The probability of Mark-I containment failure by melt-attack of the liner
- California Univ., Santa Barbara, CA (United States). Dept. of Chemical and Nuclear Engineering
- Rensselaer Polytechnic Inst., Troy, NY (United States). Dept. of Nuclear Engineering and Engineering Physics; and others
This report is a followup to the work presented in NUREG/CR-5423 addressing early failure of a BWR Mark I containment by melt attack of the liner, and it constitutes a part of the implementation of the Risk-Oriented Accident Analysis Methodology (ROAAM) employed therein. In particular, it expands the quantification to include four independent evaluations carried out at Rensselaer Polytechnic Institute, Argonne National Laboratories, Sandia National Laboratories and ANATECH, Inc. on the various portions of the phenomenology involved. These independent evaluations are included here as Parts II through V. The results, and their integration in Part I, demonstrate the substantial synergism and convergence necessary to recognize that the issue has been resolved.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; California Univ., Santa Barbara, CA (United States). Dept. of Chemical and Nuclear Engineering; Rensselaer Polytechnic Inst., Troy, NY (United States). Dept. of Nuclear Engineering and Engineering Physics; Sandia National Labs., Albuquerque, NM (United States); Argonne National Lab., IL (United States); ANATECH Research Corp., San Diego, CA (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38; AC04-94AL85000
- OSTI ID:
- 10107249
- Report Number(s):
- NUREG/CR--6025; SAND--93-0893; SAND--93-0925; ANA--92-0143; ANL/RE/LWR--92-5; ON: TI94003993; BR: GB0103012
- Country of Publication:
- United States
- Language:
- English
Similar Records
The probability of liner failure in a Mark-I containment, Part 1: probabilistic framework and results
The probability of liner failure in a Mark-I containment, Part III: corium/concrete interactions and liner attack phenomena
Related Subjects
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
CONCRETES
CONTAINMENT
CORIUM
CREEP
HEAT TRANSFER
HYDRAULICS
INTERACTIONS
LINERS
MELTDOWN
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
REACTOR SAFETY
RUPTURES