Between mid-May and late June 1976, 3409 water and water-transported sediment samples were collected from 1781 locations spread over an approximate 17000-km/sup 2/ area of northwestern Montana. All of the samples were analyzed for total uranium at the LASL, using standardized procedures and rigorous quality controls, the waters by fluorometry and the sediment (and those waters with greater than 10 ppb uranium) by delayed-neutron counting methods. All of the field collection, treatment, and packaging of the samples was performed following strict LASL specifications. The uranium concentrations measured in the waters range from undetectable (less than 0.2) ppb to 173.6 ppb, but average only 0.66 ppb. The low uranium concentrations in the waters of this area are thought to be due primarily to a general lack of readily soluble uranium and dilution with spring runoff. Those locations which did have abnormally high uranium were examined more closely, and follow-up field examinations are recommended in the vicinity of some of these sites. The uranium content of the sediment samples range from 0.5 ppM to 52.2 ppM and average 4.56 ppM. Sample locations with high and/or anomalous uranium values were examined with respect to the local geology, water chemistry, and other relevant factors. …

During August 1976, a total of 876 natural waters and 861 bottom sediments were collected at a nominal density of one location each 23 km/sup 2/ from streams and small lakes throughout the Noatak NTMS quadrangle, the southern two-thirds of the Baird Mountains NTMS quadrangle, and in the southwest corner of the Ambler River NTMS quadrangle. These samples were collected as part of the National Uranium Resource Evaluation program in Alaska being conducted by the Los Alamos Scientific Laboratory (LASL). The field collection and treatment of the samples were performed following strict LASL specifications. Total uranium was measured in the waters by fluorometry and in the sediments by delayed-neutron counting, using stringent quality assurance controls at the LASL. The uranium contents of the waters ranged from below the detection limit of 0.02 parts per billion (ppB) to a high of 8.38 ppB, and the uranium contents of the sediments ranged from a low of 0.3 parts per million (ppM) to a high of 34.0 ppM. In general, the locations of waters containing relatively high uranium contents were found to occur in clusters, and particularly in the headwaters of streams draining the southern slopes of the Baird Mountains. Few sediments contained …

We subjected the Meteorological Data Acquisition (MEDA) remote station hardware to temperature, vibration, and road tests. The MEDA equipment was designed at the Lawrence Livermore Laboratory (LLL) for the Air Resources Laboratory (ARL). ARL supplied all MEDA sensors. The prototype system passed these tests.

QIKMIX is a quick-turnaround computer code developed to compute the radiative Rosseland mean opacity of specified mixtures at specified temperature and density points. The QIKLIB data base, which QIKMIX uses, has been derived from the OPLIB library. For most mixtures, QIKMIX can compute opacities over a temperature range of 50 to 25,000 eV in less than 1 min of CDC 7600 computer time. The purpose of this report is to discuss the QIKLIB data base and the operation of the QIKMIX code.

First results from the SLAC-LBL Mark II magnetic detector at SPEAR are presented. The performance of the detector is discussed and preliminary results are given on inclusive baryon production R/sub p + anti p/, R/sub ..lambda.. + anti ..lambda../, on decay modes of the D mesons and on two-photon production of eta' mesons.

This report recommends developing a statistical model to characterize the three-dimensionall pattern of thermal plumes, It indicates the danger of drawing detailed conclusions on the basis of a small number of observations, and emphasizes the need for proper interpretation of empirical measurements, Two reports, on the discharges (1) from the Dresden Power Station into the Illinois River and (2) from Waukegan Station into-Lake Michigan are analyzed. In conclusion, a plan for interpretation of temperature measurements is recommended.

In a previous report on effects of thermal discharges from power plants into the Great Lakes, we stressed the need for a statistical analysis of the spatial and temporal pattern of the thermal plume. The plume pattern is recognized as stochastic in nature and requires statistical analysis. A single realization of the Waukegan Station plume is studied with emphasis on its information content. Areas between isotherms at various depths are computed together with volumes of water in given temperature ranges above ambient; these measurements indicate the extent of the various parts of the plume together with the heat content of each part.

This report recommends developing a statistical model to characterize the three-dimensionall pattern of thermal plumes, It indicates the danger of drawing detailed conclusions on the basis of a small number of observations, and emphasizes the need for proper interpretation of empirical measurements, Two reports, on the discharges (1) from the Dresden Power Station into the Illinois River and (2) from Waukegan Station into-Lake Michigan are analyzed. In conclusion, a plan for interpretation of temperature measurements is recommended.

In a previous report on effects of thermal discharges from power plants into the Great Lakes, we stressed the need for a statistical analysis of the spatial and temporal pattern of the thermal plume. The plume pattern is recognized as stochastic in nature and requires statistical analysis. A single realization of the Waukegan Station plume is studied with emphasis on its information content. Areas between isotherms at various depths are computed together with volumes of water in given temperature ranges above ambient; these measurements indicate the extent of the various parts of the plume together with the heat content of each part.

