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Title: RESULTS OF NS SAVANNAH CORE I FUEL ROD IRRADIATION PROGRAM

Technical Report ·
OSTI ID:4840110

An irradiation test program was carried out to confirm the NMSR Core I fuel rod design. This program provided data on the behavior of the UO/sub 2/ fuel and stainless steel cladding materials tested in the range of Core I operating conditions. The coolant water temperature and pressure are 508 F and 1750 psi. The average and maximum fuel rod heat fluxes are 62000 and 234,000 Btu/hr-ft/sub 2/ with a maximum burnup of 16,700 Mwd/ton of oxide. Irradiations were conducted in a high temperature and pressure dynamic water loop and in static capsules. UO/sub 2/ fuel rods clad in stainiess steel performed satisfactorily during irradiation. Heat ratings, thermal conditions, and burnup conditions bracketed Core I design maximum and average condi tions. Satisfactory performance is based on insignificant dimensional changes, the integrity of the cladding, end caps, and welds, and fuel pellet stability, and fission gas retention characteristics. Loop irradiations were conducted in B&W's MTR test loop at a water temperature and pressure of 500 deg F and 1500 psi. For the seven fuel rod specimens irradiated, the average cladding surface heat flux was approximately 100,000 Btu/hr-ft/sup 2/. No harmful effects were noted. Fuel burnups ranged from 550 to 1100 Mwd/ ton of oxide. The static tests were conducted in open process water and in sealed NaK capsules. Fuel rod specimens were irradiated to burnups of 350 to 16500 Mwd/ton of oxide. Cladding surface heat fluxes varied from 200,000 to 330,000 Btu/hr-ft/sup 2/. There was no evidence of cladding failure or distortion. A sublimation-condensation process caused some fuel redistribution at the higher heat ratings. Fission gas release varied from 4% at low heat rating to 10% at the higher ratings. (auth)

Research Organization:
Babcock and Wilcox Co. Atomic Energy Div., Lynchburg, Va.
DOE Contract Number:
AT(30-3)-274
NSA Number:
NSA-16-019434
OSTI ID:
4840110
Report Number(s):
BAW-1247
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English