Recently, Late Washing (LW) and Nitric Acid (NA) flowsheets, developed respectively for the DWPF at Savannah River Technology Center SPC and CPC, were demonstrated in the one-fifth scale DWPF pilot facilities, PHEF and IDMS. Using the LW flowsheet, four runs in the PHEF produced enough PHA for two runs in the IDMS (denoted by PX4 and PX5). One of the objectives of these IDMS runs was to obtain peak hydrogen generation rates and compare them to the peak hydrogen generation rate design basis obtained from a previous IDMS run, based on the HAN and Formic Acid (HAN-FA) flowsheets.

The modeling of sodium pool fires constitutes an important ingredient in conducting LMFBR accident analysis. Such modeling capability has recently come under scrutiny at Westinghouse Hanford Company (WHC) within the context of developing CONACS, the Containment Analysis Code System. One of the efforts in the CONACS program is to model various combustion processes anticipated to occur during postulated accident paths. This effort includes the selection or modification of an existing model and development of a new model if it clearly contributes to the program purpose. As part of this effort, a new sodium pool fire model has been developed that is directed at removing some of the deficiencies in the existing models, such as SOFIRE-II and FEUNA.

Single-charge and row-charge subsurface cratering experiments were performed to learn how close-spacing enhances single-crater dimensions. Our first experimental phase established cratering curves for 60-lb charges of the chemical explosive. For the second phase, to be described in a subsequent report, the Row-cratering experiments were designed and executed. This data report contains excavated dimensions and auxiliary data for the single-charge cratering experiments. The dimensions for the row-charge experiments will be in the other report. Significant changes in the soil's water content appeared to cause a variability in the excavated dimensions. This variability clouded the interpretation and application of the cratering curves obtained.

As a result of an explosion in the Waste Treatment Facility, 242-Z Building, 200 West Area of the Hanford Reservation on August 30, 1976, the Manager of the Richland Operations Office (RL), Energy Research and Development Administration (ERDA), appointed an ERDA Committee to conduct a formal investigation and to prepare a report on their findings of this occurrence. The Committee was instructed to conduct the investigation in accordance with ERDAMC 0502, insofar as circumstances would permit, to cover and explain technical elements of the casual sequence(s) of the occurrence, and to describe management systems which should have or could have prevented the occurrence. This report is the result of the investigation and presents the conclusions of the review.

We introduce the coalescence variables, a set of three boost-invariant kinematic quantities which may be used in analyzing n-particle correlations. These variables characterize the invariant mass of an n-particle and in three directions and separate the timelike and spacelike characteristics of the source. The analytic Kolehmanien-Gyulassy model is generalized to give two, three, and four-particle correlation functions, with coherence and Coulomb corrections applied to the basic formalism. We demonstrate the relation of the coalescence variables to be radius and duration of the source, and find that for sufficiently large transverse radii, Coulomb effects can suppress the structure of the Hanbury-Brown-Twiss correlations so that no significant information on source size can be obtained. 11 refs., 10 figs.

This report documents the results of the Department of Energy's (DOE) Tiger Team Assessment of the Argonne Illinois Site (AIS) (including the DOE Chicago Operations Office, DOE Argonne Area Office, Argonne National Laboratory-East, and New Brunswick Laboratory) and Site A and Plot M, Argonne, Illinois, conducted from September 17 through October 19, 1990. The Tiger Team Assessment was conducted by a team comprised of professionals from DOE, contractors, consultants. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety, and Health (ES H) Programs at AIS. Argonne National Laboratory-East (ANL-E) is the principal tenant at AIS. ANL-E is a multiprogram laboratory operated by the University of Chicago for DOE. The mission of ANL-E is to perform basic and applied research that supports the development of energy-related technologies. There are a significant number of ES H findings and concerns identified in the report that require prompt management attention. A significant change in culture is required before ANL-E can attain consistent and verifiable compliance with statutes, regulations and DOE Orders. ES H activities are informal, fragmented, and inconsistently implemented. Communication is seriously lacking, both vertically and horizontally. Management expectations are not known or commondated …

The MFTF SNBPSS comprises a number of sources of potentially hazardous electrical energy in a small physical area. Power is handled at 80 kV dc, 80 A; 70 V dc, 4000 A; 25 V dc, 5500 A; 3 kV dc, 10 A; and 2 kV dc, 10 A. Power for these systems is furnished from two separate 480 V distribution systems and a 13.8 kV distribution system. A defense in depth approach is used; interlocks are provided in the hardware to make it difficult to gain access to an energized circuit, and the operating procedure includes precautions which would protect personnel even if no interlocks were working. The complexity of the system implies a complex operating procedure, and this potential complexity is controlled by presenting the procedure in a modular form using 37 separate checklists for specific operations. The checklists are presented in flowchart form, so contingencies can be handled at the lowest possible level without compromising safety.

The Ca II absorption lines observed in the late time optical spectra of Type I supernovae are analyzed in the context of the /sup 56/Ni model. The analysis indicates that a metal rich atmosphere of mass approx. 0.2 M/sub solar mass/ surrounds the /sup 56/Ni core. This result is consistent with properties of the atmosphere derived from spectra near maximum light.

