Details
Originalsprache | Englisch |
---|---|
Seiten (von - bis) | 433-439 |
Seitenumfang | 7 |
Fachzeitschrift | KERNTECHNIK |
Jahrgang | 85 |
Ausgabenummer | 6 |
Publikationsstatus | Veröffentlicht - 23 Feb. 2021 |
Abstract
Within the scope of the pending search for a final storage site location for highly radioactive waste such as used fuel assemblies, the cladding integrity in case of a relocation of the rod from an interim storage to a final storage cask remains uncertain. In order to assess the potential reduction of the rod integrity by hydride precipitation and reorientation, a study of the long-term behaviour of hydrides in Zircaloy 2 is carried out. The focus is on simulation and analysis of the precipitation behaviour under different load conditions such as starting temperatures of 673 K, hoop stresses of up to 150 MPa and cooling rates between 4 and 1 K/h. The analytical methods comprised microscopic investigations as well as X-ray diffraction analyses and first results from imaging with X-rays.
ASJC Scopus Sachgebiete
- Physik und Astronomie (insg.)
- Strahlung
- Physik und Astronomie (insg.)
- Kern- und Hochenergiephysik
- Energie (insg.)
- Kernenergie und Kernkraftwerkstechnik
- Werkstoffwissenschaften (insg.)
- Allgemeine Materialwissenschaften
- Ingenieurwesen (insg.)
- Sicherheit, Risiko, Zuverlässigkeit und Qualität
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in: KERNTECHNIK, Jahrgang 85, Nr. 6, 23.02.2021, S. 433-439.
Publikation: Beitrag in Fachzeitschrift › Artikel › Forschung › Peer-Review
}
TY - JOUR
T1 - Investigation of the temporal rearrangement of zirconium hydride precipitates in cladding material for the interim and final storage period
AU - Bongartz, Benedict
AU - Hassel, Thomas
N1 - Funding Information: The authors gratefully acknowledge financial support by the German Federal Ministry for Economic Affairs and Energy (BMWi) under contract no. 1501560 and the Framatome GmbH for the provision of the used Zircaloy 2 cladding tubes.
PY - 2021/2/23
Y1 - 2021/2/23
N2 - Within the scope of the pending search for a final storage site location for highly radioactive waste such as used fuel assemblies, the cladding integrity in case of a relocation of the rod from an interim storage to a final storage cask remains uncertain. In order to assess the potential reduction of the rod integrity by hydride precipitation and reorientation, a study of the long-term behaviour of hydrides in Zircaloy 2 is carried out. The focus is on simulation and analysis of the precipitation behaviour under different load conditions such as starting temperatures of 673 K, hoop stresses of up to 150 MPa and cooling rates between 4 and 1 K/h. The analytical methods comprised microscopic investigations as well as X-ray diffraction analyses and first results from imaging with X-rays.
AB - Within the scope of the pending search for a final storage site location for highly radioactive waste such as used fuel assemblies, the cladding integrity in case of a relocation of the rod from an interim storage to a final storage cask remains uncertain. In order to assess the potential reduction of the rod integrity by hydride precipitation and reorientation, a study of the long-term behaviour of hydrides in Zircaloy 2 is carried out. The focus is on simulation and analysis of the precipitation behaviour under different load conditions such as starting temperatures of 673 K, hoop stresses of up to 150 MPa and cooling rates between 4 and 1 K/h. The analytical methods comprised microscopic investigations as well as X-ray diffraction analyses and first results from imaging with X-rays.
UR - http://www.scopus.com/inward/record.url?scp=85098919127&partnerID=8YFLogxK
U2 - 10.3139/124.200070
DO - 10.3139/124.200070
M3 - Article
AN - SCOPUS:85098919127
VL - 85
SP - 433
EP - 439
JO - KERNTECHNIK
JF - KERNTECHNIK
SN - 0932-3902
IS - 6
ER -