Assessment of extent and degree of thermal damage to polymeric materials in the Three Mile Island Unit 2 Reactor building [electronic resource].
- Published
- Livermore, Calif : Lawrence Livermore National Laboratory, 1985.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 11 : digital, PDF file
- Additional Creators
- Lawrence Livermore National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- This paper describes assumptions and procedures used to perform thermal damage analysis caused by post loss-of-coolant-accident (LOCA) hydrogen deflagration at Three Mile Island Unit 2 Reactor. Examination of available photographic evidence yields data on the extent and range of thermal and burn damage. Thermal damage to susceptible material in accessible regions of the reactor building was distributed in non-uniform patterns. No clear explanation for non-uniformity was found in examined evidence, e.g., burned materials were adjacent to materials that appear similar but were not burned. Because these items were in proximity to vertical openings that extend the height of the reactor building, we assume the unburned materials preferentially absorbed water vapor during periods of high, local steam concentration. A control pendant from the polar crane located in the top of the reactor building sustained asymmetric burn damage of decreasing degree from top to bottom. Evidence suggests the polar-crane pendant side that experienced heaviest damage was exposed to intense radiant energy from a transient fire plume in the reactor containment volume. Simple hydrogen-fire-exposure tests and heat transfer calculations approximate the degree of damage found on inspected materials from the containment building and support for an estimated 8% pre-fire hydrogen.
- Report Numbers
- E 1.99:ucrl-92070
E 1.99: conf-851098-1
conf-851098-1
ucrl-92070 - Subject(s)
- Other Subject(s)
- Three Mile Island-2 Reactor
- Fires
- Reactor Accidents
- Combustion
- Damage
- Hydrogen
- Inspection
- Loss Of Coolant
- Accidents
- Chemical Reactions
- Elements
- Enriched Uranium Reactors
- Nonmetals
- Oxidation
- Power Reactors
- Pwr Type Reactors
- Reactors
- Thermal Reactors
- Thermochemical Processes
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
06/01/1985.
"ucrl-92070"
" conf-851098-1"
"TI85013822"
International fire safety meeting, Gaithersburg, MD, USA, 7 Oct 1985.
Alvares, N.J. - Funding Information
- W-7405-ENG-48
View MARC record | catkey: 14369021