In an effort to understand the expected performance of snubbers, a survey of current design methods was performed. Questionnaires were sent to the major snubber manufacturers requesting information on important phases of snubber analysis, testing, shipping, and handling. The elements of design considered in the questionnaire were derived from an evaluation of snubber failure histories and the performance requirements of snubber users.

A case study of the French CEREN system is provided. The foundation of the system is outlined, that is, the concepts that ensure the systems comprehensiveness, detail, and manageability. The implementation of the system is emphasized, in particular, the data collection and data processing methodology. Applications of the CEREN energy information system are reviewed for analyzing energy use, cross-industry impacts, and social, and economic impacts of changing energy-use patterns. (MHR)

The Closed Loop In-Reactor Assembly (CLIRA) is a test vehicle for in-core material and fuel experiments in the Fast Flux Test Facility (FFTF). The FFTF is a fast flux nuclear test reactor operated for the Department of Energy (DOE) by Westinghouse Hanford Company in Richland, Washington. The CLIRA is a removable/replaceable part of the Closed Loop System (CLS) which is a sodium coolant system providing flow and temperature control independent of the reactor coolant system. The primary purpose of the CLIRA is to provide a test vehicle which will permit testing of nuclear fuels and materials at conditions more severe than exist in the FTR core, and to isolate these materials from the reactor core.

A novel grid structure that is cooled only by radiation and conduction is shown to be capable of continuously extracting 2.5 kA.m/sup -2/ of 1-keV positive deuterium ions while dissipating a power loading of 0.4 MW.m/sup -2/.

A study was conducted of the University of California's Lawrence Livermore Laboratory Quality Assurance Program, which focused on training needs and recommendations tailored to the various on-going programs. Specific attention was directed to an assessment of the quality status for the MFTF facility and the capabilities of assigned quality project engineers. Conclusions and recommendations are presented which not only address the purpose of this study, but extend into other areas to provide insight and needs for a total cost effective application of a quality assurance program.

Until the Rotating-Target Neutron Source II (RTNS II) and the Li(D,n) stripping source for high fluxes of high-energy neutrons are in operation, work related to DMFE's fusion-reactor materials and radiation-effects program is being conducted with lower-flux prototypes, the RTNS I at LLL and a Be(D,n) stripping source at the University of California, Davis. This paper describes these sources and presents results of some exploratory experiments in which 0.5-mm-thick tensile specimens of copper, vanadium, niobium, and Nb-1 wt% Zr alloy were irradiated by high-energy neutrons from these sources and by lower-energy neutrons from the Livermore Pool-Type Reactor (LPTR). After being irradiated, the specimens were tensile-tested, and the increases in their 0.2%-offset yield strengths were related to the neutron fluences and energies to which they had been subjected.

This paper assesses a method for extracting tritium from liquid lithium for specific application to the conceptual laser fusion reactor that uses a continuous lithium ''waterfall.'' The tritium diffuses through a refractory metal that contains a getter and is then stored in a hydride-forming alloy. There are various uncertainties with this method including helium-4 extraction, unknown impurities that may accumulate in liquid lithium, the effects of these impurities on tritium separation, and the maintenance of tritium-contaminated equipment. Our study indicates that major tritium losses will occur during equipment maintenance rather than as a result of permeation losses through the primary vessel.

The reactor design is a multicell arrangement wherein a series of field-reversed plasma layers are arranged along the axis of a long superconducting solenoid which provides the background magnetic field. Normal copper mirror coils and Ioffe bars placed at the first wall radius provide shallow axial and radial magnetic wells for each plasma layer. Each of 11 plasma layers requires the injection of 3.6 MW of 200 keV deuterium and tritium and produces 20 MW of fusion power. The reactor has a net electric output of 74 MWe and an estimated direct capital cost of $1200/kWe.

The fission product inventory, fission product release fractions, and radiation levels following a blowdown into the test chamber are presented. Operating sequences discussed are based on present knowledge and are used for the purpose of calculating radiation levels at different times.

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An experimental program was conducted to assess the endurance and lifetime of HEPA filters exposed to fire-generated aerosols, and to reduce the aerosol exposure by installing engineering countermeasures in the duct between the fire source and HEPA filters. Large cribs of wood and other potential fuels of interest were ''forcefully burned'' in a partially ventilated enclosure. In a ''forceful burn'' the crib of fuel is continuously exposed to an energetic premixed methane flame during the entire experimental period. This tactic serves two purposes: it optimizes the production of smoke rich in unburned pyrolyzates which provides severe exposure to the filters, and it facilitates the ignition and enhances the combustion of cribs formed with synthetic polymers. The experiments were conducted in an enclosure specifically designed and instrumented for fire tests. The test cell has a volume of 100 m/sup 3/ and includes instrumentation to measure the internal temperature distribution, pressure, thermal radiation field, flow fields, gas concentration, particulate size distribution and mass, fuel weight loss, inlet and exit air velocities, and smoke optical density. The countermeasure techniques include the use of passively operated sprinkler systems in the fire test cell, of fine and dense water scrubbing sprays, and of rolling prefiltration …

A stress analysis was performed on the 2''-IA-299-AB pipe system inside containment penetration S-5B. Deadweight, thermal expansion and seismic loads were considered. The results indicate that this piping will meet ASME Section III, Class 2 requirements.

Line 2''-IA-295-AB outside containment penetration S-2A was analyzed to ASME Section III, Subsection NC (Class 2) criteria. The line is part of the Containment Isolation System. The model considered the line from the penetration outward through the first isolation valve. Results of the analysis show that this section of the line meets Class 2 requirements without modification.

