A description is given of methods used for data reduction and post-processing of reduced data for the 1/5-scale Boiling Water Reactor (BWR) Mark I pressure suppression experiment. Output from approximately 200 transducers, recorded onto analog magnetic tape, were reduced to engineering quantities with an analog-to-digital, COBOL-like conversion code. The reduced data were analyzed with conversational FORTRAN codes and mass-processed for reports with batch-processing FORTRAN codes.

This Gruy Federal Type II-B prospect was drilled as the Superior Oil Company No. 1 Watkins-Miller, API designation 17-023-20501 and is located in Section 5, T15S, R5W, Cameron Parish, Louisiana. The well site is just north of lot 39 on Indian Point Island and is readily accessible from state highway Route 82 and a shell road in good condition. Superior Oil completed this well in late 1970 as a dual gas producer in sands between 11,150 and 11,250 feet but eventually abandoned the well in December, 1974. The cellar of the well is still visible on the site. This location is shown on the lower portion of USGS topographic sheet ''Grand Lake West'' in the map pocket of the Gruy Federal report ''Investigation and Evaluation of Geopressured-Geothermal Wells, Prospective Test Wells in the Texas and Louisiana Gulf Coast'', February 28, 1978.

Recent advances in design and operation of the internal PIG sources at the LBL 88-Inch Cyclotron have led to the development of high charge state (0.4 < or approx. = to Q/A < or approx. = to 0.5) heavy ion beams between lithium and neon with energies 20 < or approx. = to E/A < or approx. = to 32 MeV per nucleon, including fully stripped ions up to /sup 16/O/sup 8 +/. Total external intensities of these beams range from 10/sup 12/ particles/s for /sup 6/Li/sup 3 +/ to 0.1 particles/s for /sup 16/O/sup 8 +/. Techniques have been developed for routine tune-out of the low intensity beams. These include use of model beams and reliance on the large systematic data base of cyclotron parameters which has been developed over many years of operation. Techniques for delivery of these weak beams to the experimental target areas are presented. Source design and operation, including special problems associated with Li, Be, and B beams are discussed.

The effects of several abnormal conditions resulting from a possible non-uniform void distribution in a multifilamentary and cabled superconductor on the cryogenic recovery capability of a triplex, a seven strand bundle and a 19 strand bundle were studied. For a triplex, if only one of the three strands was cooled, the maximum recoverable initial normal temperature is reduced by 1/3 of the value for the nominal case in which all the three strands are cooled equally. If the outer six strands of a seven strand bundle were cooled and the center one was not cooled, the recovery capability of this bundle is just slightly below that of the nominal triplex. If only the outer 12 strands of a 19 strand bundle were cooled, the bundle would not recover once it is driven normal. The effects of the cold and stagnant helium located in the space between the strands and of the insulation thickness are small.

This report presents the results of a laboratory effort which was undertaken to determine mechanical properties of salt from Lyons, Kansas. Another goal of the experimental work was to define testing procedures, calibrations and data reduction during the process of generating strength data. Mechanical properties such as modulus of deformation and principal strain ratio were incorporated into simulations of Project Salt Vault using finite element methods. Deformational behavior of Lyons salt subjected to constant stress levels for extended periods of time was also evaluated in this experimental effort and compared to results determined for salt from other locations. Strength data and empirical relationships of strain as a function of time, stress and temperature were reduced for application to finite element analyses.

The design requirements, subsystem characteristics, environmental requirements, and cost and performance evaluation techniques are defined for the HTLF Large Solar Power System. The system is described as consisting of an array of linear focusing heliostats focusing on tower-mounted linear receivers. Heat transfer is by water/steam, and sensible heat storage is in oil/rock. (LEW)

An automated, controlled-flow air infiltration measurement system is described. This system measures total air flow, a volume per unit time, due to infiltration in a test space. Data analysis is discussed and the mixing problem is analyzed. Different modes of operating the system are considered: concentration decay, continuous flow in a single chamber; and continuous flow in a multichamber enclosure. Problems associated with the use of nitrous oxide as a tracer gas are described.

A rapid method is presented for calculating transport in a network of one-dimensional flow paths or ''pipes''. The method defines a Green's function for each flow path and prescribes a method of combining these Green's functions to produce an overall Green's function for the flow path network. A unique feature of the method is the use of the Laplace transform of these Green's functions to carry out most of the calculations.

The possible operating points of air/water and helium/water steam generators are parametrically presented. Calculation procedures and a sample computer program listing are provided. Multiple saturated steam conditions are shown to be attainable with the same gas inlet and exit temperatures. Design considerations of heat transfer surface area and pumping requirements are also discussed.

