Research Progress on Radiation Shielding Concrete

Jun, Yang; Chen, Zhen Fu; Gan, Yuanchu; Tao, Qiu Wang

doi:10.4028/www.scientific.net/amm.253-255.303

Cited by 4 publications

(4 citation statements)

References 28 publications

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“…It has been reported in the literature that lithium-containing and boron-containing compounds are excellent thermal neutron absorbing materials. Example compounds include LiF, lithium bromide, lithium hydroxide, boron oxide, boric acid, and boron carbide [4]. The lithium content of LiF (27%) is much higher than in similar compounds and the boron content of B 4 C (78%) is much higher than in other boron-containing compounds.…”

Section: Resultsmentioning

confidence: 99%

Preparation of an Ultra-Thin, Highly Filled, Neutron-Shielding Material

Hou

Li²,

Chen³

et al. 2015

MSF

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We develop an ultra-thin, highly filled, neutron-shielding material. This material exhibits a desirable neutron-shielding performance, and also has certain advantageous mechanical properties and uses. We study the physical properties of shielding materials with different polyolefins as base materials, and investigate the neutron-shielding performance of boron-containing and lithium-containing shielding materials. We furthermore report on the effect of additive amounts of functional additives on shielding properties and physical-chemical properties. We additionally study the effect of radiation crosslinking technology on shielding material properties. We show that, using ethylene-octene copolymer (POE) modified low-density polyethylene (PE-LD), the additive amounts of boron carbide (B4C) and nano-montmorillonite (OMMT) are 60–70% and 4%, respectively. The optimal radiation dose is 160 kGy, and the shielding materials exhibit good neutron-shielding performance and mechanical strength.

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Section: Resultsmentioning

confidence: 99%

Preparation of an Ultra-Thin, Highly Filled, Neutron-Shielding Material

Hou

Li²,

Chen³

et al. 2015

MSF

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“…Pozzolanic reaction does not occur until later, the early strength of concrete is reduced, with a corresponding reduction in heat of hydration. Research on properties of RSC with different aggregates or admixtures and the effect of high temperature on the performance of shielding concrete are introduced [23]. Ice was introduced for mixing RSC to reduce hydration temperature.…”

Section: Key Engineering Materials Vol 705mentioning

confidence: 99%

Optimization of Radiation Shielding Concrete for Radiotherapy Treatment Room at Bangabandhu Sheikh Mujib Medical University

Sarker

Biswas

Rahman

et al. 2016

KEM

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The objective of this study is to recommend optimized shield design from the shielding viewpoint for installation of the Cyclotron,Cyberknife and Linear Acceleration (LINAC) facility at Bangabandhu Sheikh Mujib Medical University (BSMMU) in Dhaka, Bangladesh. The shield design for Cyclotron, Cyberknife and LINAC has been performed considering ICRP-103 (2007) recommendations for occupational and public dose limits. The optimized design parameters for Radiation Shielding Concrete (RSC) with hardened density of 2.35 gm/cm3 are: 254 cm thickness of RSC as primary barrier for LINAC on both side of the source, 198 cm and 178 cm thickness of RSC on parking side and earthen side wall for Cyclotron, a maze wall of thickness 198 cm and 122 cmRSC for Cyclotron and LINAC, 168 cm and 152 cm thickness of RSC from opposite to the maze wall, slab thickness 152 cm excluding a false ceiling of thickness 122 cm with RSC having a functional story height of 503 cm for LINAC, 122 cm and 259 cm slab thickness of RSC for Cyberknife and Cyclotron. The use of RSC in the shield design of wall and roof shows that it limits radiation exposure of staff, patients, visitors and the public to acceptable level, thus optimizing radiation protection.

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“…In the process of nuclear fission, reactor may produce various radiation rays, including particle α and β, X-ray and γ-ray, as well as neutrons of various energies. Therefore, nuclear reactor shielding (Lacey, 2021;Wang et al, 2021;Zeng and Li, 2013) shall be a key method to ensure nuclear energy safety. In practice, people also put forward higher requirements for other properties of shielding materials in addition to shielding performance.…”

Section: Introductionmentioning

confidence: 99%

An improved TOPSIS-ANP composite shielding material performance evaluation method based on gray relational projection algorithm

et al. 2023

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The performance of shielding materials directly affects the radiation protection effect and plays a very important role in the process of ensuring the safety of nuclear energy. Therefore, this paper introduces the performance evaluation of composite shielding materials, which firstly points out the disadvantages of the traditional TOPSIS method, proposes a weighted projection model of composite shielding materials under extended TOPSIS theory, and clarifies the principle of projection dimensional reduction and algorithm implementation. Secondly, this paper also introduces the basic assumption of non-linear mapping relationship between index dimensions, and scientifically determines the weight of index system based on ANP structural model, so as to form an improved TOPSIS-ANP composite shielding material performance evaluation method based on gray relational projection algorithm with coupling characteristics. The empirical results show that the improved TOPSIS-ANP composite shielding material evaluation method proposed in this paper is consistent with the conclusion of the ratio of lead-boron-polyethylene shielding materials optimized based on genetic algorithm, which proves the effectiveness of the evaluation method proposed in this paper. Meanwhile, the evaluation index system of this method is more comprehensive, and the evaluation method is more efficient and scientific as well, which has a good promotion prospects and application advantages.

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Research Progress on Radiation Shielding Concrete

Cited by 4 publications

References 28 publications

Preparation of an Ultra-Thin, Highly Filled, Neutron-Shielding Material

Preparation of an Ultra-Thin, Highly Filled, Neutron-Shielding Material

Optimization of Radiation Shielding Concrete for Radiotherapy Treatment Room at Bangabandhu Sheikh Mujib Medical University

An improved TOPSIS-ANP composite shielding material performance evaluation method based on gray relational projection algorithm

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