The Irradiation and Examination of a Plutonium-Uranium Oxide Fast Reactor Fuel

JM Gerhart; JN Siltanen; JS Cochran

doi:10.1520/STP44393S

SYMPOSIA PAPER Published: 01 January 1962

STP44393S

The Irradiation and Examination of a Plutonium-Uranium Oxide Fast Reactor Fuel

Source

A program was carried out to study the irradiation behavior of a PuO₂-UO₂ fuel. Forty fuel specimens were fabricated, encapsulated, and irradiated in the General Electric Test Reactor to burnups ranging from 5000 to 99,000 Mw days per ton and heat fluxes ranging from 0.5 × 10⁶ to 1.58 × 10⁶ Btu per hr sq ft. A postirradiation examination of the fuel was made to determine the fuel condition, central void characteristics and fission gas release. The results of this program are presented and discussed.

Author Information

Gerhart, JM

General Electric Co., Atomic Power Equipment Department, Vallecitos Atomic Laboratory, Pleasanton, Calif.

Siltanen, JN

General Electric Co., Atomic Power Equipment Department, Vallecitos Atomic Laboratory, Pleasanton, Calif.

Cochran, JS

General Electric Co., Atomic Power Equipment Department, Vallecitos Atomic Laboratory, Pleasanton, Calif.

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Details

Developed by Committee: E10

Pages: 154–195

DOI: 10.1520/STP44393S

ISBN-EB: 978-0-8031-5966-2

ISBN-13: 978-0-8031-6120-7

The Irradiation and Examination of a Plutonium-Uranium Oxide Fast Reactor Fuel

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