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AFIP-7 Irradiation Summary Report

Technical Report ·
DOI:https://doi.org/10.2172/1083244· OSTI ID:1083244
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  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
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The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-7 was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels in geometries which are prototypic of US high power research reactor (HPRR) fuel plates. The following report summarizes the life of the AFIP-7 experiment through end of irradiation, including a brief description of the safety analysis, as-run neutronic analysis results, hydraulic testing results, and thermal analysis results.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
DOE Contract Number:
AC07-05ID14517
OSTI ID:
1083244
Report Number(s):
INL/EXT--12-25915
Country of Publication:
United States
Language:
English

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AFIP-7
Irradiation
Report
Summary