Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: July 1 - September 30, 1963 (open access)

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: July 1 - September 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. Quarterly progress: The densitometry procedure (for measurement of alpha autoradiographs of fuel pellets) has been modified to eliminate the need for a second emulsion. The existence of a problem of latent image fading and non-reciprocity of the high-resolution emulsion has been recognized. A tentative procedure has been worked out to correct these emulsion difficulties. the number of polished pellets has been increased to thirteen. The number of hot spots per pellet has not changed appreciably. The largest spot seen is irregular with an estimated volume equivalent to that of a sphere of 35 mil diameter with a PuO2 concentration in the neighborhood of 60%. The VBWR irradiation run now under way is not scheduled to end until October. To the end of the last run the cumulative exposure reached 3703 MWD/T, as logged by VBWR operating personnel. Applying the same scale factor between logged exposure and Ce-Cs analysis of the first fuel sample gives a corrected exposure of 4416 MWD/T. Further debugging of EPITHERMOS, the epithermal extension of …
Date: October 15, 1963
Creator: Robkin, M. A.
System: The UNT Digital Library
Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Sixth Quarterly Progress Report, July 1-September 30, 1963 (open access)

Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Sixth Quarterly Progress Report, July 1-September 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: October 15, 1963
Creator: Garelis, Edward & Meyer, P.
System: The UNT Digital Library
Environmental Testing of a B4C-Ni Prototype Control Rod (open access)

Environmental Testing of a B4C-Ni Prototype Control Rod

Summary: A prototype control rod containing absorber plates made from an electro- deposited dispersion of boron carbide in nickel was tested in the VBWR. It was exposed to the reactor environment of 545 degree F boiling water and thermal neutron fluxes (perturbed) which ranged from 0.6 to 1.1 x 10/sup 13/ nv for 2236 hours over a period of six months. The maximum B/sup 10/ burnup achieved during the test period was 1.8 percent. After irradiation, the rod was examined. The results of the examination are summarized below: (1) The B/sub 4/C-- Ni plate assembly did not undergo significant dimensional changes during irradiation. (2) Numerous blisters developed on both the outer and inner surfaces of three of the four plates. Blistering was more severe on the outer surface than on the inner, and was most severe in a large region located in the lower half of plate 4. Metallographic examination revealed that the blisters were located only in the 2- mil protective nickel overlay covering the B/sub 4/C-- Ni dispersion. It was concluded that they formed from the buildup of gas pressure at the Ni: Ni-- B/sub 4/C interfaces, rather than from corrosion attack. Helium from the B/sup 10/(n alpha …
Date: October 15, 1963
Creator: Megerth, F. H. & Zimmerman, D. L.
System: The UNT Digital Library
Collected Methods for Analysis of Sodium Metal (open access)

Collected Methods for Analysis of Sodium Metal

Methods for analyzing chemical impurities in sodium metal samples are presented. Chemical analysis was used to determine the following impurities: Calcium, Carbon, Chromium, Iron, Lithium, Nickel, Oxygen, Potassium, and Zirconium. Spectrographic analysis was used to determine many other impurities. Sodium samples obtained from experimental apparatus operated as part of the work being conducted for Atomics International were analyzed by these methods.
Date: October 15, 1959
Creator: Perrine, H. E.
System: The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No. 10 July-September 1963 (open access)

High Performance UO2 Program Quarterly Progress Report No. 10 July-September 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: October 15, 1963
Creator: Weidenbaum, B.
System: The UNT Digital Library
Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Program Summary and Sixth Quarterly Report, July 1 - September 30, 1962 (open access)

Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Program Summary and Sixth Quarterly Report, July 1 - September 30, 1962

The work described in this report represents progress toward an agreement signed by the United States and the European Atomic Energy Community which provides a basis for cooperation in programs for the advancement of peaceful applications of atomic energy.
Date: October 15, 1962
Creator: Carver, J. G.; Lagache, M. P. & Morgan, W. R.
System: The UNT Digital Library