

scholarly journals Radiation protection, radiation safety and radiation shielding assessment of HIE-ISOLDE

2013 ◽  
Vol 155 (3) ◽  
pp. 351-363 ◽  
Author(s):  
Y. Romanets ◽  
A. P. Bernardes ◽  
A. Dorsival ◽  
I. F. Goncalves ◽  
Y. Kadi ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Radiation Safety ◽  
Radiation Shielding

Radiation protection

2018 ◽  
Author(s):  
Jim Hughes
Keyword(s):  
Radiation Exposure ◽  
Radiation Protection ◽  
Plain Film ◽  
Radiation Shielding ◽  
Surgical Team ◽  
Surgical Interventions ◽  
Positive Identification ◽  
Radiation Scatter ◽  
Beam Collimation

The basics of radiation protection in theatre for the patient follow principles similar to those used in plain-film imaging. These include ensuring positive identification of the patient, justification of radiation exposure, avoiding irradiation of pregnant patients wherever possible, minimization and optimization of exposures performed (ALARP principle), protection of all staff involved, and recording and monitoring of all exposures performed. This chapter covers the aspects of protection from radiation for the patient, surgical team, and the radiographer when performing imaging during surgical interventions. Topics covered include the use of beam collimation, minimizing exposure to the patient and team, radiation scatter, and the use and requirements of radiation shielding such as lead aprons and barriers.

scholarly journals Tailoring bismuth borate glasses by incorporating PbO/GeO2 for protection against nuclear radiation

2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Ashok Kumar ◽  
Anisha Jain ◽  
M. I. Sayyed ◽  
Farah Laariedh ◽  
K. A. Mahmoud ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Photon Energy ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Neutron Shielding ◽  
Bismuth Borate ◽  
Removal Cross Section ◽  
Buildup Factors

AbstractNuclear radiation shielding capabilities for a glass series 20Bi2O3 − xPbO − (80 − 2x)B2O3 − xGeO2 (where x = 5, 10, 20, and 30 mol%) have been investigated using the Phy-X/PSD software and Monte Carlo N-Particle transport code. The mass attenuation coefficients (μm) of selected samples have been estimated through XCOM dependent Phy-X/PSD program and MCNP-5 code in the photon-energy range 0.015–15 MeV. So obtained μm values are used to calculate other γ-ray shielding parameters such as half-value layer (HVL), mean-free-path (MFP), etc. The calculated μm values were found to be 71.20 cm2/g, 76.03 cm2/g, 84.24 cm2/g, and 90.94 cm2/g for four glasses S1 to S4, respectively. The effective atomic number (Zeff)values vary between 69.87 and 17.11 for S1 or 75.66 and 29.11 for S4 over 0.05–15 MeV of photon-energy. Sample S4, which has a larger PbO/GeO2 of 30 mol% in the bismuth-borate glass, possesses the lowest MFP and HVL, providing higher radiation protection efficiency compared to all other combinations. It shows outperformance while compared the calculated parameters (HVL and MFP) with the commercial shielding glasses, different alloys, polymers, standard shielding concretes, and ceramics. Geometric Progression (G-P) was applied for evaluating the energy absorption and exposure buildup factors at energies 0.015–15 MeV with penetration depths up to 40 mfp. The buildup factors showed dependence on the MFP and photon-energy as well. The studied samples' neutron shielding behavior was also evaluated by calculating the fast neutron removal cross-section (ΣR), i.e. found to be 0.139 cm−1 for S1, 0.133 cm−1 for S2, 0.128 cm−1 for S3, and 0.12 cm−1 for S4. The results reveal a great potential for using a glass composite sample S4 in radiation protection applications.

scholarly journals Investigation of Novel Composite Material Based on Extra-Heavy Concrete and Basalt Fiber for Gamma Radiation Protection Properties

2018 ◽  
pp. 52-58 ◽  
Author(s):  
І. Romanenko ◽  
M. Holiuk ◽  
A. Nosovsky ◽  
V. Hulik
Keyword(s):  
Composite Material ◽  
Gamma Radiation ◽  
Electron Density ◽  
Radiation Protection ◽  
Atomic Number ◽  
Gamma Ray ◽  
Basalt Fiber ◽  
Effective Atomic Number ◽  
Radiation Shielding ◽  
Effective Electron

The paper presents a new composite material for radiation protection based on extra-heavy concrete reinforced by basalt fiber. Basalt fiber is a new material for concrete reinforcement, which provides improved mechanical characteristics of concrete, reduces the level of microcracks and increases the durability of concrete. Within the scope of present work, the gamma-ray radiation protection properties of concrete reinforced with basalt fiber was modeled. Two types of extra-heavy concrete were used for this paper. The main gamma-ray attenuation coefficients such as mean atomic number, mean atomic mass, mean electron density, effective atomic number, effective electron density, Murty effective atomic number were analyzed with help of WinXCom software. It has been shown that the addition of basalt fiber to concrete does not impair its gamma-ray radiation shielding properties. With increasing the basalt fiber dosage in concrete, the radiation properties against gamma radiation are improved. This research was carried out with the financial support of the IAEA, within the terms and conditions of the Research Contract 20638 in the framework of the Coordinated Research Project (CRP) “Accelerator Driven Systems (ADS) Applications and use of Low-Enriched Uranium in ADS (T33002)” within the project “The Two-Zone Subcritical Systems with Fast and Thermal Neutron Spectra for Transmutation of Minor Actinides and Long-Lived Fission Products”.

Design Analysis of Radiation Shielding Door in High-Level Waste Treatment Plant

2021 ◽  
Author(s):  
Jingyi Shen ◽  
Zonghuan Chen ◽  
Bingheng Wang ◽  
Guiling Gao
Keyword(s):  
Dose Rate ◽  
Radiation Protection ◽  
Waste Treatment ◽  
Treatment Plant ◽  
Lap Joints ◽  
Radiation Shielding ◽  
High Level Waste ◽  
Waste Treatment Plant ◽  
Radioactive Sources ◽  
High Level

Abstract In high-level waste treatment plants, rooms where the highly radioactive sources (such as the vitrification containers) are operated have high radiation protection risk. On the purpose of ensuring the safety of operators, it is necessary to design corresponding shielding walls, windows and shielding doors to guarantee that the dose rate at the personal operating location outside the room meets corresponding control requirements. Compared with walls, the radiation safety designs of the doors and windows are more complicated. In this article, a shielding door of a hot room inside a high-level waste treatment plant is selected. By means of combing the source characteristics and the source location, the gap between the door and door frame as well as the lap joints of the door and the wall are analyzed in order to characterize the influence factor of the dose rate outside the shielding door. The results illustrate that, under the premise that the shielding design requirements are satisfied, the lap joint between shielding wall and door has a significant impact on the outdoor dose field due to the oblique incidence of the radiation ray. Therefore, in the follow-up design of the radiation shielding door, A certain overlap form of the lap joints between the door and the wall need to be satisfied, furthermore, special attention need to be paid to the shielding of radioactive sources with weak self-shielding effect and strong penetration ability, for ensuring the shielding door to the greatest extent radiation protection ability.

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