Eine Plattform für die Wissenschaft: Bauingenieurwesen, Architektur und Urbanistik
Eine Plattform für die Wissenschaft: Bauingenieurwesen, Architektur und Urbanistik
Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask (Preprint)
The VSC-17 Spent Nuclear Fuel Storage Cask was surveyed for degradation of the concrete shield by radiation measurement, temperature measurement, and ultrasonic testing. No general loss of shielding function was identified.
Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask (Preprint)
The VSC-17 Spent Nuclear Fuel Storage Cask was surveyed for degradation of the concrete shield by radiation measurement, temperature measurement, and ultrasonic testing. No general loss of shielding function was identified.
Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask (Preprint)
S. L. Morton (Autor:in) / P. L. Winston (Autor:in) / T. Saegusa (Autor:in) / K. Shirai (Autor:in) / A. Sasahara (Autor:in)
2006
9 pages
Report
Keine Angabe
Englisch
Radiation Shielding, Protection, & Safety , Radioactive Wastes & Radioactivity , Reactor Fuels & Fuel Processing , Spent fuel casks , Concretes , Nuclear fuels , Shielding , Performance , Radiations , Radioactive waste management , Storage , Temperature measurement , Ultrasonic testing , Spent fuels
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