Power from inertial confinement fusion holds much promise for society. This paper points out many of the benefits relative to combustion of hydrocarbon fuels and fission power. Potential problems are also identified and put in perspective. The progress toward achieving inertial fusion power is described and results of recent work at the Lawrence Livermore National Laboratory are presented. Key phenomenological uncertainties are described and experimental goals for the Nova laser system are given. Several ICF reactor designs are discussed.

Molybdenum catalysts (both supported and unsupported) have been examined in various stages of preparation and use with respect to BET surface area and low temperature oxygen chemisorption. The results are detailed. X-ray diffraction has been used to characterize ammonium molybdate - after calcination, heated in tetralin under nitrogen and after use in an autoclave. Metal salts have been tested for catalytic effects by heating a tetralin-coal mixture (without hydrogen) at a loading of 1% of the coal. Only ammonium heptamolybdate and stannous chloride had a large incremental effect (based on blank runs with tetralin and catalyst without coal). Differences in liquefaction behavior in tubing bombs and in autoclaves are explained by thermodynamic considerations based on the gas to liquid volume in the two cases. (LTN)

A refrigeration system for the 3 m phi x 5 m superconducting solenoid for the Collider Detector at Fermilab has been installed and operated with a dummy load. The nominal 600-W capacity of the system was achieved in the initial test. The solenoid and integral control dewar were tested in Japan with a 300-W refrigerator. The cooldown time was 7 days and the measured heat load of 35 W agrees well with the estimated value.

PNL and its consultants conclude that the TDI diesel engines at the GGNS have the needed operability and reliability to fulfill their intended (auxiliary) emergency power function for the first refueling cycle. This conclusion is reached with a number of understandings regarding limits to the engine requirements, NRC concurrence with MP and L findings/conclusions regarding items to be supplied to NRC, limitations on the engine Brake Mean Effective Pressure (BMEP), and MP and L's implementation of the modifications to their proposed surveillance and maintenance program.

The stability of spheromak equilibria with a flux core, or reversal coil, is studied by means of an ideal MHD code. Results depend critically upon whether the flux hole region (the current free area just inside the separatrix) is treated as perfectly conducting plasma or as vacuum. This indicates that the tilt and shift modes persist as resistive instabilities if they are stable in ideal MHD. Specifically, for nonoptimally shaped equilibria, the flux core must nearly touch the current channel if the flux hole is vacuum, whereas the core may be slightly outside the separatrix if the flux hole has conducting plasma. A larger margin exists for optimally shaped equilibria.

In our recent experiments on the TMX-U thermal-barrier device, we achieved the end plugging of axial ion losses up to a central cell density of n/sub c/ = 6 x 10/sup 12/ cm/sup -3/. During lower density experiments, we measured the axial potential profile characteristic of a thermal barrier and found an ion-confining potential greater than 1.5 kV and a potential depression of 0.45 kV in the barrier region. The average beta of hot end plug electrons has reached 15% and of hot central cell ions has reached 6%. In addition, we heated deuterium ions in the central cell with ICRF to an average perpendicular energy of 2 keV. During strong end plugging at low density (7 x 10/sup 11/ cm/sup -3/), the axial ion confinement time tau/sub parallel to/ reached 50 to 100 ms while the nonambiopolar radial ion confinement time tau/sub perpendicular to/ was 14 ms - independent of end plugging. Electrically floating end walls doubled the radial ion confinement time. At higher densities and lower potentials, tau/sub parallel to/ was 6 to 12 ms and tau/sub perpendicular to/ exceeded 100 ms.

For a number of years the MORSE user community has requested additional help in setting up problems using various options. The sample problems distributed with MORSE did not fully demonstrate the capability of the code. At Oak Ridge National Laboratory the code originators had a complete set of sample problems, but funds for documenting and distributing them were never available. Recently the number of requests for listings of input data and results for running some particular option the user was trying to implement has increased to the point where it is not feasible to handle them on an individual basis. Consequently it was decided to package a set of sample problems which illustrates more adequately how to run MORSE. This write-up may be added to Part III of the MORSE report. These sample problems include a combined neutron-gamma case, a neutron only case, a gamma only case, an adjoint case, a fission case, a time-dependent fission case, the collision density case, an XCHEKR run and a PICTUR run.

