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Title: Krypton-85 health risk assessment for a nuclear fuel reprocessing plant

Abstract

The risks involved in the routine release of /sup 85/Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of /sup 85/Kr. Instead of releasing the /sup 85/Kr to the environment when fuel is reprocessed, it can be captured, immobilized and stored. Two alternative methods of capturing /sup 85/Kr (cryogenic distillation and fluorocarbon absorption) and one method of immobilizing the captured gas (ion implantation/sputtering) were theoretically incorporated into a representative fuel reprocessing plant, the Barnwell Nuclear Fuel Plant, even though there are no known plans to start up this facility. Given the uncertainties in the models used to generate lifetime risk numbers (0.02 to 0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks for the three situations, (i.e., no-capture and two-capture alternatives) cannot be considered meaningful. It is possible that no risks would occur from any of the three situations. There is certainly no reason to conclude that risks from /sup 85/Kr routinely released to the environment are greater than those that would result from the other two situations considered. Present regulations mandate recovery and disposal ofmore » /sup 85/Kr from the off gases of a facility reprocessing spent fuel from commercial sources. Because of the lack of a clear-cut indication that recovery woud be beneficial, it does not seem prudent to burden the facilities with a requirement for /sup 85/Kr recovery, at least until operating experience demonstrates the incentive. The probable high aging of the early fuel to be processed and the higher dose resulting from the release of the unregulated /sup 3/H and /sup 14/C also encourage delaying implementation of the /sup 85/Kr recovery in the early plants.« less

Authors:
; ; ;
Publication Date:
Research Org.:
Pacific Northwest Lab., Richland, WA (USA)
OSTI Identifier:
6510974
Report Number(s):
PNL-5209
ON: DE84017437
DOE Contract Number:
AC06-76RL01830
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTANT EFFECTS ON LIVING ORGS. AND BIOL. MAT.; HUMAN POPULATIONS; RADIATION DOSES; KRYPTON 85; RADIATION HAZARDS; RADIOACTIVE WASTE PROCESSING; PERSONNEL; ADSORPTION; DISTILLATION; FUEL REPROCESSING PLANTS; OFF-GAS SYSTEMS; SPUTTERING; THEORETICAL DATA; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DATA; DOSES; EVEN-ODD NUCLEI; HAZARDS; HEALTH HAZARDS; HOURS LIVING RADIOISOTOPES; INFORMATION; INTERMEDIATE MASS NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KRYPTON ISOTOPES; MANAGEMENT; NUCLEAR FACILITIES; NUCLEI; NUMERICAL DATA; POPULATIONS; PROCESSING; RADIOISOTOPES; SEPARATION PROCESSES; SORPTION; WASTE MANAGEMENT; WASTE PROCESSING; YEARS LIVING RADIOISOTOPES; 054000* - Nuclear Fuels- Health & Safety; 052001 - Nuclear Fuels- Waste Processing; 560151 - Radiation Effects on Animals- Man; 560161 - Radionuclide Effects, Kinetics, & Toxicology- Man; 050800 - Nuclear Fuels- Spent Fuels Reprocessing

Citation Formats

Mellinger, P.J., Brackenbush, L.W., Tanner, J.E., and Gilbert, E.S. Krypton-85 health risk assessment for a nuclear fuel reprocessing plant. United States: N. p., 1984. Web. doi:10.2172/6510974.
Mellinger, P.J., Brackenbush, L.W., Tanner, J.E., & Gilbert, E.S. Krypton-85 health risk assessment for a nuclear fuel reprocessing plant. United States. doi:10.2172/6510974.
Mellinger, P.J., Brackenbush, L.W., Tanner, J.E., and Gilbert, E.S. Wed . "Krypton-85 health risk assessment for a nuclear fuel reprocessing plant". United States. doi:10.2172/6510974. https://www.osti.gov/servlets/purl/6510974.
@article{osti_6510974,
title = {Krypton-85 health risk assessment for a nuclear fuel reprocessing plant},
author = {Mellinger, P.J. and Brackenbush, L.W. and Tanner, J.E. and Gilbert, E.S.},
abstractNote = {The risks involved in the routine release of /sup 85/Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of /sup 85/Kr. Instead of releasing the /sup 85/Kr to the environment when fuel is reprocessed, it can be captured, immobilized and stored. Two alternative methods of capturing /sup 85/Kr (cryogenic distillation and fluorocarbon absorption) and one method of immobilizing the captured gas (ion implantation/sputtering) were theoretically incorporated into a representative fuel reprocessing plant, the Barnwell Nuclear Fuel Plant, even though there are no known plans to start up this facility. Given the uncertainties in the models used to generate lifetime risk numbers (0.02 to 0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks for the three situations, (i.e., no-capture and two-capture alternatives) cannot be considered meaningful. It is possible that no risks would occur from any of the three situations. There is certainly no reason to conclude that risks from /sup 85/Kr routinely released to the environment are greater than those that would result from the other two situations considered. Present regulations mandate recovery and disposal of /sup 85/Kr from the off gases of a facility reprocessing spent fuel from commercial sources. Because of the lack of a clear-cut indication that recovery woud be beneficial, it does not seem prudent to burden the facilities with a requirement for /sup 85/Kr recovery, at least until operating experience demonstrates the incentive. The probable high aging of the early fuel to be processed and the higher dose resulting from the release of the unregulated /sup 3/H and /sup 14/C also encourage delaying implementation of the /sup 85/Kr recovery in the early plants.},
doi = {10.2172/6510974},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Aug 01 00:00:00 EDT 1984},
month = {Wed Aug 01 00:00:00 EDT 1984}
}