A Heavy Ion Accelerator system is described which is based upon existing technology, and which is capable of producing 150 MW of average beam power in 10 MJ, 200 TW bursts, 15 times per second. It consists of an rf linac which accelerates doubly ionized uranium ions to an energy of 20 GeV. Then by utilizing the well known procedure of multiturn injection, a 6.6 ms long burst of linac current is stored in 8 separate &#x27;&#x27;accumulator&#x27;&#x27; rings. At the conclusion of the filling process, a pulsed rf system bunches the beam in each of the 8 rings simultaneously. As the bunches decrease in length, they are then extracted from the rings and transported for about 1 km to one of 5 &#x27;&#x27;boilers&#x27;&#x27;, in which the thermonuclear pellet has been placed. The 8 beams (2 opposing clusters of 4 beams each) are then focused simultaneously onto the pellet, resulting in a release of thermonuclear energy about 80 times larger than the input beam energy.

Solid state lasers for fusion experiments must reliably deliver maximum power to small (approximately .5 mm) targets from stand-off focal distances of 1 m or more. This requirement places stringent limits upon the optical quality, resistance to damage, and overall performance of the several major components--amplifiers, Faraday isolators, spatial filters--in each amplifier train. Component development centers about achieving (1) highest functional material figure of merit, (2) best optical quality, and (3) maximum resistance to optical damage. Specific examples of the performance of large aperture components will be presented within the context of the Argus and Shiva laser systems, which are presently operational at Lawrence Livermore Laboratory. Shiva comprises twenty amplifiers, each of 20 cm output clear aperture. Terawatt beams from these amplifiers are focused through two opposed, nested clusters of f/6 lenses onto such targets. Design requirements upon the larger aperture Nova laser components, up to 35 cm in clear aperture, will also be discussed; these pose a significant challenge to the optical industry.

Line /sup 1///sub 2/''-PCS-6-VA outside the LOFT containment penetration S-5B was analyzed to ASME Code, Subsection NC (Class 2) criteria. This piping is part of the Containment Isolation System. The model considered the piping from the penetration through one isolation valve and to the first wall through which the line passes. Results of this anlysis show that this section of the line will meet Class 2 requirements without modification.

A forecast for solar-trained manpower needs was produced based on projected demand for solar systems and manpower requirement for solar systems. A skills analysis was made to determine the types of training required to produce manpower capable of performing the tasks identified in the task analysis. (MHR)

The paper discusses development of a resource allocation methodology for the BCS group to determine which energy conservation projects to fund if it is not possible to support all candidate programs and to determine how many projects to fund in one area to maintain minimal duplication. The current status of the methodology is presented. Section II deals with the technique used to evaluate a single portfolio. Section III describes the algorithm used to select the portfolios for evaluation. The search technique is described in Section IV. Information on the overall portfolio in Section IV is tabulated according to rank, project number, funding level, group number, research cost of addition, net benefit, marginal benefit, marginal rate of return, and cumulative rate of return. A summary of results is presented in Section V and group results are presented in Section VI. A table in Section VII lists the projects in numerical order with their group number, possibility of success, energy cost savings with and without DOE funding, and research cost of the project. (MCW)

A data base containing insolation and meteorological parameters at 15 minute intervals for the entire year of 1976 at Barstow, California has been prepared on computer compatible magnetic tape. The observed insolation values obtained by the Southern California Edison Company and meteorological values obtained by the Federal Aviation Agency which form the data base have been carefully checked for internal consistency. The data tape is written in a modified form of the SOLMET format and is available from The Aerospace Corporation. The data included on the tape, the sources of the data, and any editing performed on the data itself are described in detail.

A beam of relativistic particles moving inside a conducting pipe of circular cross-section is displaced from the axis of the pipe. The presence of a discontinuity in the pipe (e.g., an accelerating gap) will cause a redistribution of the image charges and currents, and a net transverse force is experienced by beam particles as they transverse the gap. This force is calculated in the static limit for the particular geometry of 3 cm wide gaps spaced 30 cm apart in a pipe of radius 7.5 cm.

