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1.
Health Phys ; 76(2): 120-8, 1999 Feb.
Article in English | MEDLINE | ID: mdl-9929122

ABSTRACT

Doses of internal radiation from inhalation of metal tritide aerosols are potentially a major radiation protection problem encountered by nuclear industry workers. Based on results of experiments with rats intratracheally instilled with titanium tritide particles and on a self-absorption factor of beta particles determined by a numerical method, a biokinetic model was developed for inhaled particles of titanium tritide. Results showed that lung burdens of the tritide are well represented by a two-component exponential equation; biological half-lives derived for the retention of 3H in lung were 0.81 d and 66 d. The tritium clearance rate via urine or feces was described by bi-phase exponential components. At 121 d after instillation, 82% of the initial lung burden of 3H had been eliminated, of which 37% was excreted in urine, 29% via feces, and 16% through exhaled air. Based on simulation results of the biokinetic model, the cumulative absorbed dose and committed effective dose were calculated as well as the annual limit of intake (ALI) and derived air concentration (DAC). The ALI and DAC values for titanium tritide were a factor of 5 lower than values for tritiated water. This information will be useful in developing new guidelines for radiation protection purposes.


Subject(s)
Lung/metabolism , Titanium/pharmacokinetics , Tritium/pharmacokinetics , Administration, Inhalation , Animals , Biological Transport , Instillation, Drug , Male , Models, Biological , Rats , Rats, Inbred F344 , Titanium/administration & dosage , Trachea , Tritium/administration & dosage
2.
Risk Anal ; 19(5): 959-86; discussion 987-93, 1999 Oct.
Article in English | MEDLINE | ID: mdl-10765441

ABSTRACT

The conceptual and computational structure of a performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) is described. Important parts of this structure are (1) maintenance of a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, with stochastic uncertainty arising from the many possible disruptions that could occur over the 10,000-year regulatory period that applies to the WIPP, and subjective uncertainty arising from the imprecision with which many of the quantities required in the analysis are known, (2) use of Latin hypercube sampling to incorporate the effects of subjective uncertainty, (3) use of Monte Carlo (i.e., random) sampling to incorporate the effects of stochastic uncertainty, and (4) efficient use of the necessarily limited number of mechanistic calculations that can be performed to support the analysis. The WIPP is under development by the U.S. Department of Energy (DOE) for the geologic (i.e., deep underground) disposal of transuranic (TRU) waste, with the indicated PA supporting a Compliance Certification Application (CCA) by the DOE to the U.S. Environmental Protection Agency (EPA) in October 1996 for the necessary certifications for the WIPP to begin operation. The EPA certified the WIPP for the disposal of TRU waste in May 1998, with the result that the WIPP will be the first operational facility in the United States for the geologic disposal of radioactive waste.


Subject(s)
Radioactive Waste , Waste Management , Geological Phenomena , Geology , Humans , Models, Statistical , New Mexico , Radioactive Waste/legislation & jurisprudence , Risk Assessment , Stochastic Processes , United States , United States Environmental Protection Agency , Waste Management/legislation & jurisprudence , Waste Management/statistics & numerical data
3.
Health Phys ; 73(4): 633-8, 1997 Oct.
Article in English | MEDLINE | ID: mdl-9314223

ABSTRACT

Metal tritides including titanium tritide (Ti 3Hx) and erbium tritide (Er 3Hx) have been used as components of neutron generators. The current understanding of metal tritides and their radiation dosimetry for internal exposure is very limited, and the ICRP Publication 30 does not provide for tritium dosimetry in metal tritide form. However, a few papers in the literature suggest that the solubility of metal tritides could be low. The current radiation protection guidelines for metal tritide particles are based on the assumption that their biological behavior is similar to tritiated water, which could be easily absorbed into body fluid. Therefore, these particles could have relatively short biological half-lives (10 d). If the solubility is low, the biological half-life of metal tritide particles and the dosimetry of an inhalation exposure to these particles could be quite different from tritiated water. This paper describes experiments on the dissolution rate of titanium tritide particles in a simulated lung fluid. Titanium tritide particles with mean sizes of 103 microm (coarse) and 0.95 microm (fine) were used. The results showed that the coarse particles dissolved much more slowly than the fine particles. The long-term dissolution half times were 361 and 33 d for the coarse and fine particles, respectively. Dissolution data of the fine particles were consistent with the diffusion theory. The dissolution half times were longer than the 10-d biological half time for tritiated water in the body. This finding has significant implications for the current health protection guidelines, including annual limits of intakes and derived air concentrations.


Subject(s)
Erbium/pharmacokinetics , Lung/metabolism , Radiation Protection/standards , Titanium/pharmacokinetics , Tritium/pharmacokinetics , Body Fluids/metabolism , Erbium/chemistry , Humans , Models, Biological , Radiation Monitoring/instrumentation , Radiation Monitoring/methods , Regression Analysis , Time Factors , Titanium/chemistry , Tritium/chemistry , Ultrafiltration
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