Published February 1986 | Version v1
Report Metadata-only

Tellurium chemistry, tellurium release and deposition during the TMI-2 accident

Creators

  • 1. EG and G Idaho Inc., Idaho Falls

Description

This paper presents the chemistry and estimated behavior of tellurium during and after the accident at Three Mile Island Unit-2. The discussion of tellurium behavior is based on all available measurement data for /sup 129m/Te, 132Te, stable tellurium (126Te, 128Te, and 130Te), and best estimate calculations of tellurium release and transport. Results from Oak Ridge National Laboratory tests, Power Burst Facility Severe Fuel Damage Tests at Idaho National Engineering Laboratory and SASCHA tests from Karlsruhe, West Germany are compared with calculated release fractions and samples taken from TMI Unit-2. It is concluded that very little tellurium was released and transported from the TMI-2 core, probably as a result of holdup by zircaloy cladding and other structural materials

Additional details

Publishing Information

Imprint Title
Thirteenth water reactor safety research information meeting: proceedings. Volume 6
Journal Page Range
p. 397-420.
Report number
NUREG/CP--0072-Vol.6

Conference

Title
13. water reactor safety research information meeting.
Dates
22-25 Oct 1985.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18002593
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL CANS; IDAHO NATIONAL ENGINEERING LAB; ORNL; OXIDATION; PRIMARY COOLANT CIRCUITS; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; TELLURIUM; THREE MILE ISLAND-2 REACTOR; VOLATILITY; ZIRCALOY
Descriptors DEC
ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; COOLING SYSTEMS; ELEMENTS; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; NATIONAL ORGANIZATIONS; POWER REACTORS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SEMIMETALS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS