| Autor: |
D. L. Knudson, K. L. Davis, B. M. Chase, J. L. Rempe |
| Rok vydání: |
2014 |
| Předmět: |
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| Popis: |
This document summarizes background information and presents results related to temperature measurements in the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) University of Illinois Project 29609 irradiation. The objective of this test was to assess the radiation performance of ferritic alloys for advanced reactor applications. The FeCr-based alloy system is considered the lead alloy system for a variety of advanced reactor components and applications. Irradiations of FeCr alloy samples were performed using the Hydraulic Shuttle Irradiation System (HSIS) in the B-7 position and in a static capsule in the A-11 position of the ATR. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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