One hundred MAD-1021 slapper test devices were built to fill the reimbursable order CM8-2909G-1 for W.F. Hemsing of Los Alamos Scientific Laboratory. Physical vapor deposition (PVD) techniques were successfully used to prepare the slapper foil assemblies. The 0. 381 mm square bridge foils were of aluminium 3 micrometers thick. Copper solder pads of 1.0 to 1.5 micrometer thickness were also applied using PVD techniques. A total of 120 were fabricated and submitted to the fabrication group for assembly. The 100 completed slapper units were fabricated with 0.025 mm thick Kapton flyers. Barrels for these slapper units were 0.38 mm long with a 0.42 mm diameter.

The Savannah River Laboratory (SRL) is currently involved as the focal point of an inter-laboratory effort to estimate the enviornmental effects of operating a nuclear preprocessing facility. As a part of this effort SRL has assumed the responsibility of providing estimates of population exposure resulting form radioactive discharges to the atmosphere. This responsibility does not include contributions from drinking water and food ingestion which are being estimated by Hanford Engineering Development Laboratory (HEDL) and Lawrence Livermore Laboratory (LLL), two of the participating laboratories for the overall environmental effects study. The SRL effort in exposure estimation is confined to contributions resulting from immersion in contaminated air and external beta and gamma dose from exposure to contaminated ground. Population exposure resulting from immersion in contaminated air traditionally have been given more attention. A primary objective of this report is to develop a technique to provide an adequate estimation of population dose resulting from gound depositions and to establish the relative importance of the contributing factors. This report was written in 1978, and has been identified as information for the Dose Reconstruction Project.

Three alternatives to decommission the Heavy Water Components Test Reactor (HWCTR) have been analyzed as summarized in Table 1. The protective confinement approach is advantageous as long as current activities onsite limit access by the general public; excellent confinement of the residual activity is provided by in situ dry storage as the radiation from {sup 60}Co diminishes. Entombment provides the most-secure confinement of the activity but at some increased cost. Dismantling HWCTR has no apparent advantages other than a demonstration at the Savannah River Plant site, because of the long-term commitment to safeguarding radioactive material; the relative cost is high. The induced radioactivity in HWCTR is current 2.3 {times} 10{sup 4} Ci; general area radiation levels are typically 3 mR/hr. In 35 years, the decay of {sup 60}Co will lower the radiation levels by a factor of 100, and the remaining radioactivity will be 2 {times} 10{sup 3} Ci of {sup 63}Ni. Minimal offsite effects are calculated to result after postulated structural failures to the decommissioned HWCTR facility. Flexibility and aesthetics favor dismantlement, but these criteria are considered less significant than public radiation dose, cost, and land area committed.

A safety survey covering the disciplines of Reactor Safety, Nuclear Criticality Safety, Health Protection and Industrial Safety and Fire Protection was conducted at the ANL-West EBR-II FEF Complex during the period January 10-18, 1972. In addition, the entire ANL-West site was surveyed for Health Protection and Industrial Safety and Fire Protection. The survey was conducted by members of the AEC Chicago Operations Office, a member of RDT-HQ and a member of the RDT-ID site office. Eighteen recommendations resulted from the survey, eleven in the area of Industrial Safety and Fire Protection, five in the area of Reactor Safety and two in the area of Nuclear Criticality Safety.

This report provides a reassessment of the Kra Canal Project as prepared in December 1972. This reassessment differs in that thirty- four salvos with a total yield of about 170 MT were assumed; acceptable firing days were selected from actual meteorological data when the winds at all levels up to the expected debris cloud top blew toward the west plus or minus thirty degrees; and the lead in the devices was assumed to be from monazite sand. The doses are considerably less than those estimated in the earlier assessment.

This correspondence provides an analysis of just why nuclear excavation experiments are necessary and important.

