PubMed · 5470336
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1970. IV. Other data.. https://pubmed.ncbi.nlm.nih.gov/5470336/
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Three different autoradiographical methods were tested for detection, localisation and quantification of radionuclides in hot particles deposited on air filters. With all methods, hot particles could successfully be localised on air filters. Two methods, a X-ray film technique and a digital autoradiography technique using a microchannel array detector, have been examined with particles of known activity and with particles on air filter samples of the Chernobyl area to be able to quantify the 90Sr activity in the hot particles consistently. The results obtained in this study suggest that the digital autoradiography system is a very useful tool having a high efficiency with a low measurement uncertainty and allowing short exposure times for extensive measurement tasks.
An analysis of 238Pu in the whole body donation to the U.S. Transuranium and Uranium Registries (USTUR) is presented. This donor accidentally inhaled an unusual physical form of plutonium, predominantly the 238Pu isotope in the form of a highly insoluble ceramic. Along with six other workers accidentally exposed at the same time, this donor excreted little or no 238Pu in his urine for several months. Subsequently, however, and, with no further intakes, the urinary excretion of 238Pu by all of these workers increased progressively. Such a pattern of increasing urinary excretion of plutonium resulting from a single acute inhalation was unknown at the time. The subject of this study provided a unique opportunity to analyze not only the pattern of urinary excretion for 17 y following this unusual intake but also the complete distribution of 238Pu in his donated body tissues and skeleton at death. Radiochemical analyses of tissues from this whole body donation were used to perform critical tests of the applicability and accuracy of the respiratory tract model and the systemic biokinetic models for plutonium currently recommended by the International Commission on Radiological Protection. The respiratory tract model was applied to analyze the donor's long-term urinary excretion pattern. The facility provided by this model to represent progressive transformation of insoluble particles in the lungs into a more soluble form, applied in conjunction with the systemic biokinetic model, predicted the total amount of 238Pu measured in the donor's body to within 17% accuracy. The measured division of 238Pu between the donor's lungs and systemic organs was predicted to within 10%. Small adjustments to several rate constants in these models provided precise predictions of the absolute amounts of 238Pu in the lungs, thoracic lymph nodes, liver, red bone marrow, skeleton (including the distribution of 238Pu between trabecular and cortical bone matrices derived from the radiochemical analyses), kidneys, testes, and muscle. The resulting individual-specific parameters were applied to evaluate the equivalent dose rates and cumulative doses received by the donor's organs and the overall effective dose. Whereas these individual modifications to the ICRP models provided a more accurate representation of the distribution of dose between the donor's organs, it was determined that the ICRP models provided an adequate estimate of the overall effective dose.
In the decommissioning of a highly contaminated alpha environment, such as the one at Hanford's 233-S Plutonium Concentration Facility, one of the key elements of a successful radiological control program is an integrated safety approach. This approach begins with the job-planning phase where the scope of the work is described. This is followed by a brainstorming session involving engineering and craft to identify how to perform the work in a logical sequence of events. Once the brainstorming session is over, a Job Hazard Analysis is performed to identify any potential problems. Mockups are utilized to enable the craft to get hands on experience and provide feedback and ideas to make the job run smoother. Ideas and experience gained during mockups are incorporated into the task instruction. To assure appropriate data are used in planning and executing the job, our principal evaluation tools included lapel and workplace air sampling, plus continuous air monitors and frequent surveys to effectively monitor job progress. In this highly contaminated alpha environment, with contamination levels ranging from 0.3 Bq cm-2 to approximately 100,000 Bq cm-2 (2,000 dpm per 100 cm2 to approximately 600 million dpm per 100 cm2), with average working levels of 1,600-3,200 Bq cm-2 (10-20 million dpm per 100 cm2) without concomitant ambient radiation levels, control of the spread of contamination is key to keeping airborne levels As Low As Reasonably Achievable.