Capability of LMFBR Plant Structures Beyond the Design Base

by George N. Freskakis, Burns & Roe Inc, Oradell, NJ, USA,



Document Type: Proceeding Paper

Part of: Structural Engineering in Nuclear Facilities

Abstract:

A study is presented concerning the capability of structures in a loop type Liquid Metal Fast Breeder Reactor Plant, the Clinch River Breeder Reactor Plant (CRBRP), to sustain conditions imposed by a beyond the design basis hypothetical core meltdown accident and meet the requirements for the protection of the environment and the health and safety of the public. Following a meltdown, containment structures would be subjected to severe elevated temperatures and possibly sodium concrete reactions that would result in deterioration of concrete and in generation of hydrogen. Potential scenarios of events, requirements imposed on structures, consideration of sodium concrete reactions, properties of concrete at elevated temperature, failure criteria, and analytical evaluations for the capability of concrete structures are discussed. Evaluations indicate that the CRBRP design, augmented for such an accident, provides sufficient margin for the structures to meet the imposed requirements. Augmented design includes annulus cooling, addition of insulation, increases in reinforcing steel, modifications in re-bar location, liner anchorage, and provisions in vent system.

Subject Headings: Concrete | Structural design | Temperature effects | Structural safety | Concrete structures | Accidents | Structural analysis

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