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ION-1 technical manual (open access)

ION-1 technical manual

The portable gamma-ray and neutron detector electronics (ION-1) gives a digital readout of the current-mode response produced by gamma rays in an ion chamber and of amplification and scaling of pulses received from a neutron detector. The primary application is the measurement of gamma-ray and neutron activity of irradiated reactor fuels stored at a reactor or at a storage pond away from a reactor. ION-1 is the first such instrument to use a design that allows communication of procedures, response, and results between instrument and inspector. It prompts the inspector through procedures, carries out programmed measurement steps, calculates results and error estimates, and performs internal diagnostic checks. This Technical Manual describes adjustment procedures and limited technical information that enable the inspector to troubleshoot at the board level. 5 figs., 10 tabs.
Date: July 1, 1985
Creator: Halbig, J. K. & Caine, J. C.
Object Type: Report
System: The UNT Digital Library
Tonopah Test Range capabilities: technical manual (open access)

Tonopah Test Range capabilities: technical manual

This manual describes Tonopah Test Range (TTR), defines its testing capabilities, and outlines the steps necessary to schedule tests on the Range. Operated by Sandia National Laboratories, TTR is a major test facility for DOE-funded weapon programs. The Range presents an integrated system for ballistic test vehicle tracking and data acquisition. Multiple radars, optical trackers, telemetry stations, a central computer complex, and combined landline/RF communications systems assure full Range coverage for any type of test. Range operations are conducted by a department within Sandia's Field Engineering Directorate. While the overall Range functions as a complete system, it is operationally divided into the Test Measurements, Instrumentation Development, and Range Operations divisions. The primary function of TTR is to support DOE weapons test activities. Management, however, encourages other Government agencies and their contractors to schedule tests on the Range which can make effective use of its capabilities. Information concerning Range use by organizations outside of DOE is presented. Range instrumentation and support facilities are described in detail. This equipment represents the current state-of-the-art and reflects a continuing commitment by TTR management to field the most effective tracking and data acquisition system available.
Date: November 1, 1982
Creator: Manhart, R.L.
Object Type: Report
System: The UNT Digital Library
Technical manual for calculating cooling pond performance (open access)

Technical manual for calculating cooling pond performance

This manual is produced in response to a growing number of requests for a technical aid to explain methods for simulating cooling pond performance. As such, it is a compilation of reports, charts and graphs developed through the years for use in analyzing situations. Section II contains a report summarizing the factors affecting cooling pond performance and lists statistical parameters used in developing performance simulations. Section III contains the graphs of simulated cooling pond performance on an hourly basis for various combinations of criteria (wind, solar, depth, air temperature and humidity) developed from the report in Section II. Section IV contains correspondence describing how to develop further data from the graphs in Section III, as well as mathematical models for the system of performance calculation. Section V contains the formulas used to simulate cooling pond performances in a cascade arrangement, such as the Fermilab Main Ring ponds. Section VI contains the calculations currently in use to evaluate the Main Ring pond performance based on current flows and Watts loadings. Section VII contains the overall site drawing of the Main Ring cooling ponds with thermal analysis and physical data.
Date: July 1, 1988
Creator: Krstulovich, S.F.
Object Type: Report
System: The UNT Digital Library
Spray Calciner/In-Can Melter high-level waste solidification technical manual (open access)

Spray Calciner/In-Can Melter high-level waste solidification technical manual

This technical manual summarizes process and equipment technology developed at Pacific Northwest Laboratory over the last 20 years for vitrification of high-level liquid waste by the Spray Calciner/In-Can Melter process. Pacific Northwest Laboratory experience includes process development and demonstration in laboratory-, pilot-, and full-scale equipment using nonradioactive synthetic wastes. Also, laboratory- and pilot-scale process demonstrations have been conducted using actual high-level radioactive wastes. In the course of process development, more than 26 tonnes of borosilicate glass have been produced in 75 canisters. Four of these canisters contained radioactive waste glass. The associated process and glass chemistry is discussed. Technology areas described include calciner feed treatment and techniques, calcination, vitrification, off-gas treatment, glass containment (the canister), and waste glass chemistry. Areas of optimization and site-specific development that would be needed to adapt this base technology for specific plant application are indicated. A conceptual Spray Calciner/In-Can Melter system design and analyses are provided in the manual to assist prospective users in evaluating the process for plant application, to provide equipment design information, and to supply information for safety analyses and environmental reports. The base (generic) technology for the Spray Calciner/In-Can Melter process has been developed to a point at which it is …
Date: September 1, 1980
Creator: Larson, D.E. (ed.)
Object Type: Report
System: The UNT Digital Library
WASTES: Waste System Transportation and Economic Simulation--Version 2: Technical Reference Manual (open access)

