West German Research Programs on Irradiation Effects on Reactor Pressure Vessels

K Kussmaul

doi:10.1520/STP31845S

SYMPOSIA PAPER Published: 01 January 1983

STP31845S

West German Research Programs on Irradiation Effects on Reactor Pressure Vessels

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Reactor pressure vessels of nuclear installations are subjected to operating parameters that lead to a change in material and flaw state. The safety margin of both the material for older vessels and the optimized material has to be quantified with reference to extremely long-term effects. Research programs in West Germany are focused on assessing criteria for the applicability of small-scale specimen testing to component behavior under all realistic and postulated loading conditions. The problem will be treated theoretically and experimentally for a wide range of materials, including the worst-case material state at the end of life.

Author Information

Kussmaul, K

Staatliche Materialprüfungsanstalt, University of Stuttgart, Stuttgart, West Germany

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Details

Developed by Committee: E10

Pages: 16–28

DOI: 10.1520/STP31845S

ISBN-EB: 978-0-8031-4885-7

ISBN-13: 978-0-8031-0263-7

West German Research Programs on Irradiation Effects on Reactor Pressure Vessels

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