Parametric study of pipe whip analysis
Technical Report
·
OSTI ID:5899473
In the Energy Balance Analysis Model (Standard Review Plan (USNRC, 1981), Section 3.6.2, ''Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping''), time dependence is not considered, and a constant blowdown thrust force is assumed. This force includes an amplification factor of 1.1 to account for potential effects of rebound. Many of the assumptions used in establishing the acceptance criteria, as stated in the Standard Review Plan, were based on engineering judgment and logic intended to assure upper bound design rather than on a mechanistic assessment of actual pipe rupture phenomena and their effects. As a result of the current practice an exceedingly conservative design may be introduced. This report represents a parametric study of the amplification factor to account for rebound effects in the Energy Balance Method. Of the 71 distinct cases we chose for our parametric study, the amplification factor of 1.1 seems sufficient except in five cases where the carbon steel pipes are small or have very small gaps between the pipes and the pipe whip restraints. We conclude that the amplification factor generally decreases as the parameters gap size, hinge-to-break distance and overhang increase. 9 refs., 13 figs., 8 tabs.
- Research Organization:
- Lawrence Livermore National Lab., CA (USA)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 5899473
- Report Number(s):
- NUREG/CR-5014; UCRL-21177; ON: TI88002680
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
AMPLIFICATION
AUSTENITIC STEELS
CARBON STEELS
COMPUTER CODES
DESIGN
FAILURES
FINITE ELEMENT METHOD
IRON ALLOYS
IRON BASE ALLOYS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL SOLUTION
PARAMETRIC ANALYSIS
PIPES
POWER PLANTS
REACTOR SAFETY
RESTRAINTS
RUPTURES
SAFETY
STEELS
THERMAL POWER PLANTS
W CODES
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
AMPLIFICATION
AUSTENITIC STEELS
CARBON STEELS
COMPUTER CODES
DESIGN
FAILURES
FINITE ELEMENT METHOD
IRON ALLOYS
IRON BASE ALLOYS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL SOLUTION
PARAMETRIC ANALYSIS
PIPES
POWER PLANTS
REACTOR SAFETY
RESTRAINTS
RUPTURES
SAFETY
STEELS
THERMAL POWER PLANTS
W CODES