Monthly bibliography of government documents published by Texas state entities and submitted to the depository program, listed by agency.

Newsletter of the Texas Industrial Commission discussing activities of the Commission as well as other news, events, and announcements related to industrial development in the state.

Magazine discussing natural resources, parks, hunting and fishing, and other information related to the outdoors in Texas.

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

Proceedings of the 1974 Community Conferences held January 25- February 28 in 16 communities in Texas, including the review of their vocational education activities and profits from the findings of study groups for their community.

Neutron total and elastic and inelastic scattering cross sections of /sup 92/Mo, /sup 96/Mo, /sup 98/Mo and /sup 100/Mo were measured. Neutron total cross sections were determined at intervals of less than or equal to 10 keV from 1.6 to 5.5 MeV with resolutions of approximately 10 keV. Neutron elastic and inelastic scattering cross sections were measured from 1.8 to 4.0 MeV at intervals of 0.2 MeV. Neutron groups corresponding to the excitation of forty states were identified. The experimental results were examined in the context of optical- and statistical-nuclear models. It was concluded that the real part of the optical potential includes a term proportional to ((N - Z)/A) and suggested that the imaginary part is shell dependent with decreasing magnitude as N = 50 is approached. Comparison of measured and calculated inelastic neutron excitation cross sections suggested a number of J/sup ..pi../ assignments extending previous knowledge. The experimental and calculational results were used, together with previously reported values, to generate an evaluated neutron total and scattering cross section file in the ENDF format extending over the energy range 0.1 to 8.0 MeV.

A simple program is explained for those who are just beginning to work with computers in general and the MCS-8 Microcomputer in particular. The text is a guide to understanding some of the processes which occur when a program is written into random access memory (RAM) with the Octal Debug technique (ODT). 3 figures. (RWR)

A description of the Marysville site is given. The drilling program, an environmental analysis, and a survey of geophysical surveys are described. A preliminary survey is presented of the area using aerial thermal infrared imaging techniques. (MOW)

Tantalum alloys containing 27 at percent Hf were vacuum carburized at 1900/sup 0/K in flowing methane. The rate of carbon absorption, for methane pressure between 13 and 133 Pa, was determined from the rate of carbide formation. The rates determined by this technique were similar to those observed for the absorption of carbon in pure Ta. In a preliminary test of the cluster carburizing concept, a solutionized and quenched sample was simultaneously aged hardened and carburized at 1273/sup 0/K for one hour. A hardened zone, 20 ..mu..m deep, formed adjacent to the surface. The zone had a hardness of 800 KHN compared with 500 KHN for the age hardened and 300 for the solutionized alloy. These results can be applied to predicting suitable cluster carburizing conditions.

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This report describe the recent agreement and several recent proposals on the treatment of gold.

This report outlines the Supreme Court case of Furman v. Georgia and the statues that were enacted in response to the case.

This report is a collection of published works concerning marijuana and marijuana-based products.

This report is on federal estate and gift taxes, including a general background on such taxes, legislative history, explanations of major provisions of current law, and major issues and proposals for change as related to federal estate and gift tax law.

Engineering scale experiments were performed to determine the fractional airborne release of strontium during a fire involving a contaminated, flammable solvent. Earlier laboratory scale experiments using radioactive materials indicated that this release would be one percent or less. Twenty-five grams of strontium as strontium nitrate was added to 150 liters of 30% normal tributyl phosphate in a kerosine diluent, which was then burned in the ARHCO 224-T Fire Test Facility. Temperatures of 1000/sup 0/C were recorded during the fire, the maximum scale of the instruments. There were 2 successful fires lasting 70 and 51 minutes, both burning to the point of self-extinguishment. 0.2% of the strontium was released in both burns. The bulk of the released strontium measured was collected in bubbler samplers installed upstream of the sprayed chamber air washer, indicating that the water sprayed in this chamber scavenged the strontium from the air stream.

The FFTF LMFBR is intended to have a near zero release of radioactive gases during normal reactor operation with 1% failed fuel. This report presents calculations which provide an approximation of these cover gas leakages. Data from ongoing static and dynamic seal leak tests at AI are utilized. Leakage through both elastomeric and metallic seals in all sub-assemblies and penetrations comprising the reactor cover gas containment during reactor operation system are included.

