Calculations of the surface heat flux and fuel temperatures for PRTR MK-I PuO{sub 2}-UO{sub 2} fuel element with segregated PuO{sub 2}

Technical Report · Wed Jan 02 04:00:00 EST 1963

DOI:https://doi.org/10.2172/10180338· OSTI ID:10180338

Zaloudek, F R; Hesson, G M

The methods used to fabricate the present loading of PuO{sub 2}-UO{sub 2} fuel elements for the Plutonium Recycle Test Reactor have resulted in alternating bands of high and low PuO{sub 2} concentration along each rod of the 19-rod elements. These bands are repeated every 1/2 or 1 inch along the length of the rod, depending on whether the loading of the oxides was done in 160 or 80 increments. This non-uniform distribution of PuO{sub 2} results in alternate regions of high and low heat generation rates with a direct influence on surface heat flux and fuel temperatures. Calculations were performed to determine the local surface heat fluxes and fuel temperatures in a rod of a PRTR 19-rod cluster PuO{sub 2}-UO{sub 2} fuel element. The results indicated that peak to average flux ratios of 2.37 could occur for fuel rods loaded in 80 increments (1 inch total band length) if no mixing of the PuO{sub 2}-bearing powder occurs with the UO{sub 2} powder. This would result in maximum heat flux of 660,000 Btu/hr-sq ft for a fuel element operating at a tube power of 1,200 KW. For a rod loaded in 160 increments (1/2 inch total band length), the peak heat flux ratio was calculated to be 1.35 (475,000 Btu/hr-sq ft for a 1,200 KW fuel element). These heat flux ratios as well as fuel temperatures are shown in Figures 1 through 4 for two different values of maximum PuO{sub 2} concentration.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10180338
• Report Number(s): HW--76115; ON: DE94018251
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
FUEL ELEMENTS
HEAT FLUX
HISTORICAL ASPECTS
MIXED OXIDE FUELS
PLUTONIUM OXIDES
POWER DISTRIBUTION
POWER REACTORS
NONBREEDING
OTHERWISE MODERATED OR UNMODERATED
PRTR REACTOR
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SPATIAL DISTRIBUTION
TEMPERATURE DISTRIBUTION
THEORETICAL DATA
URANIUM OXIDES