The parameter B/sub e//nr/sub p/ (here, B/sub e/ is applied magnetic field strength, nr/sub p/ is the plasma density-radius product) is proposed as a key parameter for spheromak heating studies. If B/sub e//nr/sub p/ is too large, increased magnetic fluctuations limit heating; low B/sub e//nr/sub p/ value results in excessive radiation losses. An optimum range appears to be B/sub e//nr/sub p/ approx. 1 to 5 x 10/sup -20/ Wb.

This report presents the results of a survey to determine the availability of screw feeders for use in areas related to coal feeding in the field of coal conversion. 15 references.

This report discusses the inservice leak testing of primary pressure isolation valves in commercial power reactors which was investigated to identify problems with current test procedures and requirements. Nine utilities were surveyed to gather information which is presented in this report. An analysis of the survey information was performed, resulting in recommended changes to improve valve leak testing requirements currently invoked by Section XI of the ASME Boiler and Pressure Vessel Code, Plant Technical Specifications, and Regulatory Guides addressing this subject.

Magnetotelluric (MT) measurements in southwestern Utah have yielded a model of resistivity structure in this area to a depth of about 100 km. The MT observations are strongly affected by Great Basin graben sedimentary fill, which constitutes conductive upper-crustal lateral inhomogeneity and requires simulation using two- and three-dimensional modeling algorithms before deeper portions of the resistivity section can be resolved. Included in the model is a layer of low resistivity (20 ..cap omega..-m) residing from 35 to 65 km depth. Sensitivity tests of the data to the structure weigh strongly against the top of this layer being as shallow as 25 km and against the conductivity and thickness of the layer being highly correlated. No intra-crustal low-resistivity layer is indicated by the MT data.

A method is reported here for the analysis of I-129 in decontaminated defense waste salt solution at concentrations as low as 0.14 pCi/ml. Repeated analyses have been unable to confirm the presence of I-129 in decontaminated samples of Tank 24 supernate.

This report discusses the inservice leak testing of primary pressure isolation valves in commercial power reactors which was investigated to identify problems with current test procedures and requirements. Nine utilities were surveyed to gather information which is presented in this report. An analysis of the survey information was performed, resulting in recommended changes to improve valve leak testing requirements currently invoked by Section XI of the ASME Boiler and Pressure Vessel Code, Plant Technical Specifications, and Regulatory Guides addressing this subject.

Since the Atmospheric Test Ban Treaty was signed in 1963, the United States has conducted all nuclear weapons tests underground. To meet US treaty responsibilities and to ensure public safety, the containment community must prevent any release of radioactive gases to the atmosphere. In the past two decades we have gained considerable insight into the scientific and engineering requirements for complete containment, but the papers and discussions at the Monterey Symposium indicate that a great deal remains to be done. Among papers included here, those dealing with mature topics will serve as reviews and introductions for new workers in the field. Others, representing first looks at new areas, contain more speculative material. Active research topics include propagation of stress waves in rocks, formation and decay of residual hoop stresses around a cavity, hydrofracture out of a cavity, formation of chimneys, and geologic and geophysical investigations of the Nevada Test Site. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

With the improved understanding of plasma physics, progress is being made on several approaches to magnetic confinement for controlled thermonuclear fusion.

The iterative method of evaluating plasma equilibria is especially simple in a magnetic coordinate representation. This method is particularly useful for clarifying the subtle constraints of three-dimensional equilibria and studying magnetic surface breakup at high plasma beta.

Novette has been designed to deliver 18.0 kJ in 1 nsec and 28 kJ in 3 nsec as maximum damage limited drive to the frequency conversion arrays. We expect maximum frequency doubled on-target energies of 13 kJ in 1 nsec and 20 kJ in 3 nsec. Propagation studies performed as Novette has been activated will be reviewed and their bearing on the Nova laser design discussed. The characteristics of the incident laser radiation in the target chamber center will be described.

