Multiple Irradiation Capsule Experiment (MICE)-3B Irradiation Test of Space Fuel Specimens in the Advanced Test Reactor (ATR) - Close Out Documentation for Naval Reactors (NR) Information

Chen, M. ; Regan, CM ; Noe, D.

Knolls Atomic Power Laboratory

关键词: Fission;    Testing;    Irradiation;    Nesdps Office Of Nuclear Energy Space And Defense Power Systems;    Documentation;   

DOI  :  10.2172/883628
RP-ID  :  MDO-723-0015
RP-ID  :  DE-AC12-00SN39357
RP-ID  :  883628

美国|英语

来源: UNT Digital Library

【 摘 要 】

Few data exist for UO{sub 2} or UN within the notional design space for the Prometheus-1 reactor (low fission rate, high temperature, long duration). As such, basic testing is required to validate predictions (and in some cases determine) performance aspects of these fuels. Therefore, the MICE-3B test of UO{sub 2} pellets was designed to provide data on gas release, unrestrained swelling, and restrained swelling at the upper range of fission rates expected for a space reactor. These data would be compared with model predictions and used to determine adequacy of a space reactor design basis relative to fission gas release and swelling of UO{sub 2} fuel and to assess potential pellet-clad interactions. A primary goal of an irradiation test for UN fuel was to assess performance issues currently associated with this fuel type such as gas release, swelling and transient performance. Information learned from this effort may have enabled use of UN fuel for future applications.