High Performance UO2 Program Quarterly Progress Report No. 9 April-June 1963 (open access)

High Performance UO2 Program Quarterly Progress Report No. 9 April-June 1963

Work performed during the quarter is summarized by: direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
Date: July 15, 1963
Creator: Weidenbaum, B.
System: The UNT Digital Library
Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1964 (open access)

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1964

A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Project fuel fins irradiated to 1860, 3000, and 5300 MWD/T have been successfully sampled in the Radioactive Materials Laboratory. The samples have been dissolved and aliquots delivered to Chemistry for Mass Spectrometry and burnup determination. The first Stanford Pool Irradiation indicated that there was some inconsistency in the thermal flux and the near thermal epithermal flux. The experiment was repeated, increasing the number of foil wheel positions from two to three. The data from the second measurement are being reduced. The EPITHERMOS code modification has been completed. Comparisons between the results computed by the code and experimental data show much improved agreement. The metallographic photomicrographs of a polished half-pellet from rod F, irradiated to 5000 MWD/T, show structure very similar to that shown by the pellet from rod S, irradiated to 1860 MWD/T.
Date: July 15, 1964
Creator: Robkin, M. A.
System: The UNT Digital Library
Residual and Fission Gas Release from Uranium Dioxide (open access)

Residual and Fission Gas Release from Uranium Dioxide

Abstract: Residual and fission gas release from UO2 were studied in the laboratory and in in-reactor experiments. Arc-fused powder and sintered pellets were used to determine the rate of evolution and types of residual gases as a function of temperature. Fission gas release was related to the average UO2 temperature and fission gas release calculations were made using the latest thermal conductivity values, isotopic half lives, and branching ratios available in the literature. The results obtained were compared with those available in the literature, and a satisfactory agreement was found among the groups of comparable data.
Date: July 15, 1963
Creator: Spalaris, C. N. & Megerth, F. H.
System: The UNT Digital Library
Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1963 (open access)

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1963

A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 831 MWD/T during the quarter which brings the total to 3165 MWD/T. Applying the same scale factor between logged exposure and Ce-Cs analysis of the first fuel sample gives a corrected exposure of 3774 MWD/T.
Date: July 15, 1963
Creator: Robkin, M. A.
System: The UNT Digital Library
Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fifth Quarterly Progress Report, April 1-June 30, 1963 (open access)

Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fifth Quarterly Progress Report, April 1-June 30, 1963

Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The development of pulsed neutron source techniques for large power reactors has led to a new theoretical model recently developed by E. Garelis and J.L. Russell, Jr. The theory is presently based on a bare, one-group model with m-delayed precursors and takes all spatial modes into account. Results indicate, however, that the application of this model is much broader. Experiments were designed and carried out to both verify this new theory and to demonstrate the performance of the experimental hardware in a large power reactor.
Date: July 15, 1963
Creator: Garelis, Edward & Meyer, P.
System: The UNT Digital Library
Hydraulic Instability In a Natural Circulation Loop With Wet Steam Generation at 1000 PSIA (open access)

Hydraulic Instability In a Natural Circulation Loop With Wet Steam Generation at 1000 PSIA

Experimental test loops have been used to study the problem of hydraulic stability. The oscillatory behavior of a single-phase and two-phase natural circulation loop has been examined at atmospheric pressures and oscillating modes of operation were studied in terms of heat input.
Date: July 15, 1959
Creator: Levy, S. & Beckjord, E. S.
System: The UNT Digital Library
Post-Irradiation Examination of Cored, Edge Loaded, Thoria-Urania Nuclear Fuel (open access)

Post-Irradiation Examination of Cored, Edge Loaded, Thoria-Urania Nuclear Fuel

Three edge loaded thoria-urania nuclear fuel samples were assembled into a capsule, irradiated and examined. This irradiation was the first of a series to develop thoria-urania fuel for high heat flux, specific power and burn-up operation in a sodium graphite reactor.
Date: July 15, 1959
Creator: Slosek, T. J.
System: The UNT Digital Library
Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962 (open access)

Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962

The Program fuel element has continued under irradiation in the Vallecitos Boiling Water Reactor, thermal energy group transfer cross sections for UO2 have been computed, and data have been reduced from the resonance wire activations performed last quarter. Future plans are included.
Date: July 15, 1962
Creator: Carver, J. G.; Morgan, W. R. & Robkin, M. A.
System: The UNT Digital Library