The uranium-2 wt percent molybdenum alloy was prepared, processed, and age hardened to meet a minimum 930-MPa yield strength (0.2 percent) with a minimum of 10 percent elongation. These mechanical properties were obtained with a carbon level up to 300 ppM in the alloy. The tensile-test ductility is lowered by the humidity of the laboratory atmosphere. (auth)

Studies were performed to determine the comparative effectiveness of solvent and aqueous detergent methods for cleaning various metals. The metals investigated included 304L stainless steel, beryllium, uranium-6.5 wt percent niobium alloy, and unalloyed uranium (/sup 238/U). The studies were initiated in response to governmental regulations restricting the use of some chlorinated solvents. Results showed that aqueous detergent cleaning was more effective than solvents, i.e. trichloroethylene and methyl chloroform, for the removal of light industrial soils. The subsequent adoption of aqueous cleaning at this plant has facilitated waste disposal, which contributed to recorded economic savings. The controlled use of aqueous detergents is environmentally acceptable and has decreased the hazards of fire and toxicity that are generally associated with solvents. 8 tables, 15 figures

Design-basis depressurization accident analyses for the Fort St. Vrain reactor were performed using the FLODIS (Ref. 4) code. The FLODIS code models the active core, side reflector, gas annulus between the core barrel and the PCRV liner, and the PCRV cooling system. Results are presented for the Pelton circulators operating at 10,550, 8800, and 7000 rpm. Maximum temperatures of selected components are plotted as a function of time during the transient. None of the components studied exceeded the temperature at which failure or damage may occur. However, there must be sufficient mixing of the outlet gas in the lower plenum to insure the integrity of the steel liners of the steam generator inlet ducts.

An anti p beam is produced from source protons accelerated in the main ring and focused on a target. The anti p beam is captured and accelerated in the doubler, its bunch structure intact, and a proton beam is accelerated in the main ring. The luminosity resulting from the ensuing anti pp collisions is calculated.

The above specimens were irradiated with 14-MeV neutrons from the LLL Rotating Target Neutron Source. Only the test procedure is described. (MOW)

A review of the study on ship-transportation systems is presented. The objectives and project schedule are given. Summary information on Task I (Energy Utilization Analysis Approach); Task II (Potential Case Studies); and Task III (Martime Market for Bottom-Cycle Applications) are given. (MCW)

Experimental values obtained for x-ray mass attenuation coefficients between the M/sub I/ and M/sub V/ absorption edges of rhenium are presented below. Also presented is a brief discussion of the experimental procedure.

Flooding and mass transfer experiments were performed with a CO/sub 2/-air/water system to examine mass transfer characteristics in Goodloe-packed columns of 6.4 and 15.2-cm ID for removal of radioactive Kr from HTGR off-gas. The flooding experiments verified previous correlations for the packing. The plug flow model was selected for calculation of the overall mass transfer coefficient, K/sub L/a. The correlation for K/sub L/a in terms of the molar liquid flow rate, L', is K/sub L/a = 0.359(L')/sup 0.96/ for 7.5 x 10/sup -3/ less than L ' less than 3.4 x 10/sup -2/ in the 6.4-cm column and K/sub L/a = 0.144(L')/sup 0.96/ for 2.7 x 10/sup -3/ less than L' less than 5.5 x 10/sup -2/ in the 15.2-cm column.

The following are covered: construction status, operation activities, and project cash flow. (MHR)

A round robin chemical analysis of two halthane adhesive polyol cure agents for hydroxyl number, acid number, and water content has been conducted between analytical laboratories at LLL, Pantex, Bendix, and Union Carbide (Y-12). The reported data show sufficient scatter as to recommend that specific test procedures be called out. Different methods were used in the various labs, some with slight modifications, others were entirely different. Also, some ASTM procedures were misapplied and others were incorrectly called out. For these polyether materials, ASTM E-222-73 (acetylation reflux) should be adopted for the hydroxyl number determination. The ASTM 2849-69 method for acid number should be discontinued and the ''Quaker Oats'' procedure be adopted. Water determination by Karl Fischer titration is acceptable with the recommendation that the ''Aquatest II'' instrumentation be called out (used by three of the four lab participants).

