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Experiment Description for PNL Mixed Oxides (UO2-PuO2) Irradiations in the General Electric Test Reactor

Technical Report ·
DOI:https://doi.org/10.2172/4086233· OSTI ID:4086233
 [1];  [1]
  1. Battelle Pacific Northwest Labs., Richland, WA (United States)
A fuel irradiation test program and capsule design is described for the evaluation of the steady state and transient performance characteristics of prototypic FTR length fuel pins. The fuel pins to be tested comprise 31 in. of mixed oxide (75% UO2-25%PuO2) fuel pellets clad in 0.250 in. diameter type 304 stainless steel. The fuel pellets are 93% of theoretical density (TD) and with a 0.006 in. diametrical gap the fuel has an 88% TD smeared density. The capsule is a NaK bonded instrumented assembly designed to produce a fuel pin cladding surface temperature of 800 °F and fuel central temperature of 4000 °F when the fuel pin is producing 14.5 kW/ft (axial peak). The safety analysis, heat transfer calculations and operating instructions are also described.
Research Organization:
Battelle Pacific Northwest Labs., Richland, WA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
DOE Contract Number:
AT(45-1)-1830
NSA Number:
NSA-24-046080
OSTI ID:
4086233
Report Number(s):
BNWL-1382
Country of Publication:
United States
Language:
English