Technical Report:

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  • A health risk assessment was conducted to investigate the impact of implementing regulations from the Environmental Protection Agency's Final Environmental Statement - 40 CFR 190 - Environmental Protection Requirements for Normal Operation of Activities in the Uranium Fuel Cycle. Potential risks involved in the routine release of /sup 85/Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of /sup 85/Kr. The average occupationally exposed worker was estimated to receive about 400 to 600 mrem/y from /sup 85/Kr recovery and immobilization activities. This dose is a factor of 20,000 to 30,000more » higher than the estimated dose to the maximum offsite individual (0.02 mrem/y), and a factor of 130,000 to 200,000 higher than the dose received by the average member of the 50-mile population (0.003 mrem/y) from routine release of all /sup 85/Kr. Given the uncertainties in the models used to generate lifetime risk numbers (0.02-0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks cannot be considered meaningful. There is certainly no reason to conclude that risks from /sup 85/Kr routinely released to the environment are greater than those that would result from recovery, immobilization and storage of the noble gas. 22 references, 1 figure, 3 tables.« less
  • A technical and economical analysis has been made of methods for collecting and concentrating krypton from the off-gas from a typical nuclear fuel reprocessing plant. The methods considered were cryogenic distillation, fluorocarbon absorption, mordenite adsorption, and selective permeation. The conclusions reached were: Cryogenic distillation is the only demonstrated route to date. Fluorocarbon absorption may offer economic and technical advantages if fully developed and demonstrated. Mordenite adsorption has been demonstrated only on a bench scale and is estimated to cost more than either cryogenic distillation or fluorocarbon absorption. Selective permeation through a silicone rubber membrane is not sufficiently selective for themore » route to be cost effective.« less
  • The state-of-the-art for the continuous monitoring of /sup 14/C, /sup 129/I, and /sup 85/K was evaluated. Published methodology and developmental programs at the Idaho Chemical Processing Plant are summarized. A sequential monitor is proposed where all forms of /sup 14/C and /sup 129/I are catalytically converted to a single form (CO/sub 2/ or I/sub 2/) and separated from interferences by selective permeation. Lastly, /sup 85/K is monitored with a beta detector mounted in a flow chamber. A developmental program for extending the state-of-the-art is outlined. 6 figures, 6 tables.
  • The dose commitment to individuals and the regional population from ingesting aquatic foods contaminated by radionuclides emitted from proposed nuclear fuel reprocessing at the Savannah River Plant was estimated. The estimates are based on source emission data and deposition patterns provided by the project coordinator and on the Hanford Engineering Development Laboratory's predictions of radionuclide concentrations in surface waters of the southeast hydrologic study region. The 50-y dose commitment to an individual is very low, ranging from about 1 ..mu..rem to the kidneys to 26 ..mu..rem to bone. The 50-y dose commitment to the regional and total populations ranges frommore » about 1 person-rem to the kidneys to 55 person-rem to bone. Freshwater fish and marine shellfish contribute 99.8% or more to the total dose commitment. Marine fish contribute less than 0.2%. For the source term under consideration, the major portion of the dose commitments is attributable to Sr and Cs.« less