Measuring the Release of Short-lived Fission Gases During Capsule Irradiations

Measuring the Release of Short-lived Fission Gases During Capsule Irradiations PDF

Author: Charles William Townley

Publisher:

Published: 1960

Total Pages: 18

ISBN-13:

DOWNLOAD EBOOK →

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).

Comparison of Predicted and Measured Fission Product Behavior in the Fort St. Vrain HTGR During the First Three Cycles of Operation

Comparison of Predicted and Measured Fission Product Behavior in the Fort St. Vrain HTGR During the First Three Cycles of Operation PDF

Author:

Publisher:

Published: 1985

Total Pages:

ISBN-13:

DOWNLOAD EBOOK →

Fission product release from the reactor core has been predicted by the reference design methods and compared with reactor surveillance measurements and with the results of postirradiation examination (PIE) of spent FSV fuel elements. Overall, the predictive methods have been shown to be conservative: the predicted fission gas release at the end of Cycle 3 is about five times higher than observed. The dominant source of fission gas release is as-manufactured, heavy-metal contamination; in-service failure of the coated fuel particles appears to be negligible which is consistent with the PIE of spent fuel elements removed during the first two refuelings. The predicted releases of fission metals are insignificant compared to the release and subsequent decay of their gaseous precursors which is consistent with plateout probe measurements.

Measurements for the JASPER Program Fission Gas Plenum Experiment

Measurements for the JASPER Program Fission Gas Plenum Experiment PDF

Author:

Publisher:

Published: 1987

Total Pages: 52

ISBN-13:

DOWNLOAD EBOOK →

The Fission Gas Plenum Experiment was conducted at the Oak Ridge National Laboratory Tower Shielding Facility during FY 1987 to: provide data for verification of the assumptions and calculational methods used to determine the neutron leakage from the plenum, and provide an uncertainty evaluation associated with the calculations. The Tower Shielding Reactor source was modified to represent the neutron spectrum leaving a typical liquid-metal-cooled reactor core along its axis. The experimental configurations resulted from the insertion of either a homogeneous or homogeneous-heterogeneous gas plenum combination into the iris of a concrete slab, with the only variable being the thickness of the plenum. Integral neutron fluxes were measured behind each of the configurations at specified locations, and neutron spectra were obtained behind selected mockups. The experimental data are presented in both tabular and graphical form. This experiment is the second in a series of six experiments to be performed as part of a cooperative effort between the United States Department of Energy and the Japan Power Reactor and Nuclear Fuel Development Corporation. The research program is intended to provide support for the development of advanced sodium-cooled reactors.

Lanterna Rally - Theme by Grace Themes