JAI examined alternative methods for structuring charges for Federal Interim Storage (FIS) services were examined and the conclusion reached that the combined interests of the Department and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, and (4) impact aid payments made in accordance with section 136(e) of the Act. The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under-or over-estimation in the costs used to calculate the Initial Payment of the fee including savings due to rod consolidation), (2) module costs (i.e., storage casks, drywells, or silos), and (3) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, …

Advantages of using Co-57 as an exciter for K XRFA include: a compact design that requires no x-ray tubes; the exciter-detector assembly locates remote from support electronics; on-line, at-line, or off-line configurations for monitor/measurements; systems that can be run by semi-skilled technicians, once programmed; and operated via remote terminals with results sent to control rooms; heavy element concentrations that are measurable thru industrial pipes; independent of minor changes in solution matrix or source half life with concentration results reported in near-real-time; a dynamic range of measurable concentrations that is greater than 10/sup 4/; measurement times that are reasonable even at 1 gram/liter; and for nuclear safeguards, it provides the <0.5% accuracy required by DOE for the accountability of U, Pu, or both, once the system is calibrated.

The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Licensing Plan is to establish how a disposal site will be licensed, and to provide responsibilities of participatory agencies as legislated by the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (Public Law 95-604). This Plan has been developed to ensure that the objectives of licensing are met by identifying the necessary institutional controls, participatory agency responsibilities, and key milestones in the licensing process. The Plan contains the legislative basis for and a description of the licensing process ( Process'') for UMTRA sites. This is followed by a discussion of agency responsibilities, and milestones in the Process. The Plan concludes with a generic timeline of this Process. As discussed in Section 2.1, a custodial maintenance and surveillance plan will constitute the basis for a site license. The details of maintenance and surveillance are discussed in the Project Maintenance and Surveillance Plan (AL-350124.0000). 5 refs., 4 figs.

Research is reported on: reservoir engineering and hydrogeology, geomechanics, geophysics, and geochemistry. Separate entries were prepared for 67 research activities.

Volume 2 contains the following chapters: (1) synfuels; (2) physics base and parameters for TMR; (3) high-temperature two-temperature-zone blanket system for synfuel application; (4) thermochemical hydrogen processes; (5) interfacing the sulfur-iodine cycle; (6) interfacing the reactor with the thermochemical process; (7) tritium control in the blanket system; (8) the sulfur trioxide fluidized-bed composer; (9) preliminary cost estimates; and (10) fuels beyond hydrogen. (MOW)

This is the final report of the Long-Range Planning Committee of the Lawrence Livermore National Laboratory. It describes the make-up, purpose, working assumptions, and activities of the Committee and discusses the work done by the Committee on defense matters, energy, a number of additional topics, and future long-range planning activities.

A BWR control rod drop accident (RDA) induces a rapid core power transient involving strong neutronic/thermal-hydraulic coupling, which requires a detailed multi-dimensional spatial kinetics analysis. Typical two-dimensional (r,z) RDA calculations require that the dropped rod be a center rod, as a result of geometric limitations, while in three-dimensional (x,y,z) calculations the dropped rod is generally taken to be the center rod in order to allow a quarter-core representation and limit computer running times. However, for typical BWR core loadings, the highest worth rod is not necessarily the center rod and it is not known, a priori, what effect this difference in spatial location has on the RDA dynamics. In order to evaluate the effects of this simplification, three-dimensional RAMONA-3B calculations have been performed for both a center and off-center control rod drop accident.

Two known low-temperature areas (Warm Springs fault and Crystal Hot Springs) are located in the Jordan Valley, but the primary purpose of this report is to locate other low-temperature resources not previously identified. Geothermal reconnaissance techniques utilized in this study include a temperature survey and chemical analysis of wells and springs, and temperature-depth measurements in holes of opportunity. Also, further site specific gravity modelling for the Warm Springs fault geothermal area and initial modelling for the entire valley were also conducted. Areas identified as having potential low-temperature geothermal resources at depth are: (1) the north-central valley area; (2) an east-west portion of the central valley; and (3) a north-south oriented area extending from Draper to Midvale. Each of these areas exhibits ground-water temperatures 20/sup 0/C or greater. Each area has thermal wells with common ion characteristics similar to both Crystal Hot Springs and the Warm Springs fault geothermal systems. Significant concentrations of Sr, Li, B, and F are present in many of these wells.

Traditional bioassays are unsuitable for assessing sublethal effects from ocean disposal of low-level radioactive waste because mortality and phenotypic responses are not anticipated. We compared the usefulness of chromosomal aberration and sister chromatid exchange (SCE) induction as measures of low-level radiation effects in a sediment-dwelling marine worm, Neanthes arenaceodentata. The SCEs, in contrast to chromosomal aberrations, do not alter the overall chromosome morphology and in mammalian cells appear to be a more sensitive indicator of DNA alterations caused by environmental mutagens. Newly hatched larvae were exposed to two radiation-exposure regimes of either x rays at a high dose rate of 0.7 Gy (70 rad)/min for as long as 5.5 min or to /sup 60/Co gamma rays at a low dose rate of from 4.8 x 10/sup -5/ to 1.2 x 10/sup -1/ Gy (0.0048 to 12 rad)/h for 24 h. After irradiation, the larvae were exposed to 3 x 10/sup -5/M bromodeoxyuridine (BrdUrd) for 28 h (x-ray-irradiated larvae) or for 54 h (/sup 60/Co-irradiated larvae). Larval cells were examined for the proportion of cells in first, second, and third or greater division. Frequencies of chromosomal aberrations and SCEs were determined in first and second division cells, respectively. Results from x-ray …