This project originated as a result of the Strontium-90 Action Plan, a response to the abnormal release of radionuclides that occurred from White Oak Creek (WOC) during late November and early December 1985. Several notable problems became obvious during ORNL's response to this release: (1) no predetermined criteria existed for the operation of White Oak Dam (WOD) in response to spills, (2) the hydrodynamics of contaminant transport and dispersion within the WOC watershed and downstream were not adequately understood to support requests for modified reservoir releases, and (3) real-time data on streamflow, precipitation, and water quality within the watershed were not readily available in sufficient quantity and usable format. The modeling study was initiated to help address these problems. This report describes FY 87 accomplishments, including: improvements in data acquisition and evaluation; implementation and calibration of a model to forecast discharges of water and contaminants from the WOC watershed; implementation, documentation, and checking of a model to forecast concentrations of contaminants from WOC in the Clinch River; and three field studies that provide essential calibration data. Data from the field studies and user documentation of the Clinch River model are included as appendices to this report.

The relativistic multigroup diffusion equations describing superthermal electron transport in laser fusion plasmas were derived in an earlier UCRL. A successful numerical scheme based on these equations which is now being used to model laser fusion experiments is described.

Four different models of the migration process have been reviewed to determine their suitability as a working model. While there are several common factors in the models additional factors are included to account for several possible effects. The detail of each model leads to a certain degree of difficulty in applying the model to the problem at hand. One model predicts that inclusions smaller than 0.1 mm dimension probably will not migrate. The other models do not consider size as a factor. Thermal diffusion (Soret effect) is considered insignificant in three models, while in the fourth model it is added to the concentration diffusion term. The following conclusions are made: (1) Temperature is the most significant parameter in all models and must be known as a function of time, and distance from the canister. (2) All four models predict about the same migration velocity for a given set of conditions. For 100/sup 0/C and 1/sup 0/C/cm thermal gradient, the individual values are 3.0, 4.8, 5.6 and 6.4 mm/y. (3) The diffusion of ions through the brine inclusions is the rate controlling mechanism. (4) The difference between the thermal gradients in the liquid and in the solid should always be considered, …

We have taken the approach here of trying to understand both the feasibility and practicality of varied options for new rings at Fermilab, rather than trying to produce a single detailed design. In other words, this document is not a design report and should not be construed as such. Our perception of the potential needs for new rings (in order of priority) is as follows: Antiproton Storage and/or Recovery: A facility for storing up to 4 x 10/sup 12/ antiprotons is needed. Recovery of antiprotons from the collider becomes a viable option if the luminosity is indeed dominated by emittance dilution rather than beam loss. New or Post-Booster: The goal here would be to inject into the existing Main Ring above transition. Improved performance of the Main Ring would be anticipated. New Main Ring: Advantages would include better emittance preservation, a faster cycle time for antiproton production, and the removal of interference/backgrounds at the B0 and D0 detectors. We discuss in this paper various scenarios based on one or more combinations of the above possibilities. 14 figs., 10 tabs.

The inertia and friction-welding processes were evaluated for joining aluminum alloy 1100-H14 and Type 316 vacuum-induction melted, vacuum-arc remelted (VIM VAR) stainless steel. While both processes consistently produced joints in which the strength exceeded the strength of the aluminum base metal, 100 percent bonding was not reliably achieved with inertia welding. The deficiency points out the need for development of nondestructive testing techniques for this type of joint. Additionally, solid-state volume diffusion did not appear to be a satisfactory explanation for the inertia and friction-welding bonding mechanism.

Development of indirectly heated cathodes and duoplasmatron type electron feed assemblies is being pursued for use on positive ion sources of neutral beam systems. The cathodes utilize La/sub 2/O/sub 3/ doped molybdenum emission surfaces which supply ionizing electrons for a large rectangular (28 cm. x 60 cm.) magnetic multi-cusp confinement chamber. Single and double electron feed assemblies with different electrode geometries were tested at discharge currents of greater than or equal to 1000 A and pulse lengths of approx. 35 sec. Details of construction and performance results such as plasma uniformity are discussed.

The reconfiguration of MFTF to a tandem mirror machine with thermal barriers has caused a significant expansion in the physical scope of plasma diagnostics. From a mechanical perspective, it complicates the plasma access, system interfaces, growth and environmental considerations. Conceptual designs characterize the general scope of the design and fabrication which remains to be done.

This booklet discusses some ideas and methods for using Colorado geothermal energy. A project installed in Pagosa Springs, which consists of a pipeline laid down 8th street with service to residences retrofitted to geothermal space heating, is described. (ACR)

A mechanical model for the emplacement pipe system is developed. The model is then employed to determine the force applied to the surface collar of the emplacement pipe, the pipe-stemming load, and the stress along the emplacement pipe as a function of stemming height. These results are presented as integrals and a method for their numerical integration is given.