As the Nuclear Regulatory Commission has not yet issued a format guide for the preparation of an environmental impact statement for radioactive waste repositories, Rockwell Hanford operations has developed an annotated outline which will serve as the basis for the environmental evaluation activities until replaced by an appropriate NRC regulatory guide. According to the outline, the applicant should summarize the major environmental effects that are expected to occur during the construction, operation, and terminal isolation phases of the radioactive material repository. Compare these environmental effects with the possible effect of continued use of interim storage facilities. Unless unforeseen environmental effects become apparent, the summary should be a positive statement indicating that the short-term environmental effects are outweighed by the long-term benefits of the repository. (JSR)

A brief summary is presented of major accomplishments in a research program on the impact of synthetic fuels, electric vehicles, and railroad electification on energy consumption by the US transportation sector. (LCL)

An indirect method for estimating the inventory of a uranium enrichment cascade which presumably can be performed by the International Atomic Energy Agency within the Non-Proliferation Treaty limitations on its safeguards activities was devised and tested at the Oak Ridge Gaseous Diffusion Plant (ORGDP). This method involves the feeding of a cascade with uranium that is significantly richer in one component than the normal cascade feed for a short period of time, and the measurement of the subsequent transient concentrations of this component in the cascade withdrawal streams. The inventory estimate is then obtained from a comparison of the observed data with parallel data calculated for an appropriate but non-identical cascade model. The validity of the method is demonstrated numerically by parallel calculations made for two nearly ideal hypothetical cascade models. A test of this method conducted in the ORGDP cascade, utilizing U-236 as the spike component, yielded an estimate of the cascade inventory greater by 3.0% than that determined by the usual measurement method. The proposed method has been devised for use at enrichment plants that are subject to safeguarding by the IAEA and for which the proprietors will permit the inventories to be known. The method does not …

This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development. Selected bibliographic information on LMFBRs relative to the development and safety of the breeder reactor is presented for the year 1977. The bibliography consists of approximately 198 abstracts covering research and development, operating experience, and design practices. Keyword, author, and permuted-title indexes are included for completeness.

Young adult male and female mice of inbred strains, A, BALB/c, C57BL/6, and C57L, and B6CF/sub 1/ and F/sub 2/ hybrids were exposed to daily duration-of-life external /sup 60/Co ..gamma.. irradiation. Age at death was recorded, and most decedents were necropsied to ascertain occurrence of major types of tumors. Age- and cause-specific mortality or incidence rates were derived, and their regressions on age were fitted with polynomial equations by least-squares procedures. Age-specific and age-adjusted integrated lifetime risk in excess of the control population was expressed as the mortality ratio (irradiated/control). Linear and nonlinear functions and widely different life expectancies can be accommodated by this technique. These basic actuarial statistics provide a means for comparative analysis of dose-response functions, sex and genetic variables, relative vs. absolute risk, protraction or dose-rate factors, and major contributing causes of excess risk. They also provide a basis for extrapolation to man. As examples, life shortening in days per rad (4 days/100 rads accumulated) is generally independent of sex, genotype, and daily dose rate. The integrated average lifetime risk of death related to all tumors (0.025%/rad) is largely independent of sex, genotype and dose-rates <12 rads/day, despite the fact that tumor incidence varies by a factor …

Further progress is reported on a continuing experimental program designed to select high-performance polymeric materials for use in geothermal power plants. In field tests 12 nozzles, 27 wear plates, and 2 types of polymer lined pipe were tested. Nozzles made of Teflons TFE and PFA, Tefzel, Ryton PPS and H-Resin/carbon cloth were little changed except for some scaling. The fluorocarbons scaled least rapidly. All blade type wear plates eroded, those based on Tefzel, PPQ, and PPS the least. Fluorocarbon lined pipes were little affected by exposure. In laboratory tests samples were heated at 250 and 300/sup 0/C in brine. Several materials including fluorocarbon and unhydrolyzable aromatic or cross-linked aliphatic, thermally stable polymers survived for periods up to 1300 h. In erosion tests, coatings based on epoxy resins and a fluorocarbon were most resistant; good adhesion was required.

The 12 in. H and V Duct and related piping outside the LOFT containment and connected to containment penetration S-11B was analyzed to ASME Code, Subsection NC (Class 2) criteria. This duct is part of the Containment Isolation System. The model considered the duct from the containment O.D. outward through the second isolation valve. Results of this analysis show that this section of the line will meet Class 2 requirements without modification.

The stress corrosion susceptibility of Type 5083 aluminum--magnesium alloy in plate form and press-formed shapes was determined in the short transverse direction. C-ring type specimens were exposed to alternate immersion in a sodium chloride solution. The test equipment and procedure, with several innovative features, are described in detail. Statistical test results are listed for seven thermomechanical conditions. A certain processing scheme was shown to yield a work-strengthened part that is not sensitized with respect to stress corrosion cracking.