Material control system simulator user's manual (open access)

Material control system simulator user's manual

This report describes the use of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts.
Date: January 24, 1978
Creator: Hollstien, R.B.
Object Type: Report
System: The UNT Digital Library
Material control system simulator program reference manual (open access)

Material control system simulator program reference manual

A description is presented of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts. Although MCSS may be used independently in the design or analysis of material handling and processing systems, it has been tailored toward the determination of material accountability and the response of material control systems to adversary action sequences.
Date: January 24, 1978
Creator: Hollstien, R.B.
Object Type: Report
System: The UNT Digital Library
NH/sub 3/ preconcentrator/integrator instruction manual. [Measured 10 parts per billion of ammonia in room air] (open access)

NH/sub 3/ preconcentrator/integrator instruction manual. [Measured 10 parts per billion of ammonia in room air]

Microwave rotational spectrometry is a very selective analytical technique for polar gaseous compounds. For some selected molecules (e.g., HN/sub 3/, H/sub 2/CO, SO/sub 2/, etc.) concentrations as low as 100 ppB can be detected by continuously flowing the analyzed gas mixture through the absorption cell. However, some form of preconcentration of the desired species is required for detection limits below 100 ppB. Initial work with various trap materials for ammonia suggests using chromatographic packing material. Specifically, Chromasorb 104 provides an efficient trap and has been found to quantitatively release the ammonia upon slight heating. A preconcentrator/integrator module to thoroughly test the concept of quantitative preconcentration by the method of adsorption-desorption on chromatographic packing materials was constructed. It was used in conjunction with the microwave spectrometer ammonia detector to provide quantitative data of trapping efficiency and reproducibility. The preconcentrator/integrator system is described. (WHK)
Date: June 24, 1976
Creator: Hrubesh, L.; Barton, V. & Morris, C.
Object Type: Report
System: The UNT Digital Library
Evaluations of the Piping System Inelastic Analysis Computer Program PIRAX2 (open access)

Evaluations of the Piping System Inelastic Analysis Computer Program PIRAX2

None
Date: October 24, 1977
Creator: Rodabaugh, E. C.
Object Type: Report
System: The UNT Digital Library
Measurement considerations: dosimetry (open access)

Measurement considerations: dosimetry

None
Date: October 24, 1974
Creator: Thomas, R. H.
Object Type: Report
System: The UNT Digital Library
Method for computer simulation of problems in solid mechanics and gas dynamics in three dimensions and time (open access)

Method for computer simulation of problems in solid mechanics and gas dynamics in three dimensions and time

None
Date: April 24, 1974
Creator: Wilkins, M.L.; Blum, R.E.; Cronshagen, E. & Grantham, P.
Object Type: Report
System: The UNT Digital Library
Injector system for the 14 MeV high intensity neutron facility (open access)

Injector system for the 14 MeV high intensity neutron facility

None
Date: April 24, 1974
Creator: Beal, J. W.
Object Type: Report
System: The UNT Digital Library
Management of radioactive low level liquid, gaseous, and solid wastes in the 200 areas (open access)

Management of radioactive low level liquid, gaseous, and solid wastes in the 200 areas

The practices which are currently used for handling radioactive waste are outlined. These include burial of solid waste, scrubbing of off gas streams, and routing liquid effluents (mostly cooling water) to open ponds where the water percolates to the water table. (LK)
Date: June 24, 1976
Creator: White, A. T.
Object Type: Article
System: The UNT Digital Library
Interim program for the management of high-level radioactive liquid waste (open access)

Interim program for the management of high-level radioactive liquid waste

An overview of present operations concerned with the management of Hanford-generated high-level radioactive wastes is presented. Interim storage, leak experience, costs, and program operations are discussed. (LK)
Date: June 24, 1976
Creator: Burton, G. Jr.
Object Type: Article
System: The UNT Digital Library
Seismic stress analysis of feeder lines to LOFT primary coolant pump motors (open access)

Seismic stress analysis of feeder lines to LOFT primary coolant pump motors

The conduit system in the LOFT Support Building was analyzed for seismic loading. The conduit itself plus its various supports were subjected to both horizontal and vertical forces. The results show the system loads or stresses to be within allowables.
Date: March 24, 1978
Creator: Kuehster, C. J.
Object Type: Report
System: The UNT Digital Library
Sodium testing of intermediate-size inducer pump in SPTF at ETEC (open access)

Sodium testing of intermediate-size inducer pump in SPTF at ETEC

The overall test program includes pump assembly, installation, testing, removal from the test loop, disassembly and final inspection of the entire pump. Testing will include checkout tests, head/flow and efficiency characterizations at selected speeds and sodium temperatures, suction performance determination, a 2000 hour design point endurance test, a 300 hour off design endurance test, and thermal transient tests. The pump will be cleaned of sodium, disassembled, and examined before the 2000 hour endurance test and after the thermal transient tests to determine the effects that long-term operation at 200 percent NPSH margin and off design operation at the same flow and NPSH have on the pump components.
Date: March 24, 1979
Creator: Pfouts, J. O.
Object Type: Report
System: The UNT Digital Library
SNAP 8 summary report (open access)

