[en] In this work, lead glass doped with 50%, 55%,60%, 65%, and 70% w/w Pb₃O₄. After that, glass mixtures were melt at 1,250οC with 4 hours soaking time. Molten glass was shaped by mould casting technique then annealed at 700οC and cooled down to room temperature. It was found that the glass with 60%w/w Pb₃O₄ show maximum absorption coefficient of about 0.383 cm^-1 with I-131 at energy 364 keV. The observed refractive indices of the samples range between 1.5908 to 1.5922

[en] The invention relates to compositions, methods of production, and uses of non-combustible nuclear radiation shields, with particular emphasis on those containing a high concentration of hydrogen atoms, especially effective for moderating neutron energy by elastic scatter, dispersed as a discontinuous phase in a continuous phase of a fire resistant matrix

[en] Small volumes with lead brick and lead glass shielding are used, and in nuclear technology we call them ''hot cell''. Furthermore for separating the exposure rooms from the operator rooms lead glassed windows of heavy concreate walls can be used. Unfortunately, these glasses can not be produced in Turkey. ordinary crystals which have lead-oxide in them, can be produced in Turkey, in this essay we have investigated the usage of ordinary crystals for the radiation shielding. Crystals have been tested with different types of radiation and ''radiation absorbtion'' curves, ''half thickness'' and ''tenth value thickness'' have been calculated. (author)

No abstract available

[en] A portable shielding basket used for personnel protection from ionizing radiation in inspections, repairs and maintenance consists of an outer wall consisting, in turn, of an outer and inner jackets with a sealing fill in between them, and of a bottom consisting of a base and a floor plates. A support platform is provided between the top edges of the outer and inner jackets of the outer wall. It is fenced with a hollow elastic sealing border. The basket bottom is divided into a peripheral fixed part and an inner loose part. A gap is provided between the base plate and the circular peripheral basket base. The basket is designed for use in inspection, cleaning and repairs of the top sealing surface of the main circulating pump body and of its suction branch. (J.B.). 1 fig

[en] The radiation shielding properties of different types of building materials were investigated against gamma-radiation

[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] Purpose: To provide a radiation shielding putty-like composition excellent in radiation shielding performance and shape-retainability after its application and being capable of removing with ease after the application. Constitution: The binder for use in the composition includes liquid or semi-solid grease, liquid or semi-solid organic or inorganic polymers or the mixture thereof having a viscosity at 25⁰C of more than 10⁵ CST and non-mixing consistensity of more than 150. The composition comprises 500 - 4000 parts by weight of inorganic powder per 100 parts by weight of the binder. The inorganic powder usable herein functions as radiation shielding material and includes lead, zinc, copper or oxides and compounds thereof having a density of more than 5. The radiation shielding putty composition has a softness ranging from 1 - 25 (1 mm) at ambient temperature and a density of more than 4. Further, from 0.1 to 50 parts by weight of asbestos or like other fibers are kneaded per 100 parts by weight of the binder using a roll or the like in order to retain the configuration. (Seki, T.)

[en] From 1969 through early 1976, Oak Ridge National Laboratory was requested by the Westinghouse Advanced Reactors Division (WARD) to analyze various shields WARD designed for the Fast Flux Test Facility (FFTF). To develop the proper methodology for such a large and complex system, it was necessary to improve the basic cross-section data sets for sodium and iron and to devise calculational techniques which would allow some regions to be treated in detail and would also allow the analyses to be carried out in steps that could be coupled to each other. These requirements necessitated the performance of two types of experiments: measurements of radiation transport through bulk samples (simple geometry) of important FFTF materials; and measurements of radiation transport through mock-ups of specific geometric regions of the FFTF. The successful analyses of these experiments allowed the application of the derived data sets and various combinations and adaptations of the DOT discrete ordinates and MORSE Monte Carlo transport codes to the FFTF system itself. The first series of calculations for the full system revealed that a cavity surrounding the reactor vessel provided a pathway for neutrons to stream up to the head compartment. Also, fissions in fuel elements stored in the outer region of the reactor vessel were found to contribute significantly to the cavity streaming. As a result, the major ORNL effort was expended on analyzing various designs of a concrete shield to be added in the upper region of the reactor cavity. With the inclusion of the shield and modifications to the reactor vessel support system, the dose rates above the closure head were reduced by a factor of approximaterly 10⁴

[en] The standard presents the types, specifications and marking of lead blocks. The general technical requirements and types are given as are the extent of and procedures for testing the observance of the standard. Packing, storage, and guarantees given by the producer are described. (E.S.)