The results of an accurate determination of the recoil spectrum from (n, ..gamma..) reactions in molybdenum are presented. The recoil spectrum has been calculated from nuclear level structure data and measured branching ratios. Angular correlations between successive gammas have been accounted for using the standard theoretical techniques of Racah algebra and the density matrix formalism.

A laser fusion reactor concept is described that employs liquid metal walls. The concept envisions a porous medium, called the JADE, of specific geometry lining the reactor cavity. Some advantages and disadvantages of the concept are pointed out. The possibility of using heat pipes for passive cooling in ICF reactors is discussed. Some of the problems are outlined. (MOW)

This study is designed to assist the Division of Geothermal Energy (DGE) in deciding what kind of strategy it wants and needs in order to make its international effort as cost-effective and appropriate as possible. The purpose of this study is to construct a logic base on which DGE can, in turn, establish its own strategy for international cooperation, and can begin to plan for necessary organization, procedural and policy reforms. This report will constitute a set of decision guidelines for DGE to consider in determining the nature of future strategy-related reforms. Each chapter asks, and then answers, the question on which it is centered as follows: (1) what are the deficiencies in DGE's current approach; (2) what should an international strategy for DGE ensure; (3) how can an international strategy for DGE be manifested; (4) which strategic model presents the best opportunity now; and (5) how can the recommended alternative be achieved.

The transported volume of spent fuel, incident/accident experience and accident environment probabilities were reviewed in order to provide an estimate of spent fuel accident probabilities. In particular, the accident review assessed the accident experience for large casks of the type that could transport spent (irradiated) nuclear fuel. This review determined that since 1971, the beginning of official US Department of Transportation record keeping for accidents/incidents, there has been one spent fuel transportation accident. This information, coupled with estimated annual shipping volumes for spent fuel, indicated an estimated annual probability of a spent fuel transport accident of 5 x 10/sup -7/ spent fuel accidents per mile. This is consistent with ordinary truck accident rates. A comparison of accident environments and regulatory test environments suggests that the probability of truck accidents exceeding regulatory test for impact is approximately 10/sup -9//mile.

The Vermont State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Vermont. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Vermont. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Vermont.

The compositions of 5 major types of geothermal wastes have been determined, and samples have been subjected to EPA recommended extraction tests to determine if they contain toxic metals that would classify the wastes as hazardous. Of the samples tested, the extracts of geothermal brines clearly contain levels of As, Ba and Pb exceeding the maximum allowed concentrations that characterize wastes as toxic. Only one other waste type, geothermal scale, exhibited EP toxicity. Pb was found in the extract of geothermal scale at a level of 7 mg/l, only 2 mg/l over the maximum limit. All of the other types of geothermal waste samples showed levels of toxic metals in the extracts well below the regulated limits.

The basic idea of this diagnostic routine is to check out a parallel type A1 CAMAC Crate Controller using CDL.

In an earlier project, a literature search identified 60 underground openings in crystalline rock capable of providing access for an in-situ experimental facility to develop geochemical and hydrological techniques for evaluating sites for radioactive waste isolation. As part of the current project, discussions with state geologists, owners, and operators narrowed the original group to 14. Three additional sites in volcanic rock and one site in granite were also identified. Site visits and application of technical criteria, including the geologic and hydrologic settings and depth, extent of the rock unit, condition, and accessibility of underground workings, determined four primary candidate sites: the Helms Pumped Storage Project in grandiodorite of the Sierra Nevada, California; the Tungsten Queen Mine in Precambrian granodiorite of the North Carolina Piedmont; the Mount Hope Mine in Precambrian granite and gneiss of northern New Jersey; and the Minnamax Project in the Duluth gabbro complex of northern Minnesota.

Flue gas conditioning approaches for the Brayton-cycle heat recovery system are discussed. This revision incorporates the results of recent AiResearch tests on the subatmospheric system (SAS) turbocompressor, as well as the Electric Power Research Institute sponsored tests on ceramic fiber filters. The two primary purposes of the gas conditioning evaluation are: to determine the need for protecting the Brayton-cycle turbocompressor and heat exchanger from the potential damaging effects of erosion and deposition, and to determine what type of approach should be used for cleanup, if protection by flue gas conditioning is required.

A survey of wet cooling tower literature was performed to develop a simplified method of cooling tower design and simulation for use in power plant cycle optimization. The theory of heat exchange in wet cooling towers is briefly summarized. The Merkel equation (the fundamental equation of heat transfer in wet cooling towers) is presented and discussed. The cooling tower fill constant (Ka) is defined and values derived. A rule-of-thumb method for the optimized design of cooling towers is presented. The rule-of-thumb design method provides information useful in power plant cycle optimization, including tower dimensions, water consumption rate, exit air temperature, power requirements and construction cost. In addition, a method for simulation of cooling tower performance at various operating conditions is presented. This information is also useful in power plant cycle evaluation. Using the information presented, it will be possible to incorporate wet cooling tower design and simulation into a procedure to evaluate and optimize power plant cycles.