SNAP 8 summary report

The SNAP 8 Program was directed toward the development of lightweight nuclear reactors which would operate in space for greater than 10,000 hr at a power level of 600 kW(t). Toward this objective, two reactors were designed, built, and successfully operated. The experimental reactor (S8ER) was an engineering test of a prototype core, but did not have flight-developed hardware. The developmental reactor (S8DR) was a nuclear system test to verify the operability of the integrated flight configuration. The development, design characteristics, operating experience, experimental results, and supporting tests for the S8ER and S8DR are discussed. 20 references. (auth)
Date: September 24, 1973
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Steady state heat transfer in ORR irradiation capsules (open access)

Steady state heat transfer in ORR irradiation capsules

The differential equation and boundary conditions that describe steady state heat transfer in an Oak Ridge Research Reactor (ORR) irradiation capsule have been determined. The finite difference equations needed to obtain a numerical solution to the heat transfer problem were developed and an algorithm for the solution of these equations was specified. Analytical solutions for the second order partial differential equation with non-linear boundary conditions describing heat transfer in the problem were attempted. Various simplifying assumptions were not successful.
Date: March 24, 1977
Creator: Stiros, P.; Chao, E. I. & Michel, R. C.
Object Type: Report
System: The UNT Digital Library
Brief description of research papers accepted for publication during 1978. Annual report (open access)

Brief description of research papers accepted for publication during 1978. Annual report

Abstracts (172) of basic and applied research of papers accepted for publication are presented. An author index is included. (PCS)
Date: May 24, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
324 building safety analysis report supplement (open access)

324 building safety analysis report supplement

Process engineering designs, major equipment and plant facilities to be utilized in commercial nuclear waste preparation and vitrification in the 324 Radiochemical Engineering Building are reviewed with regard to accident potential and consequences. This Safety Analysis Report Supplement compares calculated environmental doses anticipated from the Commercial Nuclear Waste Vitrification Project (CNWVP) routine operations with the average doses from past waste management operations conducted at the Hanford Project and finds them to be significantly less. The calculated CNWVP environmental doses are found to be far below presently applicable ERDA standards and standards proposed by the EPA for nuclear power operations. (DLC)
Date: June 24, 1977
Creator: Dodd, A. O. & Wittenbrock, N. G.
Object Type: Report
System: The UNT Digital Library
Goose River, Maine, demonstration project, January 1978-October 1978. Final report (open access)

Goose River, Maine, demonstration project, January 1978-October 1978. Final report

The proposed Goose River Project is a commercial power development consisting of 4 power dams and one storage dam. All available energy is to be wholesaled to the Central Maine Power Company, the utility holding the franchise for the area. A description of the economic feasibility of the proposed project is presented.
Date: November 24, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Shiva optical diagnostics (open access)

Shiva optical diagnostics

In the laser fusion program at Lawrence Livermore Laboratory, no target experiment is complete unless it is complemented by careful measurements of the laser pulse that irradiates the target. For this purpose, an incident beam diagnostics (IBD) package has been designed for the Shiva laser. The package will furnish data on items such as the total energy and the focusable energy out of the laser chain, and the spatial and temporal energy and power distribution at the target plane. Understanding laser-plasma interactions requires knowledge of the amount of 1.06 ..mu..m light energy that is scattered in various directions from the target. The light energy that is scattered toward the beam focusing lens is analyzed by a reflected beam diagnostic (RBD) package containing a calorimeter, a multiple image camera and a TV camera. This paper describes the detailed design and operation of the IBD and RBD packages as tools to align spatial filters and targets, as well as to diagnose the laser beams and target reflectivity.
Date: October 24, 1977
Creator: Rienecker, F.; Kobierecki, M.; Ozarski, R.; Seppala, L.; Manes, K. & Merritt, B.
Object Type: Article
System: The UNT Digital Library
Analytical chemical system for the determination of heavy metals and organic compounds. Annual progress report, December 1, 1978-November 30, 1979 (open access)

Analytical chemical system for the determination of heavy metals and organic compounds. Annual progress report, December 1, 1978-November 30, 1979

Progress has been made in the synthesis and characterization of new resins for sequestering inorganic and organic compounds. The capabilities of the poly(dithiocarbamate) resin have been extended, a new poly(acrylamidoxime) resin prepared and characterized, and a series of resins for organic compounds prepared and tested. Limited actual sample analyses have been performed with these resins. A new inductively coupled plasma source, spectrometer, and computer system have been received and they are undergoing tests and installation. With this system in place, the multielement analysis of metals during the forthcoming period will insure the application of sequestering resins to practical analysis of energy-related materials. An automated sample handling and data system has been designed, some components purchased, and construction is scheduled for 1980.
Date: October 24, 1979
Creator: Siggia, S. & Barnes, R. M.
Object Type: Report
System: The UNT Digital Library
Standards for the publication of powder patterns: the American crystallographic association subcommittee's final report (open access)

Standards for the publication of powder patterns: the American crystallographic association subcommittee's final report