Volume 1-B contains the following chapters: (1) blanket and reflector; (2) central cell shield; (3) central cell structure; (4) heat transport and energy conversion; (5) tritium systems; (6) cryogenics; (7) maintenance; (8) safety; (9) radioactivity, activation, and waste disposal; (10) instrumentation and control; (11) balance of plant; (12) plant startup and operation; (13) plant availability; (14) plant construction; and (15) economic analysis.

The following are presented: thermodynamic properties of isobutane and isobutane-isopentane mixtures; a scaled fundamental equation for mixtures of isobutane and isopentane near gas-liquid critical line; and viscosities of hydrocarbons and their mixtures. (MHR)

The efficient design and operation of geothermal space heating systems requires careful analysis and departure from normal design practices. Since geothermal source temperatures are much lower than either fossil fuel or electrical source temperatures, the temperature of the delivered energy becomes more critical. Also, since the geothermal water is rejected after heat exchange, it is necessary to extract all of the energy that is practical in one pass; there is no second change for energy recovery. The present work examines several heating system configurations and describes the desired design and control characteristics for operation on geothermal sources. Specific design methods are outlined as well as several generalized guidelines that should significantly improve the operation of any geothermally heated system.

The inverse free electron laser accelerator is considered to be a potential high gradient electron accelerator. In this accelerator electrons oscillating in the magnetic field of a wiggler can gain energy from a strong laser beam propagating collinearly. The same mechanism of acceleration can work for protons and all other heavier particles. One can expect that the proton acceleration will be less effective, as it is more difficult to wiggle a heavier particle. It is indeed so, but this less efficient coupling of the proton and laser beam is partly compensated by the negligible radiative losses. These losses impose restrictions on the electron acceleration above 100 Gev. 6 references, 2 figures.

Thermal conductivities (k, k/sub eff/) have been estimated for sintered and sphere-pac Li/sub 2/O and ..gamma..-LiAlO/sub 2/ with and without neutron irradiation effects. The estimation is based on (1) data from unirradiated UO/sub 2/, Li/sub 2/O, and ..gamma..-LiAlO/sub 2/; (2) data from irradiated dielectric insulator materials; and (3) relatively simple physical models. Comparison of model predictions with limited ex- and in-reactor data found reasonable agreement, thus lending credence for their use in design applications. The impact of thermal conductivities on tritium breeding and power generation in fusion solid-breeder blankets is briefly highlighted.

This report summarizes work done at KMS Fusion, Inc. in support of the x-ray laser experimental program at Lawrence Livermore National Laboratory. It follows an earlier report of Task No. 1 of the subject purchase order. As in that report, most of the original data has been reviewed by the LLNL technical staff, with much of it transferred to LLNL for analysis. Consequently, this report does not include a detailed presentation of the data.

Underground pumped hydroelectric energy storage was conceived as a modification of surface pumped storage to eliminate dependence upon fortuitous topography, provide higher hydraulic heads, and reduce environmental concerns. A UPHS plant offers substantial savings in investment cost over coal-fired cycling plants and savings in system production costs over gas turbines. Potential location near load centers lowers transmission costs and line losses. Environmental impact is less than that for a coal-fired cycling plant. The inherent benefits include those of all pumped storage (i.e., rapid load response, emergency capacity, improvement in efficiency as pumps improve, and capacity for voltage regulation). A UPHS plant would be powered by either a coal-fired or nuclear baseload plant. The economic capacity of a UPHS plant would be in the range of 1000 to 3000 MW. This storage level is compatible with the load-leveling requirements of a greater metropolitan area with population of 1 million or more. The technical feasibility of UPHS depends upon excavation of a subterranean powerhouse cavern and reservoir caverns within a competent, impervious rock formation, and upon selection of reliable and efficient turbomachinery - pump-turbines and motor-generators - all remotely operable.

E (Experimental Physics) Division carries out basic and applied research in atomic and nuclear physics, in materials science, and in other areas related to the missions of the Laboratory. Some of the activities are cooperative efforts with other divisions of the Laboratory, and, in a few cases, with other laboratories. Many of the experiments are directly applicable to problems in weapons and energy, some have only potential applied uses, and others are in pure physics. This report presents abstracts of papers published by E (Experimental Physics) Division staff members between July 1983 and June 1984. In addition, it lists the members of the scientific staff of the division, including visitors and students, and some of the assignments of staff members on scientific committees. A brief summary of the budget is included.