Lower head creep-rupture sensitivity studies

Journal Article · Sat Jun 01 04:00:00 EDT 1991 · Nuclear Science and Engineering; (United States)

OSTI ID:5559683

Dosanjh, S S; Pilch, M ^[1]

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1. Sandia National Labs., Albuquerque, NM (United States)

During hypothetical severe nuclear reactor accidents, structural materials in the reactor vessel can relocate downward and form debris regions above the lower head. In this paper a one-dimensional model is presented that considers melt progression in the debris as well as the thermal and mechanical response of the head. Only creep rupture of the lower head is considered; however, other modes of vessel failure can be considered with the methodology developed, and the model can easily be extended to higher dimensions. Numerical solutions are compared with an analytical model developed by T.G. Theofanous. The goal of the work is to identify the parameters that most affect the state of the debris at the time of lower head creep rupture. Results of sensitivity analyses presented indicate that melt relocation phenomena, the initial composition profile of the debris, and the pressure inside the vessel are all important. On the other hand, changing the porosity or the particle diameter produces less significant effects because several competing phenomena cancel each other.

• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5559683
• Journal Information: Nuclear Science and Engineering; (United States), Journal Name: Nuclear Science and Engineering; (United States) Vol. 108:2; ISSN 0029-5639; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANALYTICAL SOLUTION
CONTAINERS
CREEP
FAILURES
LOSS OF COOLANT
MECHANICAL PROPERTIES
NUMERICAL SOLUTION
ONE-DIMENSIONAL CALCULATIONS
PRESSURE GRADIENTS
PRESSURE VESSELS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
REACTOR VESSELS
RUPTURES
SENSITIVITY ANALYSIS
SIMULATION