Ground samples of three nuclear melt glasses from underground nuclear explosions at the Nevada Test Site (NTS) were leached at 25/sup 0/C with natural ground water from NTS. Using our dynamic single-pass flow-through leaching system we monitored the release of radionuclides from the glasses during 420 days of leaching. We continually flowed the ground water over the melt glass at flow rates of 185 ml/day for half of the samples and 34 ml/day for the rest. Leachate solutions were collected continuously, and composite samples, collected on days 1, 2, 3, 6, 11, 32, 38, 70, 120, 230 and 420, were analyzed using low-background Ge(Li) gamma spectrometers. For most of the radionuclides the leach rate decreased smoothly throughout the experiment. Except for /sup 95/Zr, /sup 144/Ce, and /sup 155/Eu, there was no difference between the fast (185 ml/day) and slow (34 ml/day) flow-rate leach rates. The measurable leach rates ranged from a high of 1 x 10/sup -2/ g-glass/m/sup 2/ day for /sup 22/Na (slow flow-rate, day 1 in glass No. 2) to a low of 1 x 6/sup -6/ g-glass/m/sup 2/ day for /sup 54/Mn (slow flow-rate, day 420 in glass No. 2). Most of the leach-rate values were about …

Steady currents up to 165 kA for 3.5 seconds and 420 kA for 0.3 seconds have been maintained by 800 MHz lower hybrid waves. For line-averaged densities up to 7 x 10/sup 12/ cm/sup -3/ the current is maintained with no input power from the ohmic heating transformer. The waves are launched with an array of six waveguides. Measurements of X rays and electron cyclotron radiation show that the rf power produces and maintains a suprathermal tail of electrons apparently independent of the number of fast electrons in the plasma prior to turning on the rf power. Measurements of current-drive efficiency and the electron tail provide direct evidence for a resonant wave-particle interaction. The radial profile of the rf-sustained current inferred from x-ray measurements is peaked in the center of the plasma and appears to obey the same q-value restraints as the inductively driven ohmic heating current. Current drive is observed to be accompanied always by radiation at frequencies greater than or equal to ..omega../sub ce/ and less than or equal to ..omega../sub pe/. The connection between this radiation and the current-drive mechanism is under study.

Biomedical and health effects research conducted at PNL in 1982 on the evaluation of risk to man from existing and/or developing energy-related technologies are described. Most of the studies described in this report relate to activities for three major energy technologies: nuclear fuel cycle; fossil fuel cycle (oil, gas, and coal process technologies, mining, and utilization; synfuel development), and fudion (biomagnetic effects). The report is organized under these technologies. In addition, research reports are included on the application of nuclear energy to biomedical problems. Individual projects are indexed separately.

The biomass with which this report is concerned includes aquatic plants, which can be converted into liquid fuels and chemicals; organic wastes (crop residues as well as animal and municipal wastes), from which biogas can be produced via anerobic digestion; and organic or inorganic waste streams, from which hydrogen can be produced by photobiological processes. The Biomass Program Office supports research in three areas which, although distinct, all use living organisms to create the desired products. The Aquatic Species Program (ASP) supports research on organisms that are themselves processed into the final products, while the Anaerobic Digestion (ADP) and Photo/Biological Hydrogen Program (P/BHP) deals with organisms that transform waste streams into energy products. The P/BHP is also investigating systems using water as a feedstock and cell-free systems which do not utilize living organisms. This report summarizes the progress and research accomplishments of the SERI Biomass Program during FY 1982.

Coflexip (France) flexible drilling pipe can provide economies in drilling geothermal wells. However, the current liner materials cannot take the high temperatures (approx.250C) and pressures (approx.69 MPa). Development was undertaken to replace the liner with higher temperature materials and, thus increase the temperature capability of the flexible pipe. DuPont Teflon PFA 350, L'Garde EPDM Y267 and L'Garde AFLAS 291 were considered but they all require backing by a closely woven stainless steel fabric to prevent extrusion. A graphite-reinforced EPDM elastomer was developed which has the potential of meeting the pressure-temperature requirements without the metal fabric reinforcement.

Geothermal well operators have expressed concern over the vulnerability of unsupported casing to buckling from thermal elongation. Preliminary numerical and theoretical calculations are presented, which indicate the buckling phenomenon should not be serious in N-80 casing if the string is tension preloaded. Buckling would be detrimental for K-55 casing. The effect of wall contact was found to be beneficial for closely confined pipe strings and of no detriment when hole gaps are large. The weakness of API screw joints in bending appears to be the structural limitation. The analysis assumed stresses above yield constituted failure, that thermal expansion was strain controlled, and that the casing was continuous. Excessive internal pressure instability was ignored. The temperature variation considered was between cementing conditions of 100 to 200/sup 0/F (40 to 95/sup 0/C) and shut-in conditions of 425 to 450/sup 0/F (220 to 230/sup 0/C).

The project description, required research project personnel, an annotated list of reports, and problems and recommendations are included. (MHR)

A drift collection calorimeter having a combined radiator and field-shaping structure made of lead-glass tubing is described. A high-resistance metallic layer is formed by reduction of the lead oxide at the surface of the glass and forms a continuous voltage divider for drift-field shaping. The energy resolution of such a calorimeter is modeled, for several configurations, by the Monte Carlo technique.