A retrofit solar water-heating system has been operating for the past two years in a three-story apartment building at Drexel University. The system employs two conventional collector banks (9 PPG collectors) mounted at the latitude angle for Philadelphia of 40 deg from the horizontal and two double-exposure collectors (DEC's) mounted vertically in mirrored enclosures. The relative performance of the conventional and double-exposure collectors has been monitored with an instrumentation system which was developed and installed in the basement of the apartment building. The DEC units have been found to provide from two to four times as much useful heat output per panel area than the PPG collectors. The higher relative performance values occur on clear winter days whereas lower relative performance values are found on clear summer days and generally overcast days. A cost analysis for a DEC unit relative to a conventional collector has also been performed. In the Philadelphia area the DEC units with their mirror enclosures would cost approximately 1.7 times as much per panel area as conventional collectors. Since the DEC units provide two to four times as much useful heat output, they are a cost-effective choice for flat or gently sloping roofs for which they …

Corrective actions had been taken in four of the six areas of concern that were addressed in the 1982 report. The remaining two areas are summarized as follows: Certification of Remedial Actions. We found, in the initial inspection, that FUSRAP properties were not being certified as decontaminated in a timely manner following remedial action. This problem has not yet been resolved. The Assistant Secretary for Nuclear Energy acknowledged that the certification process is lengthy but maintained that progress was being made. The Assistant Secretary stated that attempts will be made to speed up the process; and Permanent Waste Disposal. The lack of permanent repositories for FUSRAP wastes continues to be a major issue. The Assistant Secretary for Nuclear Energy indicated to us that meetings are being held with state and congressional representatives to impress on them the need for locating disposal sites for FUSRAP wastes in their states.

When canisters containing radwastes are emplaced in a repository the heat produced by the decaying radwaste will cause moderate thermal gradients to develop which will cause the brine present in a halite medium (salt deposits) to accumulate around the canister. Four different models of the migration process have been reviewed to determine their suitability as a working model. One model predicts that inclusions smaller than 0.1 mm dimension probably will not migrate. The other models do not consider size as a factor. Thermal diffusion (Soret effect) is considered insignificant in three models, while in the fourth model it is added to the concentration diffusion term. The following conclusions can be made: Temperature is the most significant parameter in all models and must be known as a function of time, and distance from the canister. All four models predict about the same migration velocity for it is a given set of conditions; for 100/sup 0/C and 1/sup 0/C/cm thermal gradient, it is 3.0, 4.8, 5.6 and 6.4 mm/y. Diffusion of ions through the brine inclusions is the rate controlling mechanism. The difference between the thermal gradients in the liquid and in the solid should always be considered and is a function …

Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be enclosed in a 50 cubic meter box-shaped vacuum chamber. The chamber will have a number of unorthodox features to accomodate both neutral beam and TFTR requirements. The design constraints, and the resulting chamber design, are presented.

The demonstration of ICF scientific feasibility requires success in target design, driver development and target fabrication. Since these are interrelated, we present here some results of ion beam target studies and relate them to parameters of interest to ion accelerators. Ion deposition physics have long been a well known subject apart from high beam currents. Recent NRL experiments at up to 250 kA/cm/sup 2/ ions confirm the classical deposition physics now at current densities which are comparable to most ion targets. On the other hand, GSI data at low current density but 1 to 10 MeV/nucleon are continually being accumulated. They have yet to find anomalous results. Relying on target concepts outlined briefly, we report on the energy gain of ion-driven fusion targets as a function of input energy, ion ranges and focal spot radius. We also comment on some consequences of target gain versus driver and reactor requirements.

The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facility. This is a major step to reach the goal of fusion power using toroidal magnetic fields for plasma confinement. A major part of this test reactor will be four neutral beam injection systems. These systems will inject 20 MW of 120 kV neutral deuterium atoms into the plasma for 0.5 seconds. In order to achieve the required power input to the plasma, several systems are required within the neutral beam line. These are the source, neutralizer, ion deflection magnet, calorimeter and retraction system, ion dump, cryopumps and vacuum enclosure. All of these systems have constraints imposed which increase the complexity of their designs. Since all systems must operate in a tritium environment, remote handling capabilities must be incorporated into the design. An overview is presented of the Lawrence Livermore Laboratory/Lawrence Berkeley Laboratory Neutral Beam Injection System design. Specifications for the machine and a general description of the total system are presented.

The Tandem Mirror Experiment (TMX) is designed to test the physics of a new approach to Q-enhancement in open confinement systems. In the tandem mirror concept, the ends of a long solenoid are plugged electrostatically by means of ambipolar potential barriers created in two mirror machines or plugs, one at each end of the solenoid. The ambipolar potential in mirror machines develops as a consequence of the higher scattering rate of electrons and the balancing of electron and ion loss rates. The TMX experiment incorporates very few new engineering developments, but it does involve a new way of combining in an integrated system many previously developed ideas. The engineering task is to design the machine that would provide a proof-of-principle evaluation of the tandem mirror concept as rapidly as possible. The preliminary design was started in September 1976 and was completed by December 1976. It led to a cost estimate of $11 million and a scheduled construction period of 18 months.