Accelerated Testing of the CSNF Waste Form: Applicability to Yucca Mountain

Hanson, B. ; Buck, E. ; Brady, P.

United States. Department of Energy. Yucca Mountain Project Office.

关键词: Flow Rate;    Waste Forms;    Wastes;    Radioisotopes;    11 Nuclear Fuel Cycle And Fuel Materials;   

DOI  :  10.2172/840138
RP-ID  :  NONE
RP-ID  :  NONE
RP-ID  :  840138

美国|英语

来源: UNT Digital Library

【 摘 要 】

Spent fuel tests in support of Yucca Mountain have been performed for many years. Most of these tests have been either single-pass flowthrough (SPFT) or unsaturated drip tests that have been used to elucidate waste form degradation rates. In general, the tests have been considered accelerated tests per the definition found in ASTM Standard C1174 in that either the temperature or flow rate has been increased in order to increase the rate of alteration. However, as the design and models for the proposed repository have solidified, it is clear that much of what was originally considered an accelerated test is, in reality, either a service condition test or a test that determines bounding conditions that grossly overestimate radionuclide degradation and release rates under repository relevant conditions. This presentation will examine the factors that need to be considered for future waste form, including waste package internals, degradation tests.