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Fission Gas Behaviour in Water Reactor Fuels
Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Measuring the Release of Short-lived Fission Gases During Capsule Irradiations
A technique is described for the determination of the release of short- lived fission gases during capsule fuel irradiations. Sweep helium passes over the fuel specimen and carries fission gases to a delay trap located close to the capsule. Short-lived fission gases decay in the trap and deposit long-lived daughters which are assayed by radiochemical methods after trap removal. In two demonstrations of the technique the radiochemical analyses have provided information on the rate of release of 1.7-sec Xe/sup 141/, 16-sec Xe/sup 140/, 3.9 min Xe/sup 137/, and 3.2-min Kr/sup 89/. The technique should find considerable application in the irradiation evaluation of fuel materials when it is necessary to determine the contribution shont-lived fission gases make to the coolant-contamination problem. (auth).
