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Title: Control of the TMI-2 (Three Mile Island Unit 2) reactor building environment

Abstract

As a result of the March 28, 1979, accident at Three Mile Island Unit 2 (TMI-2), significant quantities of radioactive fission products, including gases, particulates, and iodine, were released into the enclosed reactor building atmosphere from failed fuel in the reactor core. Air samples of the reactor building atmosphere showed /sup 85/Kr with a 10.7-yr half-life to be the principal remaining radionuclide. To permit less restricted access to the reactor building and to proceed toward decontamination of the TMI-2 facility, it was necessary to remove the /sup 85/Kr and to provide a suitable environment for workers. The venting was conducted between June 28 and July 11, 1980. The paper discusses reactor building air sampling, venting of the reactor building, radioactivity released to the environment, and the internal dosimetry program.

Authors:
; ;
Publication Date:
OSTI Identifier:
5684426
Report Number(s):
CONF-881011-
Journal ID: CODEN: TANSA
Resource Type:
Conference
Journal Name:
Trans. Am. Nucl. Soc.; (United States)
Additional Journal Information:
Journal Volume: 57; Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC, USA, 30 Oct - 4 Nov 1988
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONTAINMENT BUILDINGS; DECONTAMINATION; PERSONNEL; RADIATION PROTECTION; THREE MILE ISLAND-2 REACTOR; REACTOR ACCIDENTS; ACCURACY; AEROSOLS; AIR SAMPLERS; ALARM SYSTEMS; BACKGROUND RADIATION; CORIUM; FISSION PRODUCTS; INGESTION; INHALATION; IODINE; KRYPTON 85; MELTDOWN; PARTICULATES; PROTECTIVE CLOTHING; RADIATION MONITORS; RADIOISOTOPES; RARE GASES; REACTOR CORE DISRUPTION; RESPIRATORS; SAMPLING; SKIN ABSORPTION; UPTAKE; US NRC; VENTS; WHOLE-BODY COUNTING; XENON; ABSORPTION; ACCIDENTS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BUILDINGS; CLEANING; CLOTHING; COLLOIDS; CONTAINMENT; COUNTING TECHNIQUES; DISPERSIONS; ELEMENTS; ENRICHED URANIUM REACTORS; EQUIPMENT; EVEN-ODD NUCLEI; FLUIDS; GASES; HALOGENS; HOURS LIVING RADIOISOTOPES; INTAKE; INTERMEDIATE MASS NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KRYPTON ISOTOPES; MATERIALS; MEASURING INSTRUMENTS; MICROSEC LIVING RADIOISOTOPES; MONITORS; NATIONAL ORGANIZATIONS; NONMETALS; NUCLEI; PARTICLES; POWER REACTORS; PWR TYPE REACTORS; RADIATIONS; RADIOACTIVE MATERIALS; REACTORS; SAMPLERS; SOLS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Lodde, G M, Good, B A, and Surgeoner, D M. Control of the TMI-2 (Three Mile Island Unit 2) reactor building environment. United States: N. p., 1988. Web.
Lodde, G M, Good, B A, & Surgeoner, D M. Control of the TMI-2 (Three Mile Island Unit 2) reactor building environment. United States.
Lodde, G M, Good, B A, and Surgeoner, D M. 1988. "Control of the TMI-2 (Three Mile Island Unit 2) reactor building environment". United States.
@article{osti_5684426,
title = {Control of the TMI-2 (Three Mile Island Unit 2) reactor building environment},
author = {Lodde, G M and Good, B A and Surgeoner, D M},
abstractNote = {As a result of the March 28, 1979, accident at Three Mile Island Unit 2 (TMI-2), significant quantities of radioactive fission products, including gases, particulates, and iodine, were released into the enclosed reactor building atmosphere from failed fuel in the reactor core. Air samples of the reactor building atmosphere showed /sup 85/Kr with a 10.7-yr half-life to be the principal remaining radionuclide. To permit less restricted access to the reactor building and to proceed toward decontamination of the TMI-2 facility, it was necessary to remove the /sup 85/Kr and to provide a suitable environment for workers. The venting was conducted between June 28 and July 11, 1980. The paper discusses reactor building air sampling, venting of the reactor building, radioactivity released to the environment, and the internal dosimetry program.},
doi = {},
url = {https://www.osti.gov/biblio/5684426}, journal = {Trans. Am. Nucl. Soc.; (United States)},
number = ,
volume = 57,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1988},
month = {Fri Jan 01 00:00:00 EST 1988}
}

Conference:
Other availability
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