Radiation protection instrumentation. Installed dose ratemeters, warning assemblies and monitors. X and gamma radiation of energy between 50 keV and 7 MeV

Naturally Occurring Radioactive Materials (NORMs) in the offshore petroleum industry are generally associated with the formation of scale in pipes and vessels. As scale and sludge contain radioactive isotopes of radium they are in the category of Low Specific Activity (LSA) NORMs. Handling of NORMs creates issues involving occupational health and safety, environmental protection and radioactive waste management and waste disposal. Barium(Radium)Sulfate scale is highly insoluble and can create serious production problems by clogging pipes and valves.The paper discusses the external gamma radiation monitoring at the external surfaces of well and oil production pipes which assists in establishing the scale thickness patterns in pipes and in identifying the optimum location of a scale inhibitor injection point.To minimise radiation doses received by workers special NORM handling Work Procedures and Instructions supported by radiation protection training need to be developed. If facility personnel are trained in radiation protection and Work Procedures and Instructions are adopted it is possible to effectively manage personal radiation exposures below the public limit of 1 millisievert per year. Under such conditions no personal radiation monitoring during routine operations is required and the assessment of routine annual external radiation doses may be carried out through yearly external gamma radiation surveys of of fshore petroleum production facilities.The NORM waste cannot be disposed of onshore within the same disposal sites used for general non-radioactive waste. In Australia only the NORM waste generated in Western Australia can be disposed of onshore in an official low level radioactive waste disposal facility. It is important that Governments of other States and Territories address the onshore NORM waste disposal option. Regulations should also address a screening method for scrap metal contaminated by NORMs to be released for smelting.

Download Full-text

Composition Material for Radiation Protection Based on Modified Disperse Titanium Hydride and Silicate Connecting

Solid State Phenomena ◽

10.4028/www.scientific.net/ssp.299.163 ◽

2020 ◽

Vol 299 ◽

pp. 163-168

Author(s):

R.N. Yastrebinskii ◽

A.A. Karnauhov

Keyword(s):

Composite Material ◽

Gamma Radiation ◽

Radiation Protection ◽

Titanium Hydride ◽

Atomic Hydrogen ◽

Composition Material ◽

Physicochemical Interaction ◽

Alkaline Environment ◽

Organosilicon Modifier

This paper presents an analysis of known radiation protection materials. The prospects of using materials based on titanium hydride are shown. The possibility of obtaining finely ground titanium hydride with a high content of atomic hydrogen in its structure has been established. The features of the physicochemical interaction of dispersed titanium hydride and heavy flint, after hydrolysis in the alkaline environment of the organosilicon modifier – tetraethoxysilane, are revealed. The possibility of obtaining a thermostable low-activated composite material based on dispersed titanium hydride for complex protection against neutron and gamma radiation has been established. The structure of the obtained composite was investigated.

Download Full-text

Erratum - In the article "Rapid and long-term gamma-radiation annealing in low-dropout voltage regulators" by Vladimir Dj. Vukic

Nuclear Technology and Radiation Protection ◽

10.2298/ntrp1703305e ◽

2017 ◽

Vol 32 (3) ◽

pp. 305-305

Author(s):

E Editorial

Keyword(s):

Gamma Radiation ◽

Radiation Protection ◽

Voltage Regulators ◽

Nuclear Technology ◽

Technical Preparation ◽

Radiation Annealing ◽

Font Color

Published in the Nuclear Technology & Radiation Protection journal, 32 (2017), 2, pp. 155-165, during the technical preparation of the article, errors in equations (1) and (3) and in the accompanying texts were made. Link to the corrected article <a href="http://dx.doi.org/10.2298/NTRP1702155V">10.2298/NTRP1702155V</a>

Download Full-text

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

Nuclear and Radiation Safety ◽

10.32918/nrs.2018.1(77).08 ◽

2018 ◽

pp. 52-58 ◽

Cited By ~ 1

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”.

Download Full-text