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The work plan for removal and burial of fabrication equipment used for the fabrication of plutonium weapon components from 1949 to 1965 is outlined. (JSR)

Studies are described which were performed for the Near Term Hybrid Vehicle program to determine passenger car usage patterns and to correlate these trip mission characteristics with vehicle design and performance specifications. (LCL)

This report has been prepared in nine sections plus appendices, separated into five separate volumes. This volume contains three sections. Separate abstracts were prepared for each section. (MHR)

The /sup 45/Sc nuclear magnetic resonance was studied in samples having the general composition CsSc/sub x/Cl/sub 3/ (0.67 less than or equal to x less than or equal to 1.0) in the CsCl-ScCl/sub 3/-Sc system. In particular the structure of CsScCl/sub 3/ suggests that it may be a one-dimensional conductor, and an attempt was therefore made to detect the occurrence of a metal-insulator transition of the type characteristic of one-dimensional conductors. Conventional crossed-coil (nuclear induction) techniques were employed. The /sup 45/Sc resonance was studied over a wide frequency range (4 to 24 MHz) at 300K, these measurements yielding the Knight shift and nuclear electric quadrupole coupling parameters. No significant variation in the spectra occurred from 4.2K to 450K, indicating the absence of a metal-insulator transition in this temperature range.

A bibliography of 198 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1977 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are arranged first by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

This paper describes a new technique for directly measuring the safety factor, or q, profile in a tokamak. A tightly collimated neutral beam capable of injecting approximately 100 mA of 30 keV deuterium atoms was mounted on the ATC tokamak. By proper tangential aiming of the beam a strong concentration of circulating fast ions was created at a chosen plasma minor radius. By examining the orbits of these ions with a multi-sight-line charge exchange detector, it was possible to measure the shifts of the orbits off of magnetic surfaces, and thereby to make local measurements of q. This experiment showed that when q on axis reached unity, strong internal turbulence began, and further lowering of q at the outer edge of the plasma did not lower q(0). A second result was that the measured q(0) was approximately 1.8 times larger than the q(0) deduced from the T/sub e/(r) profile, assuming z/sub eff/ to be independent of minor radius. This suggests a significant peaking of z/sub eff/ on axis in ATC.

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The exposure of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a beta dose of 10 ..mu..Ci/cm/sup 3/ and a gamma dose of 10/sup -5/ ..mu..Ci/cm/sup 3/ did not show any conclusive evidence of membrane degradation. Viscosity measurements for control membranes and irradiated membranes indicate no changes in polymer molecular weight were caused by the radiation exposure. This, in turn, suggests no physical or mechanical degradation took place. A continuous run on the ultrafiltration pilot plant was completed. The run lasted 33.5 hr; during this period, the flux declined from 4 gal/min to 0.8 gal/min while rejection of alpha activity increased slightly. A total of 20,000 gal were processed through the ultrafiltration system. The small laboratory column tests were continued with uranium-233 and americium-241. Several new resins were being evaluated along with the same type of resin as used before with uranium-233 and plutonium-238. Tests were continued with the 2-in. Engineering Columns using ultrafiltration product spiked with uranium-233.

The Oak Ridge Imaging System (ORIS) is a general purpose access, storage, processing and display system for nuclear medicine imaging with rectilinear scanner and gamma camera. This volume contains listings of the PDP-8/E version of ORIS Version 2. The system is designed to run under the Digital Equipment Corporation's OS/8 monitor in 16K or more words of core. System and image file mass storage is on RK8E disk; longer-time image file storage is provided on DECtape. Another version of this program exists for use with the RF08 disk, and a more limited version is for DECtape only. This latter version is intended for non-medical imaging.

