Temperatures, strains and crack behavior during local thermal shock tests on the RPV-cylinder of the HDR

At the HDR, an inactive boiling water reactor at Karlstein, FRG, a series of thermal shock tests on the reactor pressure vessel (RPV) is already carried out, further tests are intended. This report summarises and critically discusses the results obtained from thermal shocks locally applied to the inner surface of the RPV-cylinder. This evaluation is based on on-line measurements (temperatures and strains at the RPV-wall during the thermal shock loading, non-destructive-testing), see fig. 1 , on materials investigations, see fig. 2 , and on theoretical investigations (finite element calculations, fracture mechanics analyses). The comparison between the corresponding measured and calculated results serves as a basis for subsequent assessments. Fig.1 Survey of Online Measurements on HDR-Vessel A diagram of thermal shock tests on a reactor pressure vessel. https://www.w3.org/1999/xlink" xlink:href="#long-desc177"/> https://www.w3.org/1999/xlink" xlink:href=" https://s3-euw1-ap-pe-df-pch-content-public-p.s3.eu-west-1.amazonaws.com/9781003763246/3dd1067a-243d-4b3a-b8d3-0e516be855dd/content/pg330_1.tif "/> Fig.2 Investigation of HDR-RPV Material A table comparing properties of base material and cladding for thermal shock tests on a reactor pressure vessel. https://www.w3.org/1999/xlink" xlink:href="#long-desc178"/> https://www.w3.org/1999/xlink" xlink:href=" https://s3-euw1-ap-pe-df-pch-content-public-p.s3.eu-west-1.amazonaws.com/9781003763246/3dd1067a-243d-4b3a-b8d3-0e516be855dd/content/pg330_2.tif "/>