Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, April 1--June 30, 1978 (open access)

Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, April 1--June 30, 1978

The objectives of the program are to evaluate candidate alloys for Very High Temperature Reactor Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (Helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in the report includes the activities associated with the procurement of the materials for the screening test program, information from vendor certification for the materials receiver, and preliminary information from the materials characterization tests performed by General Electric. The construction status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment are discussed. The status of the data management system is also reviewed.
Date: August 31, 1978
Creator: unknown
System: The UNT Digital Library
Basalt Waste Isolation Program: monthly report (open access)

Basalt Waste Isolation Program: monthly report

A feasibility study is being conducted on utilizing basalt formations for terminal storage of commercial nuclear waste. Work is reported in the following projects: site studies, drilling, technology development, near-surface test facility, and repository. (DLC)
Date: August 31, 1978
Creator: Deju, R.A.
System: The UNT Digital Library
LOFT downcomer instrumentation assembly analysis (open access)

LOFT downcomer instrumentation assembly analysis

A supplemental stress analysis of the LOFT Downcomer Instrumentation Assembly (DIA) has been completed in accordance with the stress requirements of Section III of the ASME Code. Both thermal loads, due to LOCE and operating conditions, and fluid loads were considered. The following conclusions were made: (1) Inconel 600 is an acceptable material for the pressure tubes. (2) The flowmeter can be attached to the DIA with /sup 1///sub 4/-inch diameter, SA-193 type B8M screws. They should be lubricated with two coats of Neolube and torqued to 1.25 ft-lbs. This applies to all of the screws attaching the flowmeter to the DIA. As an alterative, SA-453, grade 600 screws may be used. They should be coated with 2 coats of Neolube and torqued to 4.9 ft-lbs (4.5 ft-lbs is acceptable). (3) The method of mounting the instrument leads and the pressure tubes is adequate.
Date: August 31, 1978
Creator: Beers, R.J. Jr.
System: The UNT Digital Library
LOFT emergency core coolant facility piping review (open access)

LOFT emergency core coolant facility piping review

The purpose of the review was to examine all remaining lines of the LOFT emergency core coolant facility piping outside of containment and with a diameter of less than two inches, not analyzed by ITT Grinnell Corporation. Because of a discrepancy on the Grinnell analysis, lines 3''-ECCV-10-A, 2''-ECCV-10-A and 2''-ECCV-11-A were included in this review. In addition, some lines from other systems which connected to the ECC piping were also examined, as listed on the isometric sketches in this report. An on-site ''walk-through'' was made first to verify existing restraint and valve locations. Very short stub lines were eliminated by inspection. All remaining lines, together with the lines analyzed by Grinnell and lines being currently analyzed by R. M. Fors of the Applied Mechanics Branch constitute a complete analysis of the ECC facility piping as now listed in LOFT Specification P-1, Line Designation Tables.
Date: August 31, 1978
Creator: McKay, T. K. & Fors, R. M.
System: The UNT Digital Library
LOFT pump speed controller stability and accuracy analysis (open access)

LOFT pump speed controller stability and accuracy analysis

Two system modifications to the primary coolant pumps motor generators control systems have recently been completed. The range of pump speed operation has been extended and the scoop tube positioner motor replaced. This has necessitated a re-analysis of PSMG stability throughout its range of operation. System accuracy requirements of less than 4 Hz differential pump speed when operating at less than 35 Hz and 8.5 Hz differential pump speed when operating at greater than 35 Hz can be guaranteed by specifying the gain of the system. The installation of the new scoop tube positioner motor will increase the PSMG system's bandwidth and stability. Low speed pump trips should be carefully evaluated if the pump's operational range is to extend to 10 Hz.
Date: August 31, 1978
Creator: Good, R.R.
System: The UNT Digital Library
Morning light cleanup and recovery operation: simulation studies of possible reactor fuels. [Cosmos 954 orbiting Russian reactor with U-10 wt% Mo fuel] (open access)

Morning light cleanup and recovery operation: simulation studies of possible reactor fuels. [Cosmos 954 orbiting Russian reactor with U-10 wt% Mo fuel]

