Soviet exhibit of radiation shielding and protection equipment for handling radioactive materials

1963 ◽  
Vol 13 (6) ◽  
pp. 1246-1248
Author(s):  
S. B. ◽  
L. P.
Keyword(s):  
Radiation Shielding ◽  
Radioactive Materials

scholarly journals Accidental Drop of a Carbon Steel/Lead Shipping Cask at Low Temperatures

2007 ◽  
Author(s):  
Brian D. Hawkes ◽  
Kenneth R. Durstine
Keyword(s):  
Carbon Steel ◽  
Brittle Failure ◽  
Low Carbon Steel ◽  
Significant Loss ◽  
Radiation Shielding ◽  
The Body ◽  
Low Carbon ◽  
Radioactive Materials ◽  
Accident Scenarios ◽  
The Impact

A shielded cask is used to transport radioactive materials between facilities. The cask was fabricated with an outer and inner shell of hot rolled low carbon steel. Lead was poured in the annular space between the shells to provide radiation shielding. Carbon steel is known to be susceptible to low-temperature brittle fracture under impact loading. This paper will present the analysis results representing postulated transportation accidents during on-site transfers of the cask. The accident scenarios were based on a series of cask drops onto a rigid surface from a height of 6 ft assuming brittle failure of the cask shell at subzero temperatures. Finite element models of the cask and its contents were solved and post processed using ABAQUS software. Each model was examined for failure to contain radioactive materials and/or significant loss of radiation shielding. Results of these analyses show that the body of the cask exhibits considerable ruggedness and will remain largely intact after the impact. There will be deformation of the main cask body with localized brittle failure of the cask outer shell and components and but no complete penetration of the cask shielding. The cask payload outer waste can will experience some permanent plastic deformation in each drop, but will not be deformed to the point where it will rupture, thus maintaining confinement of the can contents.

scholarly journals Muography applications developed by IFIN-HH

2018 ◽  
Vol 377 (2137) ◽  
pp. 20180137 ◽  
Author(s):  
Bogdan Mitrica ◽  
Denis Stanca ◽  
Bogdan Cautisanu ◽  
Mihai Niculescu-Oglinzanu ◽  
Alexandru Balaceanu ◽  
...  
Keyword(s):  
Detection System ◽  
Cosmic Ray ◽  
Muon Flux ◽  
Radiation Shielding ◽  
Radioactive Materials ◽  
Mining Sites ◽  
Non Invasive ◽  
Cosmic Muon ◽  
New Directions ◽  
Flux Measurements

Cosmic-ray muons have been studied at IFIN-HH for more than 20 years. Starting as fundamental physics research, the muon flux measurements bring new directions of study regarding muography. Two new directions have been recently developed: underground muon scanning of old mining sites in order to detect the possible presence of unknown cavities and underwater scanning of ships in commercial harbours in order to prevent the illegal traffic of radioactive materials. The main goal of the first direction of study is to improve the security of underground civilian and industrial infrastructures, by starting the development of a new, innovative detection system that can be used to identify potentially dangerous conditions using a non-invasive, totally safe method. The method proposed uses information provided by a device placed underground that measures directional cosmic muon flux and identifies anomalies produced by irregularities in the geological layers above. For the second direction of study, the method proposed is based on the detection and analysis of the cosmic muon flux. The high-density materials (uranium, lead—used for radiation shielding, etc.) cause a decrease in the directional muon flux. The detection system will be submerged underneath the ship that will be scanned, being able to locate illegal radioactive materials without exposing any personnel to radiation or contamination. Correlated with simulations based on the known configuration of the ship scanned, the data provided by the detection system will provide the location and dimensions of the undeclared material transported. This article is part of the Theo Murphy meeting issue ‘Cosmic-ray muography’.

Research on Approval of Domestic and International Transport Container Application of Radioactive Material

2017 ◽  
Author(s):  
Wang Yue ◽  
Zhan Lechang ◽  
Ma Wenjuan ◽  
Zhang Yongxin ◽  
Ma Li
Keyword(s):  
Heat Dissipation ◽  
Competent Authority ◽  
Radiation Shielding ◽  
Radioactive Material ◽  
Civil Aviation ◽  
Radioactive Materials ◽  
Management Procedures ◽  
International Transport ◽  
Transport Safety ◽  
Administrative Licensing

Due to the potentially dangerous properties of radioactive material, it is during the transport that the process of nuclear energy and technology uses are prone to nuclear and radiation accidents. Radioactive material hence must be transported with reasonable containers to achieve heat dissipation, confinement of radioactive material, radiation shielding and prevention of nuclear criticality. The key to transport safety lies in the designing and manufacturing quality of the transport containers. Therefore, the safety supervision for transport containers of radioactive material is a guarantee for the environment and the public from nuclear and radiation hazards, also is international general practice. As the most authoritative international organization, International Atomic Energy Agenda (IAEA) draws up and regularly revises safety regulation ‘Regulation for the Safe Transport of Radioactive Material’, which proposes technical indicators for transport containers of radioactive material and responsibility of competent authorities. According to the transport modes, other international organizations, such as International Maritime Organization, International Civil Aviation Organization, International Air Transport Association, United Nations Economic Commission for Europe, enacted related transport safety regulations based on actual needs. This paper introduces the administrative licensing approval process for the transport containers of radioactive material in China and the research on competent authority and approval procedure in American, Russia, France, Canada, Germany and Great Britain. In China, National Nuclear Safe Administration (NNSA) is responsible for the licensing approval for the transport containers of radioactive material, including designing, manufacturing, using and transporting of transport containers. NNSA also organizes and formulates relevant administrative regulations and approval procedures, and has issued administrative regulation ‘Regulation on the Safe Management for the Transport of Radioactive Material’ and a series of administrative rules, management procedures, guide, technical documents and so on. These regulations established the sort management of radioactive materials and the responsibility for competent authority, and also stipulated approval and supervision for transport and transport containers of radioactive materials. While some other countries, such as America, certifies the transport containers of radioactive material to achieve the control. The domestic and overseas research into administrative licensing approval processes for transport containers is in view of the increasing transport of radioactive material among countries and the requirement of international transport. Transport containers with material of high potential risk, such as spent fuel, need to obtain the transport approval from the competent authority of transit or arrival country. Therefore, the research on domestic and other countries licensing management of transport containers of radioactive material, which is not only beneficial to improving the transport safety management of radioactive material in China, but also can promote international transport campaigns of radioactive material..

