TMI-2 (Three Mile Island Unit 2): The early radiological conditions of the reactor building
Shortly following the accident at Three Mile Island Unit 2 (TMI-2), GPU Nuclear, along with Bechtel Power Corporation nuclear specialists, established a Containment Assessment Task Force (CATF) to assess the radiological conditions of the TMI-2 reactor building of containment. The task force was to devise and execute a series of experiments and analyses to obtain those data necessary for initial entry, containment purge, and containment recovery. The analyses and experiments were designed to assess the following: (1) airborne levels, (2) levels of surface contaminations, (3) magnitude of the basement water source term, and (4) general radiological environment within the containment. The early tasks performed under the CATF were postaccident airborne samples, remote Ge(Li) gamma-ray scans through the containment equipment hatch, remote gamma-ray scans with NaI crystals through spare containment penetrations, radiation survey maps of the containment personnel airlock, retrieval of an actual sample of the water in the containment basement, and remote television and radiation monitors installed through a penetration into the containment.
- OSTI ID:
- 5619367
- Report Number(s):
- CONF-881011-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 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
Similar Records
The role of radiation instruments in the recovery of TMI-2 (Three Mile Island Unit 2)
TMI-2 (Three Mile Island Unit 2) reactor building dose reduction task force
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTAINMENT BUILDINGS
ACTIVITY LEVELS
THREE MILE ISLAND-2 REACTOR
REACTOR ACCIDENTS
AEROSOLS
BASEMENTS
CESIUM ISOTOPES
CONTAINMENT SYSTEMS
GAMMA DETECTION
IODINE 131
LI-DRIFTED GE DETECTORS
NAI DETECTORS
ORNL
RADIATION DOSES
RADIATION MONITORS
RECOVERY
REMOTE VIEWING EQUIPMENT
SAMPLING
SHIELDING
SOURCE TERMS
THREE-DIMENSIONAL CALCULATIONS
TIME DEPENDENCE
TRITIUM
WATER
XENON ISOTOPES
ACCIDENTS
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDINGS
COLLOIDS
CONTAINMENT
DAYS LIVING RADIOISOTOPES
DETECTION
DISPERSIONS
DOSES
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
GE SEMICONDUCTOR DETECTORS
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
INTERMEDIATE MASS NUCLEI
IODINE ISOTOPES
ISOTOPES
LI-DRIFTED DETECTORS
LIGHT NUCLEI
MEASURING INSTRUMENTS
MONITORS
NATIONAL ORGANIZATIONS
NUCLEI
ODD-EVEN NUCLEI
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
RADIATION DETECTION
RADIATION DETECTORS
RADIOISOTOPES
REACTORS
SCINTILLATION COUNTERS
SEMICONDUCTOR DETECTORS
SOLID SCINTILLATION DETECTORS
SOLS
THERMAL REACTORS
US AEC
US DOE
US ERDA
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