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Activities in a program to determine the effects of neutron irradiation on A-302B steel are reported. Plans are discussed concerning performance tests on tensile, notched tensile, tube, and Charpy specimens. An irradiation capsule design was finalized. A theoretical analysis of the critical conditions arising in a tube subjected to both internal pressure and axial load is included. (J.R.D.)

Data are given on the radioactive nuclides present in waste disposal effluents during Nov. 1961. The concentrations of all activities was well within established limits for discharge to the environment. (C.H.)

A survey of the pertinent literature was made to ascertain the status of data on U/sup 233/ fission-product yields. The various experimental determinations were evaluated, and the most recent mass-spectrometric results were used as a basis for deriving a set of preferred yields. These yields were compared with values reported in two other recent compilations, and for yields >1%, the three setrs agreed with each other to an average precision of <5%. It was concluded that recent measurements have somewhar improved the reliability of U/sup 233/ fission yield data, but some recommendations for additional experimental work were made (auth)

Equations were derived by strain-energy methods for analyzing the stress and deflection in the boiler fuel element boxes used in the Pathfinder nuclear reactor. These boxes are of two types, both constructed of Zircaloy lI. One box is approximately 5 in. sq. The second is approximately 10 1/2 in. sq divided internally into four compartments (5 in. sq) by a cruciform control-rod guide structure. Stress and deflection in the box walls are caused by pressure differences across the walls. The equations were verified by testing an aluminum model of the single-element box and a Plexiglas model of the four-element box. There was less than 10% difference between theoretical and measured values for the maximum stress and deflection, and therefore, use of the equations for designing the Pathfinder fuel element boxes is justified. (auth)

The mathematical formulation of the subcritical reactor with extraneous sources is presented in detail. The solutions are presented for a two-group approximation including epithermal fission and the relationship to the usual critical reactor problem is discussed. Application of the equations to an arbitrarily complicated geometry is outlined, and an IBM-7090 program for the solution in a bare cylindrical reactor is described. (auth)

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)

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The following report is part of a series of quarterly reports discussing investigations on the development of zirconium-base alloys having corrosion resistance and strength superior to Zircaloy-2 and/or development of materials of equivalent corrosion resistance by exhibiting enhanced strength. This report covers the period between May 29 and June 18 of 1958, made by the United States and the European Atomic Energy Community (EURATOM).

The discussion and summary report presented here illustrate the type of information that is currently in data processing machine language and available to those who require it. During the progress meetings at which these reports were discussed, several persons indicated a desire to have a documented explanation of the report and a personal copy to scan. This is the answer to these requests. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest.

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The discussion and summary report presented here illustrate the type of information that is currently in data processing machine language and available to those who require it. During the progress meetings at which these reports were discussed, several persons indicated a desire to have a documented explanation of the report and a personal copy to scan. This is the answer to these requests. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest.

The objectives of this Process Improvement Transition Authorization (PITA) for KE and KW reactors are to authorize a flat 700 C graphite temperature limit in the bulk of the graphite, with a conditional 850 C limit in the 0.130 coring zone only, and in conjunction therewith to provide for routine use of nitrogen instead of carbon dioxide in the reactor atmosphere. These temperatures as quoted apply to filler blocks in the vicinity of normal channels, and are maximum limits.

The interim report included an analysis of those E-N case and blanket loading conversion ratio data which were available at that time, and an extrapolation of those data to expected, optimum, E-N operating conditions. Since issuance of the interim report further tritium yield data have become available from extraction of the tritium from the lithium-aluminum slugs irradiated in the second E-N core loading, and from the large batches of lithium-aluminum slugs irradiated as part of the blanket loading. Since these data complete the planned program of tritium analyses for the E-N demonstration load, it is felt appropriate that they be reported at this time. No further plutonium yield data have been received since issuance of the interim report and for this reason the plutonium conversion ratio is still tentative. It may be different when data from the second core test loading has been received.

The following discussion and attached summary report is sent to you to illustrate the type of information that is currently in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest. The function code numbers relate directly to the definitions of the hours expended for charge-discharge, rupture removal, tube leak repair, tube replacement, and so forth. These definitive classes are taken from the distribution records supplied by the various reactor analysts and summarized by the Reports and Statistics group in the IPD Production Operation.

This discussion and summary report illustrate the type of information that is in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in term of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed with a basic function class, the associated delay total and the number of tubes involved for those functions where a delineation by tube count may be of interest.

This report is a summary of the way information is stored on the maintenance histories of the Hanford Production Reactors. Twenty two different categories are considered as primary reasons for maintenance down times. The data is stored in terms of hours spent on different tasks, and is also grouped by the controlling cause of the outage.

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This discussion and attached summary report illustrate the type of information that was in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the cateogry defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest. The function code numbers relate directly to the definitions of the hours expended for charge-discharge, rupture removal, tube leak repair, tube replacement, and so forth. These definitive classes are taken from the distribution records supplied by the various reactor analysts and summarized by the Reports and Statistics group in the IPD Production Operation.

A series of W-5 Re/W-26 Re thermocouples have been electron beam welded at the Hamilton Standard Division at our request. This technical report is a summary of our evaluation of these joints. These weldments did exhibit incomplete fusion in cap welds and some porosity in undesirable lead junction shapes. In fairness, this was a single attempt to make a difficult joint, and the objective of ungrounded 1/16 OD clad joints was met. As noted by Hamilton, two changes are necessary to improve this joint design: (1) swaging to forming the clad end rather than crimping prior to cap welding. (2) using a fixture with rotary motion on a tilting axis.

Declassified 28 Aug 1973. Various methods of producing and using nuclear power for military land vehicles and other military equipment were investigated and evaluated. A nuclear-powered mobile energy depot (MED) would move with advancing armies and produce vehicle fuels from materials readily available in the field. This would make mechanized units independent of external fuel supplies for extended periods, and permit them to move quickly and easily to areas impossible for units that depend on the customary fuel supply lines. Many possible MED systems were evaluated on the basis of energy sources, fuel manufacturing (by both conventional and chemonuclear processes), fuel storage and transportation, and fuel utilization in both present-day internal-combustion engines and power units of the future (i.e., fuel cells). The applications of more than a dozen MED systems to vehicular propulsion were studied. (auth)

The operation of a Magnatest Type FM-500 Elastomat instrument, the detection and recognition of the resonant frequencies of a sample, the methods and formulas for the calculation of the elastic moduli from the resonant frequencies, and results obtained from testing several different materials and sample shapes are discussed. The accuracy and reproducibility of the sonic modulus method for graphite was found to be very good. The fundamental flexural resonance was reproducible to within 0.2%, with the reproducibility of the high resonances decreasing to about 0.5%. The data are tabulated. (P.C.H.)

Resulte of a laboratory investigation undertaken to adapt the Pu anion exchange process to the direct recovery of the Pu lost to the Task I oxalate filtrate are reported. It was found that the Button Line Task I Filtrate can be recovered by HNO/sub 3/ anion exchange process, thus isolating the Button Line from any solvent extraction process. (J.R.D.)

Research covers the work done on a bench test of an unclad thermionic converter. The objective is to produce an efficient, high-power-density, long- life thermionic power converter using a uranium-zirconium-carbide emitter and a high-temperature nickel collector. (auth)