The turbine tests and results for the Brayton cycle subatmospheric system (SAS) are summarized. A scaled model turbine was operated in the same environment as that which a full-scale SAS machine would experience from the hot effluent flue gas from a glass container furnace. The objective of the testing was to evaluate the effects of a simulated furnace flue gas stream on the turbine nozzles and blades. The following specific areas were evaluated: erosion of the turbine nozzles and blades from the dust in the flue gas, hot corrosion from alkali metal salts in the dust and acid vapor (sulfur trioxide and hydrogen chloride) in the flue gas, and fouling and flow blockage due to deposition and/or condensation from the flue gas constituents.

The importance of the neutron capture process and the status of the more important cross section data are reviewed. The capture in fertile and fissile nuclei is considered. For thermal reactors the thermal to epithermal capture ratio for /sup 238/U and /sup 232/Th remains a problem though some improvements were made with more recent measurements. The capture cross section of /sup 238/U in the fast energy range remains quite uncertain and a long standing discrepancy for the calculated versus experimental central reaction rate ratio C28/F49 persists. Capture in structural materials, fission product nuclei and the higher actinides is also considered.

This study is a new preliminary conceptual design and economic analysis of an inertial confinement fusion (ICF) power plant performed by Bechtel under the direction of Lawrence Livermore National Laboratory (LLNL). The purpose of a new conceptual design is to examine alternatives to the LLNL HYLIFE power plant and to incorporate information from the recent liquid metal cooled power plant conceptual design study (CDS) into the reactor system and balance of plant design. A key issue in the design of a laser fusion power plant is the degree of symmetry in the illumination of the target that will be required for a proper burn. Because this matter is expected to remain unresolved for some time, another purpose of this study is to determine the effect of symmetry requirements on the total plant size, layout, and cost.

This report covers research in: energy analysis; energy efficiency studies; solar energy; chemical process; energy-efficient buildings; environmental pollutant studies; combustion research; laser spectroscopy and trace elements; and oil shale and coal research. An energy and environment personnel listing is appended. Separate projects are indexed individually for the database. (PSB)

Resistivity data from several areas were compiled, analyzed, and interpreted in terms of possible geologic models. On the basis of this analysis alone, two areas have been ruled out for possible geothermal exploitation, two have been interpreted to have a moderate-temperature resource, and two have been interpreted to have a high-temperature resource. The two areas which have been ruled out are the Keaau and South Point areas. The Kawaihae area and the lower northwest rift zone of Hualalai appear to have anomalous resistivity structures, which suggest a moderate-temperature resource in each of these areas. Finally, specific areas in the lower southwest and lower east rift zones of Kilauea have been outlined as locations where high-temperature fluids may exist at depth.

This document discusses computer surety in NRC-licensed nuclear facilities from the perspective of physical protection inspectors. It gives background information and a glossary of computer terms, along with threats and computer vulnerabilities, methods used to harden computer elements, and computer audit controls.

The following aspects of solar access are discussed: solar geometry, topography, orientation, trees and vegetation, design options, and legal questions. (MHR)

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to ecology. This report discuses programs including a development project for microcosm screening systems, two initiatives in ecological modeling, and a program of field experiments for a national assessment of crop losses due to air pollution.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

This paper describes a computational method for improving the accuracy of a given eigenvalue and its associated eigenvector. The method is analogous to iterative improvement for the solution of linear systems. An iterative algorithm using working precision arithmetic is applied to increase the accuracy of the eigenpair. The only extended precision computation is the residual calculation. The method is related to inverse iteration and to Newton's method applied to the eigenvalue problem.

The papers presented at the first annual workshop on ice storage for cooling applications by participants from the U.S. and Canada are summarized. Novel methods of preparing naturally frozen ice and storing it are described. Attention is given to technical and economic problems and related design considerations. Comparison is made with conventional air conditioning methods. Both industrial and residential applications are discussed with regard to cost.

"In recent years, the increasing sophistication of transmission electron microscope (TEM) studies of materials has necessitated more exacting methods of specimen preparation. The present report describes improved equipment and techniques for electropolishing and chemically polishing a wide variety of specimens. Many of the specimens used in developing or improving the techniques to be described were irradiated with heavy ions such as nickel or vanadium to study radiation damage. The high cost of these specimens increased the need for reproducible methods of initial preparation, postirradiaton processing, and final thinning for TEM examination. A technique was also developed to salvage specimens that had previously been thinned but were unusable for various reasons. Jet polishing is, in general, the method of choice for surface polishing, sectioning, and thinning. The older beaker electropolishing method is included in this report because it is inexpensive and simple, and gives some insight into how the more recent methods were developed. 29 figures, 8 tables. (ERA citation 07:004650)."--NTIS abstract.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward (1) investigating alternative concepts for components of molten carbonate fuel cell stacks and (2) improving our understanding of component behavior.