Manufacture of Fuel Plates for the Experimental Boiling Water Reactor

Macherey, R.E.; Bean, C.H.; Carson, N.J.; Lindgren, Jenny

doi:10.2172/4316422

Cited by 3 publications

(3 citation statements)

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“…Other than establishing the hardnesses of the three layers making up the bond zone between the AI-U3O8 fuel and the Zircaloy-2 cladding, no attempt was made to determine the nature of the bond. 1 The bonded fuel-rod specimen was cycled by slow^ heating to 300°C and air-cooling, and by subsequent heating to 300°C in oil and waterquenching. The diffusion bond between the fuel and cladding prevented ratcheting or shortening of the fuel in both cases.…”

Section: Fuel Developmentmentioning

confidence: 99%

FABRICATION OF SPIKED-CORE FUEL ELEMENTS FOR THE EXPERIMENTAL BOILING WATER REACTOR. Final Report

Kramer¹,

McCuaig²,

Beatty³

et al. 1965

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Section: Fuel Developmentmentioning

confidence: 99%

FABRICATION OF SPIKED-CORE FUEL ELEMENTS FOR THE EXPERIMENTAL BOILING WATER REACTOR. Final Report

Kramer¹,

McCuaig²,

Beatty³

et al. 1965

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“…The molybdenum used was in the form of pieces of --in.-thick plate 8 or in the form of sintered pressed pellets. Ruthenium, rhodium, palladium, and niobium were in the form of sintered pressed pellets.…”

Section: Alloy Preparationmentioning

confidence: 99%

Preparation of Alloy for First Core Loading of Ebr-Ii

Hampson¹

1961

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“…The Zircaloy-2 cladding was metallurgically bonded to the fuel core by roll cladding using the plate and frame process. (4,5) The finished fuel plates were assembled into a fixture with Zircaloy-2 side plates and spot welded into completed fuel elements.…”

Section: Introductionmentioning

confidence: 99%

Examination of Irradiated Ebwr Core-1 Fuel Elements

Reinke¹,

Carlander²

1960

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Two fuel elements were removed from the Experimental Boiling Water Reactor at Argonne National Laboratory and examined in a hot cell. The elements had maximum burnups of 0.11 a/o and 0.39 a/o, respectively. Both were disassembled and sampled for the evaluation of the effects of in-pile operation and radiation damage to the fuel.The fuel elements were in good condition with no ruptured cladding, core-clad nonbonds, or excessive fuel plate swelling or warpage. Thin samples cut from the fuel plates in element ET-51 warped and cracked, suggesting a relieving of locked-in stresses and indicating that after 0.39 a/o burnup the fuel cores were hard, brittle and highly stressed.The rate of fuel plate volume increase due to the burnup of uranium was 6 to 7% AV per a/o burnup. Hydrogen was picked up by the fuel plates under reactor operating conditions with the probable formation of isolated areas of small amounts of zirconium hydride. Annealing studies on sections of fuel plate at 500°C and 550°C indicated bulk volume increases of 1 to 2% and 5 to 10%, respectively, after 500 hours. A 600 °C anneal resulted in a bulk volume increase of 17% after 45 hours.

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Manufacture of Fuel Plates for the Experimental Boiling Water Reactor

Cited by 3 publications

References 0 publications

FABRICATION OF SPIKED-CORE FUEL ELEMENTS FOR THE EXPERIMENTAL BOILING WATER REACTOR. Final Report

FABRICATION OF SPIKED-CORE FUEL ELEMENTS FOR THE EXPERIMENTAL BOILING WATER REACTOR. Final Report

Preparation of Alloy for First Core Loading of Ebr-Ii

Examination of Irradiated Ebwr Core-1 Fuel Elements

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