Calculation of Fission-Product Gas Pressures in Operating UO2Fuel Elements

Author:

Notley M. J. F.1

Affiliation:

1. Atomic Energy of Canada Limited, Chalk River, Ontario

Publisher

Informa UK Limited

Subject

General Engineering

Reference18 articles.

1. J. BELLE, “UO2: Properties and Nuclear Applications,” p. 518, Atomic Energy Commission (1961).

2. Fission-Gas Release During Fissioning in UO2

3. M. J. F. NOTLEY, A. S. BAIN, and J. A. L. ROBERTSON, “The Longitudinal and Diametral Expansions of UO2Fuel Elements,” CRNL report AECL-2143, Atomic Energy of Canada, Limited (1964).

4. A. S. BAIN, “Cracking and Bulk Movements in Irradiated Uranium Dioxide Fuel Elements,” CRNL report AECL-1827, Atomic Energy of Canada, Limited (1963).

5. A. M. ROSS and R. L. STOUTE, “Heat Transfer Coefficient between U02and Zircaloy-2,” CRNL report AECL-1552, Atomic Energy of Canada, Limited (1962).

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1. Nuclear Fuel Elements;Physics and Technology of Nuclear Materials;1985

2. Prospects for fission gas extraction from in-reactor UO2 nuclear fuel elements;Nuclear Engineering and Design;1982-08

3. ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel Elements;Nuclear Technology;1979-08

4. Quality Control Techniques for Pyrocarbon;Nuclear Technology;1977-09

5. Mechanisms of swelling and gas release in uranium dioxide;Journal of Nuclear Materials;1971-01

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