[en] A construction module is described for use in protecting personnel against emissions from radioactive material comprising: a shaped member suitable for assembly with other shaped members to form a structure for shielding personnel; said shaped members being formed from suitable shielding material capable of excluding passage of emissions from radioactive material and having adjoining surfaces for reception closely adjacent complementary surfaces of other shaped members; and a synthetic polymeric material having been formed by molding to engage and extend over an exterior surface of said shaped member forming a hardened coating layer protecting the shielding material from contamination by exposure to radioactive material and serving as a readily decontaminated surface to avoid exposure of personnel to emissions from radioactive material; whereby an encapsulated construction module is formed suitable for assembly as a structure to shield personnel and which is easily decontaminated avoiding exposure to emissions from radioactive material

[en] The shield is composed of a double-walled hollow body, for instance in composite materials, enclosing a part of a circuit (vane, pipe, etc.), the inside cavity between the walls can be filled (or evacuated) with a filling material such as hematite pig iron balls

[en] This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to shielding enclosures: their application and procedures guides

[en] A radiological screen for placing on a patient's skin is discussed, comprising a flat jacket containing a fine particulate filler and a settable resin binder, the fine particulate filler being of a material which absorbs medical radiation, and the jacket including a window to transmit such radiation through the flat jacket. 16 claims, 4 drawing figures

[en] For any appreciable radiation source, such as a nuclear reactor core or radiation physics accelerator, there will be the safety requirement to shield operators from the effects of the radiation from the source. Both the size and weight of the shield need to be minimised to reduce costs (and to increase the space available for the maintenance envelope on a plant). This needs to be balanced against legal radiation dose safety limits and the requirement to reduce the dose to operators As Low As Reasonably Practicable (ALARP). This paper describes a method that can be used, early in a shield design, to scope the design and provide a practical estimation of the size of the shield by optimising the shield internals. In particular, a theoretical model representative of a small reactor is used to demonstrate that the primary shielding radius, thickness of the primary shielding inner wall and the thicknesses of two steel inner walls, can be set using the Lagrange multiplier method with a constraint on the total flux on the outside of the shielding. The results from the optimisation are presented and an RZ finite element transport theory calculation is used to demonstrate that, using the optimised geometry, the constraint is achieved. (author)

[en] With the shaped brick from metal or concrete radiation protection walls can be erected in dry construction a single shape for the bricks being sufficient. The connection contours of the shaping bricks are derived from the generated surface of an equilateral prisma. If one end is shaped concave and the other convex it becomes possible to reproduce straight lines, angles, polygons, and circles and to fully cover surfaces. In order to balance wall alternations at the connection contours reinforcement ribs are arranged at the concave brick ends. (ORU)

[en] This study presents a methodology for the determination of the air kerma inside buildings due to contamination on the external surfaces and the shielding factors for the construction material to be used on emergency assessment systems for urban areas. The commonly used construction materials were simulated with the MCNP computer code. A special methodology to simulate the bricks with holes were developed, mixing all different regions into a single one, making the simulation easier and faster. The effective density and the attenuation coefficients for the 50-3000 keV energy range were determined. The effective protection for the bricks with no cement cover decreases by 40-50% for energies greater then 300 keV when compared to bricks covered on both sides. With the data made available it was possible to evaluate the influence of the construction materials densities and thickness on the exposure due to external surfaces contamination and to estimate the error on the dose when the shielding factor applied on the calculation differs from the more realistic ones. The shielding factors for three types of walls were determined for a five rooms house. Special protection procedures should be applied for houses built with bricks with no cement cover, because they are due to the double of the dose when compared to houses built with bricks two-sided cement covered. The influence of windows and doors were evaluated too. This work was developed at the IRD in order to provide information on the construction material commonly uses on building in Brazil. (author)

[en] Tests were conducted to determine the electrical and magnetic characteristics of a superconductor shielded core reactor (SSCR). The results show that a closed-core SSCR is predominantly a resistive device and an open-core SSCR is a hybrid resistive/inductive device. The open-core SSCR appears to dissipate less than the closed-core SSCR. However, the impedance of the open-core SSCR is less than that of the closed-core SSCR. Magnetic and thermal diffusion are believed to be the mechanism that facilitates the penetration of the superconductor tube under fault conditions

[en] The Light Ion Fusion Target Development Facility (TDF) is expected to test approximately ten targets per day having yields in the 50 to 800 MJ range. This large number of high yield microexplosions creates design problems in the TDF that are not present in PBFA-I and PBFA-II. The TDF would be the first light ion facility where radioactivity in the target debris and induced in the facility itself constitute a biological hazard. It must have a first wall and a target diagnostics package that can survive repeated mechanical and thermal pulses from the target microexplosions. In addition, the repetition rate is much higher than for present day light ion beam drivers. A preliminary conceptual design for the TDF including a reaction chamber, biological shield, target diagnostics package and driver that addresses these and other problems is presented

[en] In this process a neutron absorber is introduced in one, at least, of the component of the composite materials, the absorber used is gadolinium for protection against neutrons of personnal or electronic devices