On March 28, 1979, an accident occurred at the Three Mile Island nuclear power plant Unit No. 2 near Middletown, PA. A Presidential Commission was established to investigate the incident and was given the responsibility to evaluate the actual and potential impact of the events on the health and safety of the workers and the public. A main conclusion of the investigation was that the most serious health effect was severe, short-lived mental stress. This paper describes the study and the findings for four different study groups: (1) the general population of heads of households located within 20 miles of the plant; (2) mothers of preschool children from the same area; (3) teenagers in the 7th, 9th, and 11th grades from the area; and (4) nuclear workers employed at the Three Mile Island nuclear power plant. (ACR)

This report is an addendum to the MORSE report, ORNL-4972, originally published in 1975. This addendum contains descriptions of several modifications to the MORSE Monte Carlo Code, replacement pages containing corrections, Part II of the report which was previously unpublished, and a new Table of Contents. The modifications include a Klein Nishina estimator for gamma rays. Use of such an estimator required changing the cross section routines to process pair production and Compton scattering cross sections directly from ENDF tapes and writing a new version of subroutine RELCOL. Another modification is the use of free form input for the SAMBO analysis data. This required changing subroutines SCORIN and adding new subroutine RFRE. References are updated, and errors in the original report have been corrected. (WHK)

An ion-cyclotron range of frequencies (ICRF) heating system has been installed in the Tandem Mirror Experiment-Upgrade (TMX-U) central cell. Our initial objective is to heat low density ions in the near field of the antenna. This heating reduces the collisionality of central cell ions, which decreases the filling rate of the thermal barrier by passing ions from the central cell. From power- and particle-balance calculations, we determined that 60 kW of absorbed power is sufficient to heat plasma densities of up to 2 x 10/sup 12/ cm/sup -3/. These power requirements are consistent with ion heating results from the Phaedrus tandem mirror. Based on this, we have installed a 200-kW oscillator/power amplifier, tunable to as low as 1.5 MHz. It drives a 110/sup 0/, 9 1/2-turn loop antenna that has a commercially built Faraday shield and matching network. The system has been tuned with plasma and is being used for the initial heating studies at the ion-cyclotron frequency ..omega../sub ci/.

Coupled electron-photon transport calculations have been carried out to simulate the photon generation when a 5- or 50-MeV electron beam strikes a solid or gas target. Results indicate that a 5-MeV beam striking targets of tungsten wire, air, or air doped with Kr or Xe generates a photon spectrum sharply peaked in the forward direction and with approximately 1/E spectral intensity. At right angles to the beam the photon intensity is predominantly due to characteristic K x-rays. A 50-MeV beam striking the same targets generates substantially higher photon yield in the forward direction, but the yield normal to the beam is similar to that due to the 5-MeV beam. However, positron-electron annihilation radiation constitutes a significant part of the photon radiation normal to the beam, and is more intense than characteristic K x-rays when the target is more than about one-third of the electron range.

Part 5 of the 1982 Annual Report to the Department of Energy's Office of Environmental Protection, Safety and Emergency Preparedness presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Programs, Office of Operational Safety, and the Office of Nuclear Safety. The report is in three sections, introduced by blue divider pages, corresponding to the program elements: Technology Impacts, Environmental and Safety Engineering, Operational and Environmental Safety. In each section, articles describe progress made during FY 1982 on individual projects, as identified by the Field Task Proposal/Agreement. Authors of these articles represent a broad spectrum of capabilities derived from various segments of the Laboratory, reflecting the interdisciplinary nature of the work.

The equipment and methods used to recover and purify 339 g of thorium-230 and 890 mg of protactinium-231 from 22 of the 1251 drums of Cotter Concentrate are described. The process developed was (1) dissolution at 100/sup 0/C in concentrated nitric acid and dilution to 2 to 3 molar acid, (2) filtration to remove undissolved solids (mostly silica filter aid), (3) extraction of uranium with di-sec-butyl-phenyl phophonate (DSBPP) in carbon tetrachloride, (4) extraction of both thorium and protactinium with tri-n-octylphosphine oxide (TOPO) in carbon tetrachloride followed by selective stripping of the thorium with dilute of sulfuric acid, (5) thorium purification using oxalic acid, (6) stripping protactinium from the TOPO with oxalic acid, and (7) protactinium purification through a sequence of steps. The development of the separation procedures, the design of the pilot plant, and the operating procedures are described in detail. Analytical procedures are given in an appendix. 8 figures, 4 tables.