Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

A preliminary assessment of the effects of heat flux distribution and penetration on the creep rupture of a reactor vessel lower head

Conference ·
OSTI ID:467948
; ;  [1];  [2]
  1. Sandia National Labs., Albuquerque, NM (United States)
  2. Univ. of Wisconsin, Madison, WI (United States)

The objective of the Lower Head Failure (LHF) Experiment Program is to experimentally investigate and characterize the failure of the reactor vessel lower head due to thermal and pressure loads under severe accident conditions. The experiment is performed using 1/5-scale models of a typical PWR pressure vessel. Experiments are performed for various internal pressure and imposed heat flux distributions with and without instrumentation guide tube penetrations. The experimental program is complemented by a modest modeling program based on the application of vessel creep rupture codes developed in the TMI Vessel Investigation Project. The first three experiments under the LHF program investigated the creep rupture of simulated reactor pressure vessels without penetrations. The heat flux distributions for the three experiments are uniform (LHF-1), center-peaked (LHF-2), and side-peaked (LHF-3), respectively. For all the experiments, appreciable vessel deformation was observed to initiate at vessel wall temperatures above 900K and the vessel typically failed at approximately 1000K. The size of failure was always observed to be smaller than the heated region. For experiments with non-uniform heat flux distributions, failure typically occurs in the region of peak temperature. A brief discussion of the effect of penetration is also presented.

Research Organization:
Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States)
DOE Contract Number:
AC04-94AL85000
OSTI ID:
467948
Report Number(s):
NUREG/CP--0157-VOL.2; CONF-9610202--Vol.2; ON: TI97004274
Country of Publication:
United States
Language:
English

Similar Records

Experimental investigation of creep rupture of reactor vessel lower head
Journal Article · Sun Nov 30 23:00:00 EST 1997 · Transactions of the American Nuclear Society · OSTI ID:555362

Experimental investigation of creep behavior of reactor vessel lower head
Conference · Sat Feb 28 23:00:00 EST 1998 · OSTI ID:645478

TMI-2 lower head creep rupture analysis
Technical Report · Mon Aug 01 00:00:00 EDT 1988 · OSTI ID:6188768