A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the ERDA Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

Comparisons in temperature increases incurred from hypothetical storage of 133 MW of 10-year-old spent fuel (SF) or high-level waste (HLW) in underground salt formations have been made using the HEATING5 computer code. The comparisons are based on far-field homogenized models that cover areas of 65 and 25 sq miles for SF and HLW, respectively, and near-field unit-cell models covering respective areas of 610 ft/sup 2/ and 400 ft/sup 2/. Preliminary comparisons based on heat loads of 150 kW/acre and 3.5 kW/canister indicated near-field temperature increases about 20% higher for the storage of the spent fuel than for the high-level waste. In these comparisons, it was also found that the thermal energy deposited in the salt after 500 years is about twice the energy deposited by the high-level waste. The thermal load in a repository containing 10-year-old spent fuel was thus limited to 60 kW/acre to obtain comparable far-field thermal effects as obtained in a repository containing 10-year-old high-level waste loaded at 150 kW/acre. Detailed far-field and unit-cell comparisons of transient temperature increases have been made based on these loadings. Unit-cell comparisons were made between a canister containing high-level waste with an initial heat production rate of 2.1 kW and a …

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Results are presented of acceptance tests conducted on the Alternator Stator, S/N 002, for the Kilowatt Isotope Power System. These results show that the Alternator Stator, S/N 002 for the Kilowatt Isotope Power System has satisfactorily completed the testing set forth within Sundstrand Test Specification 2538. Test requirements of TS 2538 were extracted from the Kilowatt Isotope Power System, and Phase I Test Plan.

This test procedure provides a detailed description of the verification methods which shall be used in the developmental program to be conducted on the Kilowatt Isotope Power System (KIPS) Radiator Bypass Valve, to fulfill the requirements of the Ground Demonstration System Design Criteria. The test objective is to demonstrate the bypass flow characteristics of the valve as a function of the Jet Condensor Inlet Temperature. To accomplish the test objective the pump discharge temperature (TPO) will be varied by adjusting the temperature control (T/C) on the rig heaters. Heat will be rejected by adjusting the cooling rate through the heat exchanger. As the Jet Condenser inlet temperature changes, the bypass flow rate and the radiator flow rate will change.

Specific applications in which lead--acid batteries might be economically competitive on an electric utility system are identified. Particular attention is given to searching the Public Service Electric and Gas Company (PSE and G) system for installations of batteries which could defer or cancel costly transmission and/or distribution projects. Although the transmission and distribution data are based on specific applications on the PSE and G system, the generation data are based on a national reference system. The report analyzes and summarizes all costs and savings attributable to lead--acid batteries. 40 figures, 78 tables. (RWR)

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A mathematical model describing the kinetics of continuous precipitation was developed which accounts for crystal nucleation, crystal growth, primary coagulation, and secondary coagulation. Population density distributions, average particle sizes, dominant particle sizes, and suspension density fractions of the crystallites, primary agglomerates, and secondary agglomerates leaving the continuous precipitator can be determined. This kinetic model was applied to the continuous precipitation of ammonium polyuranate, which consists of: (1) elementary crystals, (2) clusters or primary coagulated particles, and (3) agglomerates or secondary coagulated particles. The crystallites are thin, submicron, hexagonal platelets. The clusters had an upper size limit of about 7 ..mu.. in diameter and contained numerous small voids (less than 0.3 ..mu..m) due to the packing of the crystallites. The agglomerates had an upper size limit of about 40 ..mu..m in diameter and contained large voids (approximately 1 ..mu..m). The particle size distribution and particle structure of the ammonium polyuranate precipitate can be controlled through proper regulation of the precipitation conditions. The ratio of clusters to agglomerates can be best controlled through the uranium concentration, and the cohesiveness or internal bonding strength of the particles can be controlled with the ammonium to uranium reacting feed mole ratio. These two conditions, in …

This manual of field procedures is prepared to aid personnel involved in the field sampling of natural waters and waterborne sediment for the Los Alamos Scientific Laboratory (LASL) as part of the US Department of Energy (DOE) Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the National Uranium Resource Evaluation (NURE) program. It presents the procedural guidelines to be followed by all contractors, contractor employees, and others who collect, treat, or otherwise handle samples taken for the LASL as part of the HSSR program. Part I relates to all sampling in the conterminous states of the US for which the LASL is responsible to the DOE for carrying out the HSSR work. Part II describes procedures to be followed for HSSR work, using helicopter support, in the state of Alaska. The objective of the manual is to insure that consistent techniques are used throughout the survey. If any procedure is unclear or cannot be followed, telephone collect to Group G-5, LASL, (505) 667-7590, for further instructions. No variations in the specific procedures should be made without prior approval of the LASL.

A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

An analytical evaluation of the Oak Ridge National Laboratory Shipping Cask D-38 (solids shipments) was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.