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Title: MARVEL Reactor Fuel Performance Report

S&T Accomplishment Report ·
OSTI ID:2000862

The Microreactor Applications Research Validation and EvaLuation (MARVEL) project will produce a test bed at the Idaho National Laboratory (INL) for performing research and development on various operational features of microreactors to ultimately improve integration of microreactors to end-user applications. In order to construct and operate the MARVEL reactor in a timely manner, the system will utilize materials and component designs which have already been used, qualified, or licensed from previous reactors. The MARVEL reactor will be located at the INL Transient Reactor Test (TREAT) facility in the north high-bay equipment pit and will use standard “off-the-shelf” U-ZrHx fuel purchased from the commercial vendor, TRIGA International. This report enables the prediction of U-ZrHx fuel performance calculations and simulations under MARVEL irradiation conditions. The information contained herein is compiled from a combination of historical reports and peer reviewed scientific publication manuscripts. Known failure mechanisms under which the fuel is susceptible to failure are highlighted and compared to conditions that could exist in the MARVEL reactor during an unanticipated transient or accident scenario. Ultimately, the purpose of this report is to provide a comprehensive survey of the known thermophysical properties, performance, and quantitative relationships associated with the MARVEL reactor fuel element and to use this information to determine its mechanical integrity during the most extreme accident scenario predicted for the reactor using the most conservative, unideal assumptions available. This analysis indicates that the MARVEL fuel element maintains its structural integrity during the most extreme accident scenario predicted for the MARVEL reactor during which the maximum hoop stress generated in the cladding reaches only 8.21 MPa, far less than the predicted yield strength of 304 SS under accident scenario conditions (about 189 MPa). This analysis suggests that the fuel temperature limit of about 950 °C is accurate in order to avoid internal gas overpressurization and cladding damage, which is far beyond the maximum temperature predicted in MARVEL fuel of about 680 °C.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
58
DOE Contract Number:
DE-AC07-05ID14517
OSTI ID:
2000862
Report Number(s):
INL/RPT-22-68555-Rev001
Country of Publication:
United States
Language:
English