[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] The disclosure pertains to a clamping apparatus having a stud capturing portion and a stud facing portion bolted together so as to compressively support a radiation-proof sheet material, such as lead sheeting, there-in-between. The interior wall covering material, such as panelling or wall board, is secured to the external surface of the stud facing portion. No nails are required to support the radiation-proof sheeting material, thereby minimizing accidental leakage due to harmful radiation passing through openings inadvertently disposed in the radiation-proof sheeting in the conventional nail securing supporting thereof. A pair of radiation-proof tracks capture the free ends of the stud capturing portion and the stud facing portion

No abstract available

[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] Safety apparatus for use in administering radioactive serums by a syringe, without endangering the health and safety of the medical operators is described. The apparatus consists of a sheath and a shield which can be retracted into the sheath to assay the radioactive serum in an assay well. The shield can be moved from the retracted position into an extended position when the serum is to be injected into the patient. To protect the operator, the shield can be constructed of tantalum or any like high density substance to attenuate the radiation, emanating from the radioactive serums contained in the syringe, from passing to the atmosphere. A lead glass window is provided so that the operator can determine the exact quantity of the radioactive serum which is contained in the syringe

[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] 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] The control of ocular protection medium which is normally used by workers, finds itself confronted by unsurmountable difficulties. Transmission determination needs fine glass lenses, extrapolating the values obtained to the real value of the medium used. The degree of protection required of the glass used by workers has been determined using successive approximations. The work method is quick and simple, and the apparatus used is within the reach of any medium sized laboratory. A theoretical justification has been made of the fundamental principles of the method; for example, the protective power of various filter lenses used by workers in this country has been determined. The method has been centred on the possibility of its practical application. The results obtained are interpreted taking into consideration a possible emissing source, and their discussion is based on prevailing standards which exist in most European countries. The control carried out has allowed to state that in most cases the protection medium used is not adequate, owing to a poor selection or an inadequate maintenance

[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] Cerrobend alloy casts are made to define the desired electron field shapes. These custom casts are fabricated for the selected electron applicator size that has been chosen for the patient. When the cast is placed into that selected electron applicator, it will block out areas that are not to be treated. When an all metal mold assembly was used for the fabrication of these casts, the lip region of the cast which is used to accurately align the cast in the actual treatment applicator, had an irregular edge that prevented an accurate alignment of the cast. To eliminate the irregular edges on the lip region of the cast, the metal mold assembly was heated to approximately 80-85 degrees C before the molten cerrobend alloy was poured into it. The heating of the metal mold assembly helps eliminate the irregular edges on the lip region of the cast. Unfortunately it also created new flaws such as holes, dents, cracks and/or crystallization of the cast as it solidified. These flaws were controlled by cooling the metal mold assembly and the cast immediately after the pouring of the molten cerrobend alloy, evenly with water