This document summarizes the requested study of theoretical factors influencing the expected conversion ratio of the fringe enrichment portion of an E-N loading. Exact calculation of the quantity is very complicated and will not be attempted here; however, it is possible, with simple geometric approximations, to derive relative conversion ratios. This present report summarizes the results of a study incorporating actual operating data from the present poisoned top and unpoisoned bottom fringe loadings at H Reactor. There is calculated decrease in buckled-zone (E-metal blanket) conversion ratio of 13% in the E-N loading as compared to normal fringe loadings; this loss is due to the effective reduction in pile size due to the presence of the blanket of BOLL material in the outermost lattice unit and the accompanying increase in enrichment demands. On a full pile basis, this loss represents about 5%. However, on the assumption that an atom of tritium is equivalent in value to an atom of plutonium, the BOLL material in the outermost layer augments over-all pile conversion by about 4% in the green reactor, and probably more in the ripe reactor in addition to compensating the 5% loss in the E-metal blanket. An Appendix is included as …

The purpose of this test is to obtain data concerning the reactivity effect of horizontal control rods in the E-N loading at H Reactor. The accurate calibration of the control rods will then provide more accurate measurement of the other reactivity variables associated with the E-N loading.

This report provides the experimental results of uranium chemical machining tests.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: The effect of the appointment of a purchasing agent for a county over 73,000 population as to (a) The continued necessity of having the County Judge approve purchases (b) Purchases by the sheriff of food and medicine for county prisoners, (c) Purchases of food, clothing and supplies by the County Welfare authorities.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a hospital district, authorized by Section 8 or Article IX of the Texas Constitution, and Article 4494q-3 of Vernon's Civil Statutes, has the authority to tax property for the operation and maintenance of hospital facilities therein.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Constitutionality of House Bill 438, prohibiting trading stamps and similar devices.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the Legislature may retire outstanding bonds issued by Texas Southern University, and related questions.

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The intent of the production test that occasioned this study was to determine if overfeeding of a coagulant having little or no sulfur present as a main constituent or impurity and consequent lower levels of parent material -- P{sup 31} and S{sup 32} -- in process water would result in lower levels of radionuclides in reactor effluent water -- e.g., P{sup 32} that constitute a potential limitation to reactor operations. Aluminum nitrate nonahydrate -- Al(NO{sub 3}){sub 3}. 9H{sub 2}O was the reagent chosen. Inasmuch as substitution of ANN for alum represented a change in the coagulant added to process water, provision was made to monitor fuel cladding and process tube corrosion rates. This report documents the corrosion data obtained during the test period. The radiological effects of this test have been separately reported.

The 12 batches were individually dissolved in Redox dissolvers. U and Pu were separated from the test solutions and purified for isotopic analyses. Results are tabulated; Am-241, Cm-242, and Np concentrations are also reported.

A product specification will impose operating problems for the HAPO reactors and the separation facilities. A preliminary analysis of several methods of operating have been considered using a linear program analysis. This document considers some of the implications. A linear programmed study of HAPO reactors was made in which six percent Pu was maximized under several reactor plans.

A method of reducing gas leakage and rear fate maintenance is to fix the rear gunbarrel and process tube to the shield and eliminate the need for a rear expansion bellows. This arrangement is being considered as part of the C-reactor conversion to self-supported fuel element program. The fixed rear gunbarrel will require that all hydraulic load and thermal expansion elongation of the tube be taken through the front bellows. In the event that tubes freeze in their channels, forces due to thermal expansion and hydraulic pressure will be transmitted to the rear shield if the tube and rear gunbarrel are fixed to the shield. Calculated maximum forces which can be transmitted to the shield are given in this report. The probability and amount of restraint which can occur in the tube are discussed. Finally, methods of insuring that the restraint does not cause excessive forces on the rear shield are discussed.

Accumulation of data on rear face piping strain, piping vibration, water pressures; and water temperatures at KE Reactor was recently completed. A preliminary review of this data indicates that much of the pressure and temperature data could be significant to the study regarding the capability of the K Reactor rear face piping to accommodate the proposed increased water flow. In view of this, a copy of the pressure-temperature data is attached. The purpose of the test was two-fold: (1) to establish mechanical and hydraulic conditions in the rear face piping accompanying operation at current flows and maximum bulk outlet temperatures; (2) to use this information to assess the feasibility of continued operation at these conditions. A preliminary review of the data brings forth the following observations: (1) a downcomer flow transition begins to occur at about the 85 C bulk outlet temperature; (2) the current flow conditions at the top of the downcomer appear to be slightly different from the original design concept; (3) the pressure recorded on the near side of the downcomer just above the orifice (P-10) appears doubtful, and instrumentation will be checked; (4) flow characteristics of the multiple parallel orifices in a single channel does not …

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As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechanical properties, and corrosion behavior in NaK, sodium, and water of niobium--uranium binary alloys containing up to 60 wt.% uranium were investigated. Alloys were cast by a skull melting and consumable and nonconsumable arc-melting methods. Fabrication difficulties with alloys containing greater than 25 wt.% uranium were related to coring-type microsegregation during casting. Tensile tests indicated 0.2% offset yield strengths of 16,880, 22,370 and 28,600 psi for niobium2000 deg F. Additional tensile data were obtained for alloys from 1600 to 2400 deg F. Stresses to produce minimum creep rates of 0.001, 0.01, and 0.1%/hr at 1600, 1800, and 2000 deg F were also determined. Both tensile and creep strengths were found to be sensitive to oxygen content. All alloys appeared compatible with NaK at 1600 deg F and with sodium at 1500 deg F. In 600 deg F water, most of the alloys tested exhibited negligible weight changes after 336 days' exposure. Weight changes were greater after 140 days' exposure to 680 deg F water, but corrosion rates were considered satisfactory for a clad fuel. The thermal and electrical conductivities of niobium are lowered by the addition of uranium, …

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

Two new explosives are under development at Lawrence Radiation Laboratory (LRL) which show considerable promise as replacements for PBX 9404 (and also PBX 9010). Three primary considerations have guided us in the development of these explosives. Compared to PBX 9404 we have sought a significant decrease it sensitivity, a substantial gain in mechanical properties and as little loss in energy and detonation velocity as possible. While testing is not complete on these materials and probably won`t be for quite some time sufficient information is available to warrant a complete status report at this time. An index of the topics covered herein is: Formulations and Raw Materials; Molding Powder; Explosive Performance; Sensitivity; Thermal Stability; Compatibility; Mechanical Properties; Machinability; Pressability; and Comparison of the Two Materials.

An easy experiment for undergraduate students to measure the mass and diameter of a copper atom can be performed with inexpensive apparatus normally available any college physics laboratory. By measuring the density and by copperplating, one can obtain results which are accurate to better than 5%.

Abstract: The removal of both SM-1 Core I high burnup elements from the SM-1 Core II and the insertion of two SM-1 Core I spare elements i their places are discussed. Nuclear and thermal characteristics of Core II with the change are presented and conclusion related to the change in hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself leads to a more conservative estimate of core safety. There is no conceivable reason why this perturbation may not be safely made in the SM-1 Core II.

A program translates an algebraic language like Algol into the machine language of an electronic computer must perform the following functions.

The IBM-70% code GHT has been programmed for the 7090computer, to be run under control of the IBM-7090 FORTAN Monitor System. By eliminating the use of tapes for intermediate number storage, it has been possible to reduce computing time by a factor of 26 over the 704. A minimum of three tapes are required; one for input, one for output, and the System tape. One scratch tape is required for transient problems, and one punch tape is required if the steady-state temperature distribution is to be punched on cards.