Nuclear power plant accident simulations of gasket materials under simultaneous radiation plus thermal plus mechanical stress conditions
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.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 508139
- Report Number(s):
- SAND-97-1666; ON: DE97007940; TRN: 97:013422
- Resource Relation:
- Other Information: PBD: Jul 1997
- Country of Publication:
- United States
- Language:
- English
Similar Records
The power of simplification: Operator interface with the AP1000{sup R} during design-basis and beyond design-basis events
H-Canyon Jumper Gasket Sealing Evaluation