GESTR: a model for the prediction of GE BWR fuel rod thermal/mechanical performance

Technical Report · Wed Mar 01 04:00:00 EST 1978

OSTI ID:6806593

Johansson, E B; Potts, G A; Rand, R A

The document provides a description of GESTR, a model for the prediction of GE BWR fuel rod thermal/mechanical performance. The GESTR model incorporates the effects of fuel/cladding thermal expansion, fuel/cladding creep and fuel irradiation swelling, densification, relocation, and fission gas release as they affect pellet-cladding thermal conductance, fuel rod internal pressure, and pellet/cladding mechanical interaction. This document provides a description of the GESTR individual model elements in addition to qualification of the integral model by comparison of GESTR predictions to experimental fuel rod deformation, pellet-cladding thermal conductance, fission gas release, and fuel rod internal pressure data.

• Research Organization: General Electric Co., San Jose, Calif. (USA). Nuclear Energy Engineering Div.
• OSTI ID: 6806593
• Report Number(s): NEDO-23785
• Country of Publication: United States
• Language: English

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