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Control of Tritium Health Hazards at the Savannah River Plant

Control of Tritium Health Hazards at the Savannah River Plant
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Release: 1962
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The essential components of the program for the control of tritium hazards at Savannah River include radiological engineering, training of operating personnel in techniques of protection, protective clothing, control of surface and air contamination, bioassay, and environmental monitoring. Rapid change of air in process areas and the continuous measurement of tritium in air are two important facets of the protection program. Workers in a tritium atmosphere wear inexpensive, polyvinyl suits which are supplied with air ana envelop the entire body. Permissible working time limits are established with the help of a nomograph that reflects the tritium concentration in air and the protective value of air masks or plastic suits. Employees submit urine specimens after jobs involving tritium exposure. These specimens are immediately assayed by means of liquid scintillation counting. Grease, oil, and other hydrocarbons retain tritium. Surface contamination is detected qualitatively by use of smears and gas flow proportional counters. Ventilation air from process areas is released to the environs through tall stacks. The stack air is continuously monitored. At the perimeter of the plant and 25 miles away, air is sampled to determine the effect of tritium released through the stacks. The Savannah River, streams on the plant, and food produced in the vicinity of the reservation are routinely analyzed. The tritium levels in the environs of the Savannah River Plant are substantially less than the limits recommended by the International Commission of Radiological Protection for large populations. (auth).


Tritium Protection at the Savannah River Plant

Tritium Protection at the Savannah River Plant
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Total Pages: 6
Release: 1988
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ISBN:

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The Savannah River Plant produces tritium for the nation's defense. In addition to the planned production, unwanted tritium results from neutron irradiation of the heavy water moderator in the plant's reactors. During the past 30 years, continual improvements have been made in methods to protect the large workforce at the reactors and at the tritium facility from the potential hazards of tritium. This paper describes the current protection program.


Environmental Effects of a Tritium Release from the Savannah River Plant

Environmental Effects of a Tritium Release from the Savannah River Plant
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Total Pages:
Release: 1981
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On March 27, 1981, a small amount of tritiated water was inadvertently released from the tritium-processing facility during a routine maintenance operation. This report describes the environmental effects of this release both on the SRP site and offsite. Also, the operation of the WIND (Wind Information and Display) emergency response system during the incident is discussed, and the predicted and diagnosed behavior of the tritium plume is compared with tritium concentrations deduced from air, vegetation, soil, and bioassay samples.


Safe Handling of Tritium

Safe Handling of Tritium
Author: International Atomic Energy Agency
Publisher:
Total Pages: 148
Release: 1991
Genre: Business & Economics
ISBN:

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This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D.


Environmental Effects of a Tritium Gas Release from the Savannah River Plant on December 31, 1975

Environmental Effects of a Tritium Gas Release from the Savannah River Plant on December 31, 1975
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Release: 1976
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At 10:00 p.m. EST on December 31, 1975, 182,000 Ci of tritium gas was released within about 1.5 min from a tritium processing facility at the Savannah River Plant. The release was caused by the failure of a vacuum gage and was exhausted to the atmosphere by way of a 200-ft-high stack. Winds averaging 20 mph carried the tritium offplant toward the east. Calculations indicate that the puff passed out to sea about 35 miles north of Charleston, South Carolina, about 7 hr after the release occurred. Samples from the facility exhaust system indicated that 99.4 percent of the tritium was in elemental form and 0.6 percent was in the more biologically active oxide (water) form. The maximum potential dose to a person (from inhalation and skin absorption) at the puff centerline on the plant boundary was calculated to be 0.014 mrem, or about 0.01 percent of the annual dose received from natural radioactivity. The integrated dose to the population under the release path was calculated to be 0.2 man-rem before the tritium passed out to sea. Over 300 environmental samples were collected and analyzed following the release. These samples included air moisture, atmospheric hydrogen, vegetation, soil, surface water, milk, and human urine. Positive results were obtained in some onplant and plant perimeter samples; these results aided in confirming the close-in puff trajectory. Tritium concentrations in nearly all samples taken beyond the plant perimeter fell within normal ranges; no urine samples indicated any tritium uptakes as a result of the release. Two milk samples did indicate a measurable tritium uptake; the maximum potential dose to an individual drinking this milk was calculated to be about 0.1 mrem. Because calculated doses from assumed exposure to the tritium are low and analyses of environmental samples indicated no significant accumulation of tritium, it is concluded that no significant environmental effects resulted from the December 31, 1975, tritium release. (auth).


Preliminary Risks Associated with Postulated Tritium Release from Production Reactor Operation

Preliminary Risks Associated with Postulated Tritium Release from Production Reactor Operation
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Release: 1988
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The Probabilistic Risk Assessment (PRA) of Savannah River Plant (SRP) reactor operation is assessing the off-site risk due to tritium releases during postulated full or partial loss of heavy water moderator accidents. Other sources of tritium in the reactor are less likely to contribute to off-site risk in non-fuel melting accident scenarios. Preliminary determination of the frequency of average partial moderator loss (including incidents with leaks as small as .5 kg) yields an estimate of (approximately)1 per reactor year. The full moderator loss frequency is conservatively chosen as 5 x 10/sup /minus/3/ per reactor year. Conditional consequences, determined with a version of the MACCS code modified to handle tritium, are found to be insignificant. The 95th percentile individual cancer risk is 4 x 10/sup /minus/8/ per reactor year within 16 km of the release point. The full moderator loss accident contributes about 75% of the evaluated risks. 13 refs., 4 figs., 5 tabs.