Discussion on “The Sir Alfred Herbert paper, 1953. The industrial applications of radioactive materials”

1953 ◽  
Vol 32 (10) ◽  
pp. 450
Author(s):  
F.E. Simon ◽  
John Cockcroft ◽  
Henry Seligman ◽  
Burton Foringer ◽  
A.O'B Brandon ◽  
...  
Keyword(s):  
Industrial Applications ◽  
Radioactive Materials

STUDIES ON THYROIDAL COLLOID PINOCYTOSIS USING A DOUBLE ISOTOPE TECHNIQUE

1972 ◽  
Vol 70 (1) ◽  
pp. 48-55 ◽  
Author(s):  
Mario A. Pisarev ◽  
Noe Altschuler ◽  
Leslie J. DeGroot
Keyword(s):  
Acid Phosphatase ◽  
Thyroid Hormone ◽  
Trichloroacetic Acid ◽  
Specific Activity ◽  
Acid Precipitation ◽  
Solvent System ◽  
Blood Stream ◽  
Radioactive Materials ◽  
Isotope Technique ◽  
Double Isotope

ABSTRACT The process of secretion of the thyroid hormone involves several steps: pinocytosis of thyroglobulin, fusion of the colloid droplets with the lysosomes, digestion of thyroglobulin by a cathepsin, dehalogenation of tyrosines and release of thyronines into the blood stream. The present paper describes a double isotope technique for studying the first two steps. Thyrotrophin (TSH) administration to rats increased the radioactivity present in all fractions, specially in the 15 000 × g pellet. When the subcellular distribution of acid phosphatase was determined, the highest specific activity was found in this fraction, thus indicating the presence of lysosomes. The content of radioactive materials in the 15 000 × g pellet was analyzed by trichloroacetic acid precipitation and by ascending paper chromatography using n-butanol:ethanol:ammonium hydroxide (5:1:2;v/v) as solvent system. The results obtained showed that 90% of the radioactivity was protein bound and strongly suggest that this material is thyroglobulin.

Comparison of Lead, Copper and Aluminium as Gamma Radiation Shielding Material through Experimental Measurements and Simulation Using MCNP Version 4c

2018 ◽  
Vol 9 (08) ◽  
pp. 20193-20206 ◽  
Author(s):  
Md. Akhlak Bin Aziz ◽  
Md. Faisal Rahman ◽  
Md. Mahidul Haque Prodhan
Keyword(s):  
Gamma Radiation ◽  
Sodium Iodide ◽  
Experimental Approach ◽  
Radiation Shielding ◽  
Test Material ◽  
Simulation Techniques ◽  
Radiation Sources ◽  
Simulation Monte Carlo ◽  
Shielding Material ◽  
Code Version

The paper compares  Lead, Copper and Aluminium as gamma radiation shielding material using both experimental and simulation techniques. Cs- 137 (662KeV), Na-22 (511KeV) and Na- 22(1274KeV) were used as gamma radiation sources and a sodium iodide (NaI) detector was used to detect the radiation. Variations were noted for detected gamma count rates by changing shielding material thickness. In the experimental approach, thickness was varied by placing sheets of a particular test material one by one. For simulation, Monte Carlo n- Particle (MCNP) code version 4c was used and the geometry of the whole experimental setup was plotted in it. The results were then compared for each test material and it was found that lead is the best shielding material for gamma radiation followed by copper and aluminium.

WIELAND DURO TUNGSTEN

Alloy Digest ◽  
2020 ◽  
Vol 69 (10) ◽  
Keyword(s):  
Melting Point ◽  
Physical Properties ◽  
Tensile Properties ◽  
Modulus Of Elasticity ◽  
Radiation Shielding ◽  
High Melting ◽  
High Modulus ◽  
High Melting Point ◽  
Structural Applications ◽  
Very High

Abstract Wieland Duro Tungsten is unalloyed tungsten produced from pressed-and-sintered billets. The high melting point of tungsten makes it an obvious choice for structural applications exposed to very high temperatures. Tungsten is used at lower temperatures for applications that can benefit from its high density, high modulus of elasticity, or radiation shielding capability. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on machining. Filing Code: W-34. Producer or source: Wieland Duro GmbH.

SD 170/175/180/185

Alloy Digest ◽  
2005 ◽  
Vol 54 (9) ◽  
Keyword(s):  
Physical Properties ◽  
Tensile Properties ◽  
Radiation Shielding ◽  
High Density

Abstract The SD group is part of the Densalloy family of materials, which are high-density alloys used for a variety of applications, from counterbalance weights to radiation shielding. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on forming. Filing Code: W-28. Producer or source: Tungsten Products, An Allegheny Technologies Company.

Sign in / Sign up

Export Citation Format

Share Document