A stress analysis of the LOFT Diesel Generator ''A'' Exhaust Stack was performed to determine its reaction to Safe-Shutdown Earthquake loads. The exhaust stack silencer and supporting foundation was found to be inadequate for the postulated seismic accelerations. Lateral support is required to prevent overturning of the silencer pedestal and reinforcement of the 4'' x 0.5'' silencer base straps is necessary. Basic requirements for this additional support are discussed.

A methodology, employing the concept of risk, is described which was created to aid in building an efficient spare parts inventory for the LOFT secondary coolant system.

This report evaluates the performance of the vital MG sets during a worst case load transfer. Evaluation of test data showed: (1) The Vital MG Set withstood the extreme loading; (2) The load can be sustained well in excess of the required time limit; and (3) The transfer perturbation caused the frequency to exceed the limits set by the SDD. The follow up evaluations of the equipment powered by the MG sets demonstrated that the equipment function will not be degraded.

A plan for the continuation of the Energy Conservation Program for State and Local Code officials is presented. The program is action-oriented, e.g., develop the enforcement tools, train the personnel in their use, and assist in the field use of these tools. Achievements to date include: the Model Code for Energy Conservation in New Building Construction has been developed and published; the basic training materials for the model code have been developed and tested in prototype field courses in 4 states; implementation activities have been proceeding, at times even before publication of final documents; the Model Code Groups are conducting courses for their members; and coordination and field awareness of the program has been achieved using many mechanisms. The management structure, constraints, and the milestone plan and management report are described. Data on the manpower, cost, and travel plans are included.

Progress in developing foil bearings for a miniature isotope-fueled Brayton cycle power system rotating unit (BRU) for space vehicles is reviewed with charts, tables, and diagrams of the program plan and schedule; performance testing; fabrication and inspection; and materials development. (LCL)

The objective of this project is the development of a preliminary design for a full-sized, closed cycle, ammonia power system module for the 100 MWe OTEC Demonstration Plant. In turn, this Demonstration Plant is to demonstrate, by 1984, the operation and performance of an ocean thermal power plant having sufficiently advanced heat exchanger design to project economic viability for commercial utilization in the late 1980's and beyond. Included in this power system development are the preliminary designs for a proof-of-concept pilot plant and test article heat exchangers which are scaled in such a manner as to support a logically sequential, relatively low-cost development of the full-scale power system module. The conceptual designs are presented for the Demonstration Plant power module, the proof-of-concept pilot plant, and for a pair of test article heat exchangers. Costs associated with the design, development, fabrication, checkout, delivery, installation, and operation are included. The accompanying design and producibility studies on the full-scale power system module project the performance/economics for the commercial plant. This section of the report describes the full-size power system module, and summarizes the design parameters and associated costs for the Demonstration Plant module (prototype) and projects costs for commercial plants in production. The …

The project objective is a basic evaluation of the technical performance and economic feasibility of providing low temperature heating by Forces Geoheat Recovery (FGR) from suitable geological structures including both thin sheet conductors with predominantly fracture flow and porous slab conductors with intergranular flow. Simple, heat-pump assisted and multi-source combined heating systems will be evaluated. Building and industrial heating applications with effective power requirements ranging upward from one MWt will be considered, with thermal water supply temperatures in the range of 25 C to 100+ C. Emphasis is being placed on the adaption of the FGR technology to the user system, including both short and long term variations in the user system demand.

92,000 BeO--UO/sub 2/ fuel elements were fabricated for the upgrading of the Sandia Annular Core Pulse Reactor. The toxicity of BeO and the radioactivity of /sup 235/U necessitated special handling procedures and equipment. This document describes the materials, specifications, and fabrication process. (DLC)

Some of the studies in progress are: distribution of deposited energy around heavy-ion tracks; effect of trapping on the thermalization of electrons in hydrocarbon liquids; effect of field-dependent mobility on escape probability; kinetics of electron scavenging reactions; second-order optical properties of solvated electrons; model molecular orbital studies of the chemisorption of atomic hydrogen and oxygen on aluminum surfaces; calculation of sum rule moments for H/sub 2/O; early events in pulse-irradiated polar liquids; radiation chemical studies of reactions of SO/sub 4//sup -/ radicals with organic compounds; reactions of the phosphate and sulfate radicals with inorganic compounds; pulse radiolysis studies of antioxidants in fatty acid soap aggregates; spectrophotometric pulse radiolytic study of the radicals produced by reduction of cis- and trans-azobenzene; correlation of singlet energies of aromatic hydrocarbons with the rates of protonation of their anion radicals; the association rate of sodium laurylsulfate micelle-monomer equilibrium; transfer of an organic molecule between micelles in an aqueous environment; in-situ photolysis ESR study of some reactions of phosphate radicals; photochemistry of sydnones; differentiation of triplet state and biradical reactions; photoenolization of aromatic ketones; and studies of Ni(III) macrocyclic ligand complexes. (LK)

Progress in various studies is reported including studies on: vapor phase structures of inorganic salts; solvated electrons; exchange perturbation theory for many-electron interactions; concept of orbital following; calculation of vibrational form factors in electron impact excitation; limiting behavior of molecule-molecule inelastic collision amplitude at zero momentum transfer; partially diffusion-controlled reactions of isolated pair in condensed media; field-dependent mobilities, T-R energy transfer between electronically excited argon and ground-state CO/sub 2/; dose and dose-rate effects in the radiolysis of liquids; coulombically correlated charge-pair distribution and recombination--the role of non-Gaussian diffusion; non-bonded interactions; pulse radiolysis studies of hydrocarbon radical scavenging processes; oxidation of methoxyhydroxycyclohexadienyl radicals by quinones; reaction of hydroxyl radical with phenol; solvent effects on the lifetimes of photogenerated biradicals; oxidation of amines by triplet duroquinone; production of singlet oxygen from excited states of aliphatic ketones; and measurement of electron spin-lattice relaxation times. (LK)

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