WASTES: Waste System Transportation and Economic Simulation--Version 2: Technical Reference Manual

The Waste System Transportation and Economic Simulation (WASTES) Technical Reference Manual was written to describe and document the algorithms used within the WASTES model as implemented in Version 2.23. The manual will serve as a reference for users of the WASTES system. The intended audience for this manual are knowledgeable users of WASTES who have an interest in the underlying principles and algorithms used within the WASTES model. Each algorithm is described in nonprogrammers terminology, and the source and uncertainties of the constants in use by these algorithms are described. The manual also describes the general philosophy and rules used to: 1) determine the allocation and priority of spent fuel generation sources to facility destinations, 2) calculate transportation costs, and 3) estimate the cost of at-reactor ex-pool storage. A detailed description of the implementation of many of the algorithms is also included in the WASTES Programmers Reference Manual (Shay and Buxbaum 1986a). This manual is separated into sections based on the general usage of the algorithms being discussed. 8 refs., 14 figs., 2 tabs.
Date: February 1, 1988
Creator: Sovers, R. A.; Shay, M. R.; Ouderkirk, S. J.; McNair, G. W. & Eagle, B. G.
Object Type: Report
System: The UNT Digital Library
Underground Injection Control Technical Assistace Manual: Subsurface Disposal and Solution Mining (open access)

Underground Injection Control Technical Assistace Manual: Subsurface Disposal and Solution Mining

Report providing a comprehensive analysis of current injection well practices in Texas and information for the general public about current practices and how they protect the quality of water resources. It is also intended to be a general guide for persons considering or planning an underground injection project.
Date: April 1983
Creator: Greene, Charles J.
Object Type: Report
System: The Portal to Texas History
SRC-I Demonstration Plant Analytical Laboratory Methods Manual. Final Technical Report (open access)

SRC-I Demonstration Plant Analytical Laboratory Methods Manual. Final Technical Report

This manual is a compilation of analytical procedures required for operation of a Solvent-Refined Coal (SRC-I) demonstration or commercial plant. Each method reproduced in full includes a detailed procedure, a list of equipment and reagents, safety precautions, and, where possible, a precision statement. Procedures for the laboratory's environmental and industrial hygiene modules are not included. Required American Society for Testing and Materials (ASTM) methods are cited, and ICRC's suggested modifications to these methods for handling coal-derived products are provided.
Date: March 1, 1983
Creator: Klusaritz, M. L.; Tewari, K. C.; Tiedge, W. F.; Skinner, R. W. & Znaimer, S.
Object Type: Report
System: The UNT Digital Library
Nuclear material operations manual (open access)

Nuclear material operations manual

This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion.
Date: February 1, 1981
Creator: Tyler, R.P.
Object Type: Report
System: The UNT Digital Library
Technical bases and user's manual for the prototype of a Suppression Pool Aerosol Removal Code (SPARC) (open access)

Technical bases and user's manual for the prototype of a Suppression Pool Aerosol Removal Code (SPARC)

This code was written to calculate the capture of aerosol particles in the pressure suppression pool (wet well) of a boiling water reactor under hypothetical accident conditions. The code incorporates five aerosol scrubbing models and two thermal-hydraulic models. The scrubbing models describe (1) steam condensation, (2) soluble particle growth in a humid atmosphere, (3) gravitational settling, (4) inertial deposition, (5) diffusional deposition. Mechanical entrainment of pool liquid by breaking of bubbles at the surface was also considered. An optional model for equilibrium pool temperature and a model for steam evaporation are the two thermal-hydraulic models used in the code. Steam evaporation was found to significantly retard deposition processes in pools near the boiling point. The code user supplies the values of several controlling variables in the code input. The SPARC output can include the decontamination factors (DF) of twenty different particle size groups, an overall DF for the whole particle distribution, particle log normal distribution parameters, and mass flow rates of particles (wet and dry) leaving the pool.
Date: May 1, 1985
Creator: Owczarski, P.C.; Schreck, R.I. & Postma, A.K.
Object Type