A HPGe detector incorporated into a Compton suppression and pair spectrometer yields a continuum suppression factor of over 30. Cryostat housing requirements to obtain such suppression are discussed, sample spectra are presented, and several experiments making use of the HPGe dual system are discussed.

Several new or poorly characterized neutron-rich nuclides were produced and studied at the Brookhaven Medium Energy Intense Neutron facility, MEIN. /sup 190/W decays with T/sub 1/2/ = 30.0 +- 1.5 min, E/sub beta/ = 0.93 +- 0.07 MeV, and ..gamma..'s of 157.6 and 162.1 keV. /sup 196/Os decays with T/sub 1/2/ = 35.0 +- 0.4 min and ..gamma..'s at 126.1, 200.7, 207.0, 257.0, 315.3, 407.6, 522.2, and 628.9 keV. /sup 230/Ra decays with T/sub 1/2/ = 93 +- 2 min to 122 +- 3 sec /sup 230/Ac; ..gamma..-ray energies and intensities are tabulated. A decay scheme is proposed for /sup 190/W, and many of the transitions following the decay of /sup 230/Ac are between known levels in /sup 230/Th.

This study was designed to provide data for dynamic modeling of radioactive pollutants in marine ecosystems adjacent to nuclear power plants. The data are relevant to the dynamics of radionuclide transfer among seawater, suspended particulates, sediments, and biota. Gamma-emitting radionuclides (/sup 54/Mn, /sup 60/Co, /sup 65/Zn, and /sup 137/Cs) were followed in the water and particulates, as well as in oysters introduced into the discharge canal of the boiling water reactor of the Humboldt Bay Power Plant near Eureka, California. The liquid waste was introduced into the canal at irregular intervals and contained radionuclides at extremely low but variable concentrations. Radionuclides were determined in the oysters, water, and particulates after single releases (over about 6 hr) and over a long series of releases (18 months).

Under the Solar Heating and Cooling Demonstration program, solar heated and cooled commercial buildings are to be constructed throughout the nation to show the technical and economic feasibility of solar energy systems and, most importantly, to establish an economically viable solar industry. The questions arise: How many solar energy systems must be installed and where should they be installed to meet these objectives. This report presents an answer to these questions.

As a result of an explosion in the Waste Treatment Facility, 242-Z Building, 200 West Area of the Hanford Reservation on August 30, 1976, the Manager of the Richland Operations Office (RL), Energy Research and Development Administration (ERDA), appointed an ERDA Committee to conduct a formal investigation and to prepare a report on their findings of this occurrence. The Committee was instructed to conduct the investigation in accordance with ERDAMC 0502, insofar as circumstances would permit, to cover and explain technical elements of the casual sequence(s) of the occurrence, and to describe management systems which should have or could have prevented the occurrence. This report is the result of the investigation and presents the conclusions of the review.

An account of irradiation of glass samples in the LPTR reactor is given. Irradiation procedures are described and irradiation exposure times and neutron fluence values are tabulated. (JRD)

Low-resolution field ionization and high-resolution 70-eV electron-impact mass spectra data were obtained for 28 GPC fractions acquired from Bartlett, Kansas, heavy petroleum by members of the Separation and Characterization group at the Bartlesville Energy Research Center. This group was supplied with most-probable empirical formulas deduced from the high resolution electron-impact data. Analysis of the qualitative and quantitative analytical data previously obtained for GPC fractions from a Synthoil sample by high- and low-resolution field-ionization and high-resolution 70-eV electron-impact mass spectrometry is essentially complete. A study of field-ionization sensitivities for saturates and mixtures of saturates and aromatics is in progress. Components required to modify the combined FI/EI ion source to permit operation in the field desorption mode have been ordered.