This specification establishes the requirements and procedures (using epoxy adhesive) for the installation and removal of the dynamic inflatable test seal for the Fast Flux Test Facility (FFTF), In-Vessel Handling Machine (IVHM) Reactor Refueling Plug (RRP).

Data tabulated for chemical composition of geothermal waters are presented for four areas of interest in Nevada: Beowawe steam well and Beowawe Hot Spring, Buffalo Valley Hot Springs, Kyle Hot Springs, and Leach Hot Springs. Material recommendations were prepared for the Nevada geothermal well. A detailed field corrosion test program planned for the Nevada test well is included. A progress report is presented for a laboratory research program on velocity effects in corrosion. (MHR)

Preliminary analysis of the proposed superheater duplex tube (2-1/4Cr-1Mo) has been performed for the steady state condition. All locations evaluated were found to satisfy the criteria set forth in Code Case 1331-8 Section 4.3 and 5.2b.

Sodium fire protection by space isolation with nitrogen flooding was evaluated by performing a large-scale sodium fire test within a mockup of an FFTF secondary sodium system pipeway. The full scale (3350 ft/sup 3/) mockup was initially filled with air and its leak tightness set to correspond to that expected in an actual FFTF pipeway. The basis for specifying the rate of nitrogen flood gas is discussed ad the experimental verification provided. Nitrogen flooding was activated 15 minutes after the spill of 770 lb of 1100/sup 0/F sodium into a 32 ft/sup 2/ steel pan. The nitrogen flow was controlled manually at a constant rate of 60 ft/sup 3//min (STP) until the pool temperature had decreased to 370/sup 0/F. After cooldown, 87% of the spilled sodium remained in the unreacted form, demonstrating that sodium fires can be effectively controlled by the method of space isolation with nitrogen flooding.

As part of the overall study of the consequences of a hypothetical failure to scram following loss of pumping power, design requirements and preliminary concepts evaluation of an ex-vessel core catcher (EVCC) were performed. EVCC is the term applied to a class of devices whose primary objective is to provide a stable subcritical and coolable configuration within containment following a postulated accident in which it is assumed that core debris has penetrated the Reactor Vessel and Guard Vessel. Under these assumed conditions a set of functional requirements were developed for an EVCC and several concepts were evaluated. The studies were specifically directed toward the FFTF design considering the restraints imposed by the physical design and construction of the FFTF plant.

In this analysis the structural integrity of the double tubesheet connector for the LMFBR demonstration plant steam generator is investigated for design and steady state conditions. Although the evaporator and superheater are to be interchangeable, only the steam outlet end of the evaporator is investigated. This was selected because the mean temperature differences between the tubesheets, tubes and connector are largest here at steady state, thus yielding the highest thermal loads. Combined with the thermal loads are superheater pressures in order to also use the highest mechanical loads. Although this is a conservative approach for the evaporator, the superheater must be analyzed separately at a later date in order to assure interchangeability. Evaluation of the results is based upon ASME Code Case 1331-8.

An analytical computer comparison was made of the compression characteristics of proposed wire-wrap bundles. The study included analysis of 7- and 37-rod straight-start bundles (base configuration), and softened 37-rod configurations. The softened configurations analyzed were: straight-start with distributed wireless fuel rods, and the staggered wire-wrap start angles of 0/sup 0/-30/sup 0/-60/sup 0/ and 0/sup 0/-45/sup 0/-90/sup 0/. The compression of the bundle simulates the bundle-to-channel interference at end-of-life conditions at which high differential swelling between the channel and bundle has been predicted. The computer results do not include the so-called dispersion effects. The effects of other variables such as pitch length, creep, axial variations in swelling, and degree of swelling were not studied. These analytic studies give an indication of trends only. No credence should be given to specific quantitative load or deflection results quoted in this report.

This is a preliminry thermal/hydraulic report reflecting work under Subtask 6.2 of Ref. 1.1. This report is an extension of the previous thermal/hydraulic design report. Parts of this report have been transmitted to GE. The detailed design basis, listed by source, is given. Additional details are discussed.