Current status of bioassay procedures to detect and quantify previous exposures to radioactive materials. Bioassay Procedures Working Group

Journal Article · Tue Jan 01 00:00:00 EST 1991 · Health Physics; (USA)

OSTI ID:5838286

Boecker, B; Hall, R; Inn, K; Lawrence, J; Ziemer, P; Eisele, G; Wachholz, B; Burr, W Jr ^[1]

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1. Lovelace Inhalation Toxicology Research Institute, Albuquerque, NM (USA)

This report was prepared by a working group established by the Oak Ridge Associated Universities (ORAU) for the purpose of assessing the current capabilities of bioassay methods that can be used to determine the occurrence and magnitude of a previous internal deposition of one or more radionuclides. The first five sections discuss general features of the use of in-vitro bioassay samples to achieve this purpose. The remainder of the report is focused on the possible use of urine bioassay procedures to detect and quantify internal depositions of radionuclides that may have occurred in United States occupation troops in Hiroshima or Nagasaki, Japan, prior to 1 July 1946, or to personnel who participated in atmospheric nuclear weapons tests conducted between 1945 and 1962. Theoretical calculations were made to estimate the quantities of various radionuclides produced in a 20-kiloton (kt) nuclear detonation that might still be present in measurable quantities in people today if they were exposed 25 to 40 y ago. Two radionuclides that emerged as good choices for this type of bioassay analysis were 90Sr, which emits beta particles, and 239,240Pu, which emits alpha particles. The current status and future prospects of chemical procedures for analyzing in-vitro urine bioassay samples for these two radionuclides were examined to determine the minimum amounts that could be detected with current methods and how much one might expect the sensitivity of detection to improve in the near future. Most routine 239,240Pu bioassay analyses involve detection by alpha spectrometry. The current minimum detectable amount (MDA) is about 0.74 mBq L-1 (20 fCi L-1), but this could be lowered to 74 muBq L-1 (2 fCi L-1). An MDA of 0.74 mBq L-1 (20 fCi L-1) is adequate for routine bioassay analyses but is too high to detect most uptakes of 239,240Pu that may have occurred 25 to 40 y ago.

• OSTI ID: 5838286
• Journal Information: Health Physics; (USA), Vol. 60 Suppl 1; ISSN 0017-9078
• Country of Publication: United States
• Language: English

Related Subjects

63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTANT EFFECTS ON LIVING ORGS. AND BIOL. MAT.
RADIATION DOSES
BIOASSAY
HIROSHIMA
NAGASAKI
NUCLEAR EXPLOSIONS
ORAU
PLUTONIUM 239
PLUTONIUM 240
STRONTIUM 90
URINE
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALINE EARTH ISOTOPES
ALPHA DECAY RADIOISOTOPES
ASIA
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BIOLOGICAL MATERIALS
BIOLOGICAL WASTES
BODY FLUIDS
DOSES
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
EXPLOSIONS
HEAVY NUCLEI
INTERMEDIATE MASS NUCLEI
ISOTOPES
JAPAN
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEI
PLUTONIUM ISOTOPES
RADIOISOTOPES
STRONTIUM ISOTOPES
US ORGANIZATIONS
WASTES
YEARS LIVING RADIOISOTOPES
560161* - Radionuclide Effects
Kinetics
& Toxicology- Man