This report contains a reassessment of the Kra Canal Project. This latest assessment differs from the original study in that: Thirty- four salvos with a total yield of about 170 MT were assumed; `Acceptable` firing days were selected from actual meteorological data when the winds at all levels up to the expected debris cloud top blew toward the west, +/- 30 degrees; and the lead in the devices was assumed to be from monazite sand. The doses are considerably less than those estimated in the earlier report. The reasons for this are: A longer trajectory to Sumatra was assumed such that the debris clouds traveled 1600 Km before crossing the west coast of Sumatra; Residents of the Nicobar Islands and Sumatra to our knowledge do not consume milk, hence the forage-cow-milk pathway is not included; The use of lead from monazite sands reduced the total dose; Some of the latest dose conversion constants used are smaller than those in the earlier report; and the effects of precipitation scavenging were based on an improved assessment.

This document presents details of the status of irradiations performed by Fuel and Target Irradiation Technology for BNW as of December 31, 1969.

The technology and data base required to license a nuclear repository in a crystalline rock medium, located at or near the Nevada Test Site are being developed. The program consists of three related project areas: field and laboratory studies of the availability and migration of radionuclides in ground water; thermomechanical response of granite, through heater tests at the Climax stock of the Nevada Test Site; and laboratory measurements of physical properties of rocks at elevated temperatures and pressures, including physical/chemical factors that inhibit water transport in deep silicate rocks. Work accomplished in these areas is report. (LK)

The technique of microautoradiography was applied to the study of the sorption of uranium and americium on five rock types which exist at the Nevada Test Site. It was found that autoradiograms could be prepared in a few days which would allow the specific minerals responsible for sorption to be identified. Furthermore, the state of aggregation of the sorbed species was clearly indicated. It was concluded that microautoradiography was a useful adjunct to currently used methods for studying sorption of certain radionuclides.

Volume 1 contains the following papers: Solution Species of {sup 239}Pu in Oxidizing Environments; Solution Species of {sup 239}Pu in the Environment; Theoretical and Experimental Evaluation of Waste Transport in Selected Rocks; Studies of Radionuclide Availability and Migration at the Nevada Test Site Relevant to Radioactive Waste Disposal; Systematic Study of Metal Ion Sorption on Selected Geologic Media; Chromatographic K/sub d/ values of Radionuclides; Effects of Redox Potentials on Sorption of Radionuclides by Geologic Media; and Transport Properties of Nuclear Waste in Geologic Media. Individual papers were processed.

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This report describes Lawrence Livermore Laboratory (LLL) activities during FY 1978 in support of the National Waste Terminal Storage Program. Current projects at LLL fall into three categories: (1) field testing, (2) laboratory rock mechanics measurements, and (3) laboratory studies of sorption and leaching. Field test activities conducted in the Climax granite at the Nevada Test Site included electrical heater tests, preparation for a spent-fuel-storage test, and planning for a series of rock mechanics tests. The heater tests determined the in situ thermal properties of Climax granite and its in situ permeability as a function of rock temperature. The two main laboratory rock mechanics projects involved (1) measurement of the permeability, electrical conductivity, and acoustic velocity of 15-cm-diam cores of granitic rocks over a range of confining pressure, pore (water) pressure, and deviatoric stress, and (2) measurement of rock thermal properties as a function of temperature and confining pressure in the presence of pore fluids to 770{sup 0}K and 200 Mpa. The leaching studies made use of an LLL-designed, single-pass leaching apparatus with three solutions, two leach temperatures, and three flow rates. The material evaluated was Np--Pu-doped simulated waste glass from Battelle Pacific Northwest Laboratories. The sorption studies involved standard …

The SIEX computer program is a steady state heat transfer code developed to provide thermal performance calculations for a mixed-oxide fuel element in a fast neutron environment. Fuel restructuring, fuel-cladding heat conduction and fission gas release are modeled to provide assessment of the temperatures. Modeling emphasis has been placed on correlations to measurable quantities from EBR-II irradiation tests and the inclusion of these correlations in a physically based computational scheme. SIEX is completely modular in construction allowing the user options for material properties and correlated models. Required code input is limited to geometric and environmental parameters, with a ``consistant`` set of material properties and correlated models provided by the code. The development of physically based correlations to model certain of the phenomana has resulted in a computer program which provides reliable estimates of thermal performance characteristics, yet requires a small amount of core storage and computer running time.

