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C D Berger

Publications and source records attributed to C D Berger.

9 recordsLinked to original sources

Managing metabolic model deficiencies for routine radiation protection purposes at a thorium dioxide facility.

At a metallurgical facility using thorium dioxide feed materials, a number of conventional direct- and indirect-bioassay methods were potentially suitable monitoring methodologies when industry-standard dose assessment methodologies were based upon ICRP recommendations issued in 1959. When the ICRP recommended a different dose assessment methodology in 1977, the intake limits for thorium dropped significantly, and conventional bioassay methods for routine monitoring were rendered ineffective. While determining the technical basis for its air monitoring program, the facility noted that the radioactive materials used as feed to the process were highly insoluble. Therefore, their solubility in simulated lung fluids was determined. The results of this determination indicated that the facility's materials, if inhaled, dissolve in the lung at a half-time that is significantly longer than that contained in international consensus standards for Y-class compounds. They also indicated that the secondary dose limits, if adjusted to eliminate the dose contribution from translocated radionuclides, should be higher, and that a derived air concentration based upon more recent international recommendations is more appropriate for use in the facility's routine monitoring program.

Biological Assay↗

Criteria for performing multiple dosimetry.

When radiation fields vary spatially as a result of job- or location-specific conditions, the use of more than one dosimeter may be necessary for a variety of radiation protection purposes. This paper contains a methodology for when and how to use multiple dosimeters under conditions incident to routine activities in the presence of ionizing radiation. It also describes a methodology for determining the effective dose equivalent when the use of multiple dosimeters has been deemed necessary by radiation protection professionals. The methodology is based upon application of compartments and compartment factors. Included herein are examples demonstrating when multiple dosimeters should be used and how effective dose equivalent should be calculated using the compartment factors.

Humans↗

Biometric estimation of chest wall thickness of females.

Optimal use of whole-body counting data to estimate pulmonary deposition of many of the actinides is dependent upon accurate measurement of the thickness of the chest wall because of severe attenuation of low-energy x rays and photons associated with the decay of these radionuclides. An algorithm for estimation of female chest wall thicknesses, verified by real-time ultrasonic measurements, has been derived based on the correlation of measured chest wall thickness and other common biometric quantities. Use of this algorithm will reduce the error generally associated with estimation of internal actinide deposition previously resulting from assuming an average chest wall thickness for all female subjects.

Actinoid Series Elements↗