Nuclear power plant accident simulations of gasket materials under simultaneous radiation plus thermal plus mechanical stress conditions Metadata

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Title

  • Main Title Nuclear power plant accident simulations of gasket materials under simultaneous radiation plus thermal plus mechanical stress conditions

Creator

  • Author: Gillen, K.T.
    Creator Type: Personal
  • Author: Malone, G.M.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Office of the Assistant Secretary for Nuclear Energy.
    Contributor Type: Organization
    Contributor Info: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)

Publisher

  • Name: Sandia National Laboratories
    Place of Publication: Albuquerque, New Mexico
    Additional Info: Sandia National Labs., Albuquerque, NM (United States)

Date

  • Creation: 1997-07-01

Language

  • English

Description

  • Content Description: In order to probe the response of silicone door gasket materials to a postulated severe accident in an Italian nuclear power plant, compression stress relaxation (CSR) and compression set (CS) measurements were conducted under combined radiation (approximately 6 kGy/h) and temperature (up to 230{degrees}C) conditions. By making some reasonable initial assumptions, simplified constant temperature and dose rates were derived that should do a reasonable job of simulating the complex environments for worst-case severe events that combine overall aging plus accidents. Further simplification coupled with thermal-only experiments allowed us to derive thermal-only conditions that can be used to achieve CSR and CS responses similar to those expected from the combined environments that are more difficult to simulate. Although the thermal-only simulations should lead to sealing forces similar to those expected during a severe accident, modulus and density results indicate that significant differences in underlying chemistry are expected for the thermal-only and the combined environment simulations. 15 refs., 31 figs., 15 tabs.
  • Physical Description: 44 p.

Subject

  • Keyword: Tensile Properties
  • Keyword: Gaskets
  • Keyword: Thermal Stresses
  • Keyword: Physical Radiation Effects
  • Keyword: Elongation
  • Keyword: Density
  • Keyword: Stress Relaxation
  • Keyword: Doors
  • Keyword: Reactor Accidents
  • Keyword: Mechanical Tests
  • Keyword: Compression Strength
  • Keyword: Silicones
  • STI Subject Categories: 22 Nuclear Reactor Technology

Source

  • Other Information: PBD: Jul 1997

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Other: DE97007940
  • Report No.: SAND--97-1666
  • Grant Number: AC04-94AL85000
  • DOI: 10.2172/508139
  • Office of Scientific & Technical Information Report Number: 508139
  • Archival Resource Key: ark:/67531/metadc690316

Note

  • Display Note: INIS; OSTI as DE97007940