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The difficulty of applying the WKB approximation to problems involving arbitrary potentials has been confronted. Recent work has produced a convenient expression for the potential correction term. However, this approach does not yield a unique correction term and hence cannot be used to construct the proper modification. An attempt is made to overcome the uniqueness difficulties by imposing a criterion which permits identification of the correct modification. Sections of this work are: semiclassical eigenvalues for potentials defined on a finite interval; reactive scattering exchange kernels; a unified model for elastic and inelastic scattering from a solid surface; and selective absorption on a solid surface. (GHT)

A description of the sequence of events and the decisions leading to the design of a versatile pulse programmer for pulsed NMR are presented. Background and application information is discussed in order that the reader might better understand the role of the pulse programmer in a NMR spectrometer. Various other design approaches are presented as a basis for comparison. Specifications for this design are proposed, the hardware implementation of the specifications is discussed, and the software operating system is presented.

Progress is reported on the following studies: chemistry studies designed to achieve a more complete understanding of the fundamental chemistry of technetium in order to facilitate the design of future radiopharmaceuticals incorporating the radionuclide /sup 99m/Tc; the development of new radiopharmaceuticals intended to improve image quality and lower radiation doses by the use of short-lived radionuclides and disease-specific agents; the development of short-lived positron-emitting radionuclides which offer advantages in transverse section imaging of regional physiological processes; and studies of the toxic effects of particulate radiation.

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The Los Alamos Scientific Laboratory contribution to the Waste Isolation Safety Assessment Program, Task 4, for the second quarter of FY-79 involved plutonium, americium, and uranium (VI) batch sorption studies on argillite, is presented. The behavior of plutonium and americium in aqueous solutions at pH approx. = 8 with respect to container sorption, filtering, and centrifuging was also investigated. Studies of the variability of the sorption behavior for tuff were completed. Migration rate studies on crushed and fractured materials were initiated. The development of the systems for performing controlled atmosphere measurements has been completed. Additional chemical analysis has been performed, as were some studies related to microautoradiography. Additional cation exchange capacity and ethylene glycol surface area measurements have also been made.

Laser plasma experiments at the Lawrence Livermore Laboratory have progressed very rapidly and have achieved new milestones in both the implosion and DT gain in laser fusion targets. New diagnostic methods were also developed for determining the state of the compressed fuel and the plasma processes which are occurring in the absorption and scattering of the laser light incident on the laser fusion pellets. A review of the program is given. (MOW)

The Multicomponent Mass Transfer (MMT) Model is a generic computer code, currently in its third generation, that was developed to predict the movement of radiocontaminants in the saturated and unsaturated sediments of the Hanford Site. This model was designed to use the water movement patterns produced by the unsaturated and saturated flow models coupled with dispersion and soil-waste reaction submodels to predict contaminant transport. This report documents the theorical foundation and the numerical solution procedure of the current (third) generation of the MMT Model. The present model simulates mass transport processes using an analog referred to as the Discrete-Parcel-Random-Walk (DPRW) algorithm. The basic concepts of this solution technique are described and the advantages and disadvantages of the DPRW scheme are discussed in relation to more conventional numerical techniques such as the finite-difference and finite-element methods. Verification of the numerical algorithm is demonstrated by comparing model results with known closed-form solutions. A brief error and sensitivity analysis of the algorithm with respect to numerical parameters is also presented. A simulation of the tritium plume beneath the Hanford Site is included to illustrate the use of the model in a typical application. 32 figs.

This report details activities of the Pacific Northwest Laboratory`s Division of Production and Hanford Plant Assistance Programs for the month of April 1970.

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Ways of detecting tau neutrinos emerging from a beam dump are studied. Key signatures are elaborated and contrasted with background arising from muon and electron neutrino interactions. Expected event rates are given for various neutrino spectra. 16 references.

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Evacuation, sheltering followed by population relocation, and iodine prophylaxis are evaluated as offsite public protective measures in response to potential nuclear reactor accidents involving core-melt. Evaluations were conducted using a modified version of the Reactor Safety Study consequence model. Models representing each protective measure were developed and are discussed. Potential PWR core-melt radioactive material releases are separated into two categories, ''Melt-through'' and ''Atmospheric,'' based upon the mode of containment falure. Protective measures are examined and compared for each category in terms of projected doses to the whole body and thyroid. Measures for ''Atmospheric'' accidents are also examined in terms of their influence on the occurrence of public health effects.

The laboratory cyclone incinerator, which started operation in January, 1978, has been developed to study the effects of burning feed containing radionuclides other than /sup 238/Pu. These isotopes must be removed from the off-gas during incineration. Preliminary data from early runs show that the combustion efficiency of the incinerator can still be improved. Controlled experiments were conducted on the pressed ash-cement pellet matrix to define compressive strength, mechanical stability, density, and effect of curing environment (wet cure and dry cure). Leachability studies were initiated on pressed sludge/cement matrix in distilled water at ambient temperature. Compressive strengths of sludge/cement pressed matrix samples were investigated. Physical and chemical attributes of incinerated ash were evaluated in relationship to the ash/cement matrix. 7 figs., 6 tables.