Assessment of thermal damage to polymeric materials by hydrogen deflagration in the reactor building
Description
Thermal damage to susceptible material in accessible regions of the reactor building was distributed in nonuniform patterns. No clear explanation for nonuniformity 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, the authors assume the unburned materials preferentially absorbed water vapor during periods of high, local steam concentration. Simple hydrogen-fire-exposure tests and heat transfer calculations duplicate the degree of damage found on inspected materials from the containment building. These data support estimated 8% pre-fire hydrogen concentration predictions based on various hydrogen production mechanisms
Additional details
Publishing Information
- Publisher
- American Chemical Society.
- Imprint Place
- Washington, DC (USA)
- ISBN
- 0-8412-0948-0
- Imprint Title
- The Three Mile Island accident. Diagnosis and prognosis
- Journal Page Range
- p. 60-86.
Conference
- Title
- 189. national meeting of the American Chemical Society.
- Dates
- 28 Apr - 3 May 1985.
- Place
- Miami, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18010091
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABSORPTION; ALGORITHMS; BUILDING MATERIALS; COMBUSTION; CONTAINMENT BUILDINGS; DATA PROCESSING; DESTRUCTIVE TESTING; FIRES; HEAT TRANSFER; HYDROGEN; INSPECTION; LOSS OF COOLANT; POLYMERS; PRODUCTION; QUANTITY RATIO; REACTOR MATERIALS; STEAM; THERMAL DEGRADATION; THREE MILE ISLAND-2 REACTOR; WATER VAPOR
- Descriptors DEC
- ACCIDENTS; BUILDINGS; CHEMICAL REACTIONS; CONTAINMENT; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUIDS; GASES; MATERIALS; MATERIALS TESTING; NONMETALS; OXIDATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; TESTING; THERMAL REACTORS; VAPORS; WATER COOLED REACTORS; WATER MODERATED REACTORS