A criticality excursion occurred at the Oak Ridge Critical Experiments Laboratory on November l0, l961 as enriched uranium metal, neutron reflected and moderated by hydrogen, was being assembled. It is estimated that the energy yield was between 10/sup 15/ and 10/sup 16/ fissions. There was no personnel exposure or property damage. Fission product contamination, both airborne and contained in the metal, decayed sufficiently overnight to allow unhindered continuation of the experiment. The excursion was caused by a too rapid approach of the two sections of uranium constituting the experiment. (auth)

About 298,000 OIIIN aluminum components were received from Harvey for evaluation after major steps were take in the vendor`s plant to upgrade product quality. This material met HAPO specifications and was comparable to Alcoa control components. Finished fuel elements (non-bumper and bumper) canned in the test and control components are tabulated by uranium core type and canning month. Non-destructive and destructive test data did not show any differences in clad fuel elements attributable to component quality. Irradiation status of non-bumper and bumper fuel elements clad in Harvey improved components as of Dec. 31, 1962, is tabulated, as is a summary of ruptures. It was recommended that Harvey Aluminum Co. be allowed to bit competitively on all future Al component orders except for the KVN and KVE component models.

The purpose of this report is to recommend variable goal plans for natural and enriched bumper fuel elements, specifically for 0-III-NB and 0-III-EB materials, to be irradiated at the B, D, DR, and F Reactors. The average goal exposure for all bumper fuel elements at D Reactor was specified to be 900 MWD/T, with provisions being made for revision by normal procedures. Exposures for enriched bumper material at the B, M. and F Reactors were not specified in the PITA supplement authorizing charging of this material.

It is the objective of this production test to authorize the use of PT IP-216-A (Quality Certification) fuel columns and supplementary numbered columns are required for obtaining routine axial flux measurements suitable for metal performance analysis.

This report provides an addendum to the February 1963 production studies and details Neptunium 237 production yields.

This report details progress in an intensive investigation which was launched to determine the basic mechanisms leading to gross loss of UO{sub 2} fuel upon thermal cycling of UO{sub 2}-W cermets and to suggest means of overcoming this serious operational problem. (This problem was recently uncovered at both Lewis Research Center and at Hanford). More than 40 separate experiments were conducted in four high temperature furnaces, at temperatures to 2600 C, pressures from 10{sup {minus}5} mm vacuum to 1000 psi, atmospheres including wet, pure and tank H{sub 2}-Ar mixtures, N{sub 2}, and He, and cycle periods from 30 seconds to 15 hours. Specimens examined included two types of NASA-fabricated plates, three types of Hanford high energy impacted discs, and several other materials used for single experiment evaluation.

None

This document reflects our comments on the drawings and design information that we have received. It is therefore contingent upon the drawings and specifications which we have not as yet received from Vitro Engineering Company.

The principal objective of the work being reported was to irradiate a variety of borides in order to assess the relationship of crystal structure to helium retention and structural changes. A secondary objective was to compare the irradiation behavior of powders and dense solids. Another objective was to compare the behavior of borides with similar crystal structures but having metal atoms with vastly different absorption cross-sections, for example, zirconium and hafnium diborides.

A plugging meter designed for the Hallam Nuclear Power Facility was tested. Plugging performance was satisfactory and excellent reprcducibility was achieved. Although the time limitations precluded complete testing of the automatic control equipment, the tests performed gave satisfactory indication of correct performance. (auth)

The filtration and pressure drop-flow rate characteristics of MC 1478 filter paper was determined over wide ranges in pressure 1/20 to 1/5 atm.) ard temperature (--40, 0, and 70 deg F). The retention of SiO/sub 2/ spherical particles by the filter paper at a flow rate of 5000 ft/min at 1/20 atm. pressure and 70 deg F was found to be essentially 100%. The retention (generally 30 to 75%) for aluminum oxide particles (about 40 A) and pressure drop were determined over wide ranges in pressure, temperature, and flow rate, The application of kinetic theory to small particle diffusion in a gas is discussed. The theory of diffusion of particles from a streaming gas to the tube wall was evolved and applied to the estimation of particle size. (C.J.G.)