This report presents details of the activities of Douglas United Nuclear at the Hanford site during the month of December 1969.

This quarterly report describes applied technology studies directed toward closing the back end of the commercial light water reactor (LWR) fuel cycle, particularly the appropriate disposition of spent fuel elements. Progress is reported in the following major tasks: Studies and Analyses (thorium reference fuel cycle), Fuel Reprocessing (coprocessing U and Pu, dissolution of spent thorium oxide fuel), and General Support (corrosion of high Ni--Cr alloys, XRD analysis of voloxidized LWR fuels, U determination in process solutions).

A coprocessing solvent extraction flowsheet for recovering and purifying LWR fuels has been altered to achieve partial partioning of uranium and plutonium to eliminate streams with pure plutonium. Partial partitioning has been demonstrated in the laboratory with simulated feeds and irradiated LWR fuel solutions. Hydroxylamine nitrate was the reductant in these tests. Plutonium was concentrated by factors of 6 to 27.4. Tests have shown that 1 to 2 plutonium atoms are reduced for each hydroxylamine molecule consumed. Nitrite interferes with the reduction of plutonium, unless the hydroxylamine concentration is increased. 12 tables, 11 figures.

This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of December 1970.

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This single page document is the January 9, 1970 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

The Earl Warren Legal Institute, part of the University of California at Berkeley, is a center for law-related interdisciplinary research and public service in areas of national social concern. Since 1975, we have worked with the U.S. Department of Energy and Lawrence Berkeley Laboratory on various projects addressing energy policy and environmental issues. We are now engaged in a major effort to identify current legal, economic and institutional obstacles to commercial development and use of geothermal energy sources. Geothermal resources--heat reservoirs beneath the earth's surface--have received increasing attention in recent years of growing energy consciousness, and much progress has been made toward understanding their nature, extent and uses. Encouraged by federal and state development programs, there now exists an active and growing community of geologists, geophysicists, engineers, drilling companies, developers and end-users of geothermal heat. However, Department of Energy studies indicate that current knowledge and available technology would support substantially broader use of the resource, particularly by private sector commercial, industrial and agricultural concerns. Accordingly, we are now seeking to determine the knowledge and attitudes of such entities toward geothermal use; the factors which will influence decisions to utilize geothermal or not; the perceived obstacles, if any, to expanded use …

Describes the status of a process that manufactures explosives downhole for injecting into formations. Shows results for oil and gas tests, where flow improvements ranged from 160% to 1300%. At this stage, the project consisted of laboratory tests of a number of explosives for possible use in geothermal dry steam or liquid dominated wells. Report has many pictures and tables. (DJE 2005)

Fault tree techniques have been used to identify possible failure paths within the NPTR which could lead to core disassembly. The analysis o f the various faults has led to formulation of design requirements, protective system requirements, and administrative restraints required to prevent accidents from these faults. Transient analyses were performed using the heat transfer-nuclear kinetics codes, Nutiger-II, FORE-II, and MELT-II . To verify results, intercomparison studies were made between the codes. The codes were i n good general agreement. Each code was found to exhibit different advantages and disadvantage. Inherent reactivity feedback effects were assessed in the analysis. With the assumed core parameters, there appears to be sufficient Doppler to prolong a nuclear transient to allow protective action to prevent fuel from melting. The use of average values of the feedback coefficients smeared over the entire core does not appear to be an acceptable method with spacially dependent temperatures. In the thermal analysis, the fuel pin gap coefficient and sodium film coefficient do not appear to be highly sensitive parameters for transient analysis. Power transients resulting from reactivity insertions of from 2$/sec to 20$/sec have been examined in detail. Sodium will be molten before fuel melting occurs for accidents …