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FINAL STATUS OF GENERAL ENGINEERING LABORATORY AIR FLOW AND DUST TEST PROGRAM. PART I. PART II

Description: A full scale 15 deg sector of the P122 reactor configuration was constructed. The model was complete with respect to all internal cooling air passages, and reflectors, thermal shielding, and island reflector. The contract was terminated before any test data could be obtained. Investigation of the effect of atmospheric dust on performance of reactor systems using wire screen matrix fuel elements is reported. The interim conclusion is that dust would not limit aircraft performance or life. Work proposed but not completed is outlined. Appendices contain previously unpublished reports. (auth)
Date: May 25, 1961
Creator: Venneman, W.F.; Lawrence, R.L. & Ryan, P.T.
Partner: UNT Libraries Government Documents Department

FLOOD SAFETY OF THE MIXED SPECTRUM SUPERHEATER

Description: Calculations are presented which show that the reactivity effect of flooding and unflooding the fast superheating section of the Mixed Spectrum Superheater can be made small by the addition of epithermal poisons to the superheater. The reactivity effects of flooding superheater sections ranging in size from 1.25 to 3.5 ft cubes and containing U/sup 23/5/sup >/oxide or Pu/sup 239/ oxide fuel and various amounts o f the epithermal poison europium were calculated. Reactivity changes during several postulated flooding processes are given. Methods for deterthination of fissile and fertile material and poison cross sections in the resonance- region are discussed. (auth)
Date: May 25, 1961
Creator: Reynolds, A.B.
Partner: UNT Libraries Government Documents Department

A Model for Fission-Gas Release From Porous Fuels in Low-Permeability Containers

Description: A simple mathematical model was developed to describe the steady-state release rate of gaseous fission products from porous ceramic fuels in low- permeability containers. The resulting equations are used to analyze experimental release rate results obtained from a UC/sub 2/-fueled graphite fuel body enclosed in a low-permeability impregnated graphite container. The relative release rates of the fission-product species Kr/sup 85m/, Kr/sup 88/, and Xe/sup 133/ were predicted with reasonable success. Absolute-rate predictions were not possible due to lack of information on true permeability and porosity profiles in the graphite container. (auth)
Date: August 25, 1961
Creator: Prados, John W.
Partner: UNT Libraries Government Documents Department

Radiation Levels in the Vicinity of the Purification Demineralizers. Core 1, Seed 2. Test Evaluation T-641306

Description: Measurements were made to determine the extent of activity build-up inside the 1 AC and 1 BD punification demineralizer concrete enclosures. Radiation levels were obtained at 6-in. intervals from 6 to 17.5 ft below the top of the concrete shield on the 1 AC demineralizer and from 0.5 tc 24.5 ft on the 1 BD dendneralizer by lowering the probe through the 3-in. pipe on top of the concrete enclosure. The results indicated that the long-lived activity in the purification demineralizers had decreased considerably, since the previous test, with the addition of new resin. (M.C.G.)
Date: May 25, 1961
Partner: UNT Libraries Government Documents Department

SUMMARY NUCLEAR CALCULATIONS FOR THE SM-2 CORE 1

Description: The results of a limited analysis of the extended SM-2 critical experiments are given. A review of the analytical models is presented to ascertain the accuracy of the reactivity calculations for the reference SMi-2 Core I. A new reference B-l0 loading was derived based on analysis and experimental measurements. Calculations of power distributions and burnup behavior of the reference core are presented and comparisons to available measured data made. (auth)
Date: September 25, 1961
Creator: Fried, B.E.; Beam, R.H. & Bobe, P.E.
Partner: UNT Libraries Government Documents Department