The nuclear fuel for Cosmos 954, the orbiting Russian reactor that broke up on reentry during January of 1978, has been identified as a U--Mo alloy containing about 10 wt% molybdenum. Identification was based on a combination of simulation studies at LLL, examination of fuel debris at Whiteshell Nuclear Research Establishment (WNRE), Pinawa, Manitoba, and reactor technology knowledge. In the LLL simulation studies, mixtures of uranium, molybdenum, and UO/sub 2/ were heated under conditions that simulated reentry and then examined by scanning electron microscopy, energy dispersive spectrometry, and x-ray diffraction. These studies indicated metallic behavior and suggested a U--Mo alloy. The identification was useful in assisting the Canadians in recovery, cleanup, and health/safety activities associated with the radioactive debris, which was scattered over a wide region of the Great Slave Lake.
Date: August 31, 1978
Creator: Landingham, R. L. & Casey, A. W.
System: The UNT Digital Library
Reaction studies of hot silicon and germanium radicals. Period covered: September 1, 1977--August 31, 1978 (open access)

Reaction studies of hot silicon and germanium radicals. Period covered: September 1, 1977--August 31, 1978

The experimental approach to attaining the goals of this research program is briefly outlined and the progress made in the last year is reviewed in sections entitled: primary steps in the reaction of recoiling silicon and germanium atoms and the identification of reactive intermediates; thermally induced silylene and germylene reactions; the role of ionic reactions in the chemistry of recoiling silicon atoms and other ion-molecule reactions studies; and silicon free radical chemistry.
Date: August 31, 1978
Creator: Gaspar, P.P.
System: The UNT Digital Library
Stress analysis of loft (ECC) system; left side (open access)

Stress analysis of loft (ECC) system; left side

An analysis has been performed by the Applied Mechanics Branch on a new Left Side configuration of the LOFT Emergency Core Coolant (ECC) System. This system has been geometrically modified from that analyzed in a previous report, LTR 113-40. LOCE and Safe Shutdown Earthquake (SSE) were the only loading conditions considered capable of producing high stresses. Review of the analyses indicates that the new configuration passes the requirements of the ASME Code for Class 1 and 2 piping.
Date: August 31, 1978
Creator: Kido, C.
System: The UNT Digital Library
Stress analysis of LOFT Emergency Core Coolant System modification (left and right side) (open access)

Stress analysis of LOFT Emergency Core Coolant System modification (left and right side)

A stress analysis has been performed on proposed modifications to the Emergency Core Coolant System right and left side. For the right side thermal expansion and seismic loads were considered. Results of a previous report using dead weight, design LOCE, and LOCA loads were treated as valid and not repeated here. For the left side LOCE loading only was considered. The results of a previous analysis using dead weight, thermal, and LOCE loads were treated as valid and again not repeated here. Review of the analysis indicated that both proposed modifications pass the requirements of the ASME Boiler and Pressure Vessel Code Section III for Class 1 and 2 piping.
Date: August 31, 1978
Creator: Kido, C.
System: The UNT Digital Library
Technology Development Needs for High Temperature Process Heat. (open access)

Technology Development Needs for High Temperature Process Heat.

None
Date: August 31, 1978
Creator: Copeland, R. J.
System: The UNT Digital Library
Thermal-emission mass spectrometer for rapid and accurate determination of uranium isotopes (open access)

Thermal-emission mass spectrometer for rapid and accurate determination of uranium isotopes

A 60-degree (..pi../3-radian) magnetic-sector, 6-inch (152.4-mm) mass spectrometer has been designed and built for uranium isotopic analyses. The instrument uses a Nier-type geometry and has several improvements, both optically and electrically, which make it rapid and precise. Instrument control is good and the analytical results for uranium isotopes are excellent.
Date: August 31, 1978
Creator: McBryde, W. T.; Rogers, E. R. & Ferguson, J. R.
System: The UNT Digital Library
Western Gas Sands Project Status Report (open access)

Western Gas Sands Project Status Report

This edition of the WGSP Status Report summarizes the progress during July, 1978, of the government-sponsored projects directed toward increasing gas production from the low-permeability gas sands of the western United States. Background information is provided in the September 1977 Status Report, NVO/0655-100. On-site personnel were provided by CER Corporation to assist in coring and logging the Joseph J.C. Paine well located in Valley County, Montana. The information gathered was the first for the WGSP Coring and Logging Programs. The DOE test trailer was moved to Grand Junction, Colorado and then to the MHF 3 well site for trial runs and checkout of the test equipment. The USGS continued work on characterization and assessment of the resource in the four primary study areas. The National Laboratories and Technology Centers are continuing activities toward the development of mathematical modeling, new tools and instrumentation systems, data analysis and rock mechanics. Field tests and demonstrations in the WGSP continued. Mitchell Energy Corporation had reached 9,160 ft in their Muse-Duke well No. 1, and Mobil Research and Development Corporation fractured zones 6 and 7 (8,443--8,650 ft and 8,173--8,372 ft) in the PCU 31-13 well.
Date: August 31, 1978
Creator: unknown
System: The UNT Digital Library