The work described in this report represents a continuation of the fission cross section ratio measurements in progress at the Lawrence Livermore Laboratory. Preliminary results are provided for the /sup 241/Am//sup 235/U fission cross section ratio from 0.2 to 30 MeV. Upper limits on this ratio are given over broad energy bands from 0.001 to 0.2 MeV. Using the threshold cross section method, the value of 1.616 +- 0.042 is obtained for the cross section ratio in the interval 1.75 to 4.00 MeV.

A megachannel pulse-height analysis system using a PDP-8/E computer and two moving-head disk memories has been developed. The system has a storage capacity of 220 memory locations, is capable of processing 1100 events/s, and provides on-line sorting and disk storage. An X- or Y-pulse-height spectrum in coincidence with one or several arbitrary pulse-height windows can be assembled in core for scope display and spectral analysis within 2 to 20 seconds. Reconstruction of a complete X- or Y-pulse-height spectrum requires about 3 minutes.

Values of the gram-atomic volumes and enthalpies of atomization to the monatomic ideal gas state for liquid elements at their melting points are collected to facilitate predictions of the behavior of mixed systems. Estimated values are given for experimentally undetermined quantities.

A mercury-enhanced silver solid-state bond has produced reliable high strength joints in the bonding of Vascomax-250 (maraging steel). The joints are achieved by applying a uniform bond pressure across the mercury-activated silver-coated bonding surfaces at low temperatures. Mercury assists in making reproducible bonds by being an effective surface conditioner prior to bonding. The fractured surface morphology was analyzed by scanning electron microscopy and energy dispersive x-ray analysis. 14 figures.

It is assumed that objects exist, and the consequences and possible tests of these assumptions are examined. Various experiments on particle interactions are considered. (JFP)

Irradiation experiments were performed with the two beam Nd:YAG glass laser systems, Janus(approximately less than 40 J/100 psec, approximately 0.4 TW), Cyclops (approximately less than 70 J/100 psec, approximately 0.7 TW), and Argus (approximately less than 70 J, 35 psec, approximately 2 TW). Two classes of targets have been used, glass microshells (approximately 40 to 120 ..mu..m diameter x approximately 0.75 ..mu..m wall thickness) filled with an equimolar DT mixture and disks (approximately 160 to 600 ..mu..m diameter x approximately 10 ..mu..m thick) of several compositions. The targets were supported in vacuum (pressure approximately less than 10/sup -5/ Torr) by thin glass stalks. This paper reports results related to the propagation, absorption and scattering of laser light by both spherical and planar targets. The absorption measurements cannot be explained using only inverse Bremsstrahlung. The scattered light and the plasma energy are polarization dependent, which is evidence of resonance absorption. The x-ray spectra are characterized by a thermal and a suprathermal distribution. The ''temperature'' of the hot x-rays is given by theta/sub H/ approximately equals I./sup 3/-./sup 4/ depending on the target material. Evidence is also presented which indicates that the laser radiation pressure is producing density steepening in the region …

Heavy metal sulfides form a substantial part of the scale solids depositing from high-temperature, high-saline geothermal brines. An assessment has been made of the prospects for controlling this deposition by chemical modification of the brine. An outline is given of the types of reactions influencing sulfide precipitation. It is suggested that two factors affecting sulfide solubility and that are amenable to chemical modification of the brine are oxidation state and pH. A partial oxidation process can be used to convert aqueous sulfide species to free sulfur, a process favored by thermodynamics and kinetics. Some oxidizing agents are suggested for this purpose. A discussion is given of the possibilities of precipitating other solid phases after extensive oxidation. It is concluded on the basis of the available data that this possibility exists, but that uncertainties in reaction kinetics, unavailable data, and solution complexity make an exact analysis difficult. The usefulness of a field evaluation of chemical modification processes is indicated. (auth)