A subcommittee of the American Crystallographic Association (ACA) was formed to recommend some guidelines that would improve the overall quality of published powder diffraction data. An analysis of the Powder Diffraction File shows that many of the well-known techniques for obtaining good quality data are often not being applied, and hence there is a need for the establishment of publication standards. A major recommendation from this subcommittee is the use of a standard data-form at the author/referee level of publication. The proposed data-form is divided into five sections: sample characterizaton, technique, unit cell data, references, and the powder data. The information asked for in these five sections represents what, in most cases, the referee and editor can reasonably expect of experimenters seeking to publish their powder data. An example of a filled-out form is shown, and instructions for completing the form are given. Another recommendation is that the ACA request that the International Union of Crystallography consider implementing these recommendations in all IUCr journals.
Date: April 24, 1979
Creator: Calvert, L. D.; Flippen-Anderson, J. L. & Hubbard, C. R.
Object Type: Article
System: The UNT Digital Library
LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974) (open access)

LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included.
Date: February 24, 1977
Creator: Buchanan, J. R. & Keilholtz, G. W.
Object Type: Report
System: The UNT Digital Library
A Manpower Assessment of the Geothermal Industry (open access)

A Manpower Assessment of the Geothermal Industry

The authors were asked to estimate the net employment gains in the geothermal industry from 1980 to 1985 and 1990. Method was by survey. Response rates were high, so the estimates here likely reflect industry knowledge and outlooks at the start of the most active construction decade of the U.S. geothermal industry. An untitled table following Table IV-1 is of great interest because it breaks out employment requirement estimates for different phases/aspects of project development, i.e., exploration and resource assessment, exploratory drilling, production drilling, power plant construction, feed system (field piping) construction, field operation and maintenance, power plant operation and maintenance, and transmission line construction. Estimates like these are rare in the U.S. geothermal literature. While these estimates are dated, they comprise an historical economic baseline from which improvements in labor use in the geothermal industry might be constructed. (DJE 2005)
Date: August 24, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Supplement to safety analysis report for the 325 Radiochemistry Building (open access)

Supplement to safety analysis report for the 325 Radiochemistry Building

The Waste Preparation Task (Task 6) of the Commercial Nuclear Waste Vitrification Project (CNWVP) includes the design, installation and operation of small scale (1 MTU LWR fuel/month) equipment to prepare high-level liquid waste (HLLW) from commercial LWR spent fuel. The HLLW will be used in Task 5, the radioactive demonstration of waste vitrification. The operational aspects of this task include the procurement of irradiated LWR fuel; the processing operations to prepare HLLW; and other necessary operations associated with the disposition of the uranium waste and other fuel residues, including the plutonium associated with the fuel. The processing operations in the 325-A Building will require handling in excess of 45 percent of a Minimum Critical Mass (MCM), use of an organic solvent to extract uranium and plutonium away from the fission products, and ion exchange resin for plutonium purification. An analysis of the environmental consequences and probability of conceivable accidental conditions that may result from this operation indicates no undue consequences to the environment. The calculated maximum environmental consequences of postulated accidents would be low radiotoxic doses of 0.3 rem whole body 50-yr dose commitment to a maximum individual and 20 man-rem whole body 50-yr dose commitment to the surrounding population. …
Date: June 24, 1977
Creator: Bryan, G. H. & Wittenbrock, N. G.
Object Type: Report
System: The UNT Digital Library
HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1976. [Graphite and fuel irradiation; fission product release] (open access)

HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1976. [Graphite and fuel irradiation; fission product release]

The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and, where appropriate, the data are presented in tables, graphs, and photographs.
Date: September 24, 1976
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Terrestrial service environments for selected geographic locations. Final report. [1965--1974 data; to define solar array environment to aid in encapsulation program] (open access)

Terrestrial service environments for selected geographic locations. Final report. [1965--1974 data; to define solar array environment to aid in encapsulation program]

This report contains results obtained from analyses of climatic, precipitation, air pollution, and other environmental data for the years 1965 to 1974 at nine widely different geographic locations in the United States (Albuquerque, N.M.; Bismarck, N.D.; Boston, Mass.; Brownsville, TX.; Cleveland, OH; Fairbanks, AK; Los Angeles, CA; Miami, FL; and Phoenix, AZ). In addition to descriptive and diurnal statistics for 24 individual climatic variables, ''environmental cell'' statistics were computed to obtain the frequencies, durations, and transitions for the simultaneous occurrence of various combinations of environmental variables. Results are presented for the simultaneous occurrence of specific levels of air temperature, relative humidity, wind speed, and insolation, in addition to representative results obtained for other combinations of variables. The results characterize the environmental conditions to which terrestrial solar arrays would be exposed over a 20-year lifetime, and serve to identify environmental factors and levels that can be used in testing candidate encapsulation materials and systems for such terrestrial exposures. An innovative methodology was applied to obtain these results for combinations of environmental variables. Because of its generality and demonstrated feasibility, it is concluded that the methodology also has broad applications to other testing programs.
Date: June 24, 1976
Creator: Thomas, R. E. & Carmichael, D. C.
Object Type: Report
System: The UNT Digital Library