This report reviews the activities and operations of the Advanced Computing Research Facility (ACRF) for the period January 1, 1989, through January 31, 1990. The ACRF is operated by the Mathematics and Computer Science Division at Argonne National Laboratory. The facility's principal objective is to foster research in parallel computing. Toward this objective, the ACRF continues to operate experimental advanced computers and to sponsor new technology transfer efforts and new research projects.

Highlights of the Chemical Technology (CMT) Division's activities during 1989 are presented. In this period, CMT conducted research and development in the following areas: (1) electrochemical technology, including high-performance batteries (mainly lithium/iron sulfide and sodium/metal chloride), aqueous batteries (lead-acid and nickel/iron), and advanced fuel cells with molten carbonate and solid oxide electrolytes; (2) coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized-bed combustion; (3) method, for recovery of energy from municipal waste and techniques for treatment of hazardous organic waste; (4) nuclear technology related to a process for separating and recovering transuranic elements from nuclear waste and for producing 99Mo from low-enriched uranium targets, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor (the Integral Fast Reactor), and waste management; and (5) physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.

"The appendix contains daily and monthly tabulations of running time for each station" monitoring earthquake activity in the Western Ohio - Indiana region. (p. A1)

"This appendix contains phase arrival information for local and near-regional events which have been well recorded by the Anna Seismic Network." (p. B1)

The results of tests done using the Unsaturated Test Method are presented. These tests, done to determine the suitability of glass in a potential high-level waste repository as developed by the Nevada Nuclear Waste Storage Investigations Project, simulate conditions anticipated for the post-containment phase of the repository when only limited contact between the waste form and water is expected. The reaction of glass occurs via processes that are initiated due to glass/water vapor and glass/liquid water contact. Vapor interaction results in the initiation of an exchange process between water and the more mobile species (alkalis and boron) in the glass. The liquid reaction produces interactions similar to those seen in standard leaching tests, except due to the limited amount of water present and the presence of partially sensitized 304L stainless steel, the formation of reaction products greatly exceeds that found in MCC-1 type leach tests. The effect of sensitized stainless steel on the reaction is to enhance breakdown of the glass matrix thereby increasing the release of the transuranic elements from the glass. However, most of the plutonium and americium released is entrained by either the metal components of the test or by the reaction phases, and is not released …

This report discusses the results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1989. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared. A variety of radionuclides were measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples.

Report describing the methodology used to sample and analyze sediment at Ocean City, Maryland as part of a beach nourishment project. During the project, sediment was moved from borrow sites to construct parts of the beach area; both the borrow sites and native beach were tested.

Experimental iron-, nickel-, and cobalt-base weldment materials were exposed in TVA 20-MW and Rocketdyne atmospheric fluidized bed combustors (AFBCs) at 849 degrees C for 1261 h and 871 degrees C for 1000 h, respectively. Post-exposure analyses were conducted at Argonne National Laboratory. All specimens experienced different degrees of internal oxidation/sulfidation. Among eight filler materials, Marathon 25/35R and Haynes 188 showed the least corrosion attack, i.e., less than 0.5 mm/yr. A high nickel content in the weldment was unfavorable for corrosion resistance in the AFBC environment. Differences in the coal/bed chemistry of the TVA and Rocketdyne systems yielded different corrosion behavior in the materials. Calcium sulfate deposits on the specimens significantly affected the internal oxidation/sulfidation of the alloys. The results of this study supplement the material data base, in particular that of weldment performance, and aid in materials selection for AFBC applications.

The Experimental Boiling-Water Reactor (EBWR) was designed, built, and operated to provide experience and engineering data that would demonstrate the feasibility of the direct-cycle, boiling-water reactor and be applicable to improved, larger nuclear power stations; and was based on information obtained in the first test boiling-water reactors, the BORAX series. EBWR initially produced 20 MW(t), 5 MW(e); later modified and upgraded, as described and illustrated, it was operated at up to 100 MW(t). The facility fulfilled its primary mission - demonstrating the practicality of the direct-boiling concept - and, in fact, was the prototype of some of the first commercial plants and of reactor programs in some other countries. After successful completion of the Water-Cooled Reactor Program, EBWR was utilized in the joint Argonne-Hanford Plutonium Recycle Program to develop data for the utilization of plutonium as a fuel in light-water thermal systems. Final shutdown of the EBWR facility followed the termination of the latter program.

From introduction: This necropsy manual is a guide for students and technicians in the examination of dead phocids, specifically the Hawaiian monk seal. With this manual, the person performing the necropsy should be able to conduct a gross examination of a monk seal and collect the necessary tissues for microscopic pathology and toxicological studies. The necropsy instructions are based on the assumption that the seal's carcass is very fresh and time is not a limiting factor.

The Fixed Mask Assembly (FMA) is the first component to interact with the photon beam. Two sets of a pair of FMA channels, vertically and horizontally disposed, contain the beam rather than define it. They are subject to very large heat fluxes during containment. In current practice, the FMA channels are made of heavy, seamless copper, have rectangular cross-sections, and are cooled internally with water. Channels are set at grazing angles ranging from 1 to 6 degrees with respect to the beam, depending on the type of insertion device. APS insertion devices will impose higher heat fluxes on FMAs. Therefore, a need exists to improve the FMA engineering, keeping in the mind the current design criteria and philosophy of FMAs. Preliminary analysis of current heat transfer practice indicates that the major resistance to heat transfer is on the coolant side. Therefore, FMA cooling would benefit from enhanced heat transfer on the coolant side. With this principle in mind, an experimental program has been undertaken to explore the feasibility of using high-performance copper tube configurations which are expected to yield heat transfer coefficients, h, '' in single phase flow systems 2 to 5() times higher than equivalent plain tubes. In this …

The only effective way to raise the confidence level of a program significantly is to give a convincing proof of its correctness. But one should not first make the program and then prove its correctness, because then the requirement of providing the proof would only increase the poor programmer's burden. On the contrary: the programmer should let correctness proof and program grow hand in hand.

From abstract: The Frontier Formation of the Mancos Group in northeastern Utah and northwesternmost Colorado (proposed new rank designations; formerly known as the Frontier Sandstone Member of the Mancos Shale) consists of several facies of marine and nonmarine rocks of Late Cretaceous (Turonian) age that grade eastward into totally marine rocks in easternmost Utah and northwestern Colorado.

From abstract: The primary goal of the U.S. Geological Survey-Bureau of Indian Affairs drilling project in the Upper Jurassic Morrison Formation in McKinley County, New Mexico, was to better understand the relationship between host-rock stratigraphy and uranium mineralization. As part of this project, geochemical studies of approximately 280 samples from 8 cores and 1 outcrop were undertaken; samples from 4 of the cores show uranium enrichment. Geochemical relationships between samples of weathered outcrop, oxidized core, reduced (unmineralized) core, and ore-bearing core were contrasted by comparison of element abundances.

A report regarding geophysical investigations of the Western Ohio-Indiana Region

This report is based on the observational studies of the Hawaiian monk seal studied on Laysan Island in the Northwestern Hawaiian Islands from 28 February to 20 June and from 24 October to 13 November 1988. The data collected covers haul-out patterns, population structure, reproductive patterns, and patterns affecting survival (primarily adult male aggression toward adult female and immature seals).

The interfacial area concentration is one of the most important parameters in a thermal-hydraulic analysis of two-phase flow systems based on the two-fluid model. A theoretical foundation of the measurement method for the time averaged local interfacial area using a double sensor probe is presented. Based on this theory, the double sensor resistivity probe was employed for the measurement of local properties of two-phase flow such as the interfacial velocity, local interfacial area concentration and void fraction in vertical air-water bubbly flow. Experimental data are presented on the radial profiles of the void fraction, bubble velocity, bubble chord length and interfacial area concentration at various gas flow rates. In addition to these, some statistical information on turbulent motions of bubbles are presented. Each of the double sensors are checked against the global void measurement using a differential pressure. The result is very satisfactory. Furthermore, the area averaged void fraction, and the interfacial area concentration obtained from the double sensor probe measurement compared very well with the photographic measurements. The results show that the double sensor probe method is accurate and reliable for the local measurements of interfacial area and void fraction in bubbly two-phase flow. Results of the measurement of …

Data listing for three sample problems are provided to illustrate the use of MACCS (MELCOR [We84] Accident Consequence Code System developed by Sandia National Laboratories) referred to in the accompanying report as Problems A, B, and C.

A conference at Argonne National Laboratory for executives and technical personnel in small and medium-size manufacturing companies summarized how materials evaluation and inspection by nondestructive methods are changing and broadening. The application of these rapidly emerging techniques in maintaining and improving the quality and competitiveness of manufactured products was stressed. Individual papers have been cataloged separately.

"This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment.

From abstract: This report concerns the resource extraction potential for the Adobe Town Wilderness Study Area. There are no identified resources in the study area.

From abstract: At the request of the U.S. Bureau of Land Management, approximately 19,300 acres of the Black Mountains North Wilderness Study Area (AZ-020-009) and 23,310 acres of the Burns Spring Wilderness Study Area (AZ-020-010) were evaluated for mineral resources and mineral resource potential. In this report, the area studied is referred to, collectively or individually, as the 'wilderness study area' or simply 'the study area'; any reference to the Black Mountains North or Burns Spring Wilderness Study Areas refers only to that part of the wilderness study area for which a mineral survey was requested by the U.S. Bureau of Land Management. The study area is located in western Arizona, about 30 mi northwest of Kingman. There are no identified resources in the study area.

From abstract: This report is on an investigation of the Buffalo Hump and Sand Dunes Addition Wilderness Study Areas for the purpose determining the resource extraction potential.

From abstract: The Coal Canyon (UT-060-1000), Spruce Canyon (UT-060-100D), and Flume Canyon (UT-060-100B) Wilderness Study Areas are in the Book Cliffs in Grand County, eastern Utah. Demonstrated coal reserves totaling 22,060,800 short tons, and demonstrated subeconomic coal resources totaling 39,180,000 short tons are in the Coal Canyon Wilderness Study Area. Also, inferred subeconomic coal resources totaling 143,954,000 short tons are within the Coal Canyon Wilderness Study Area. No known deposits of industrial minerals are in any of the wilderness study areas. All three of the wilderness study areas have a high resource potential for undiscovered deposits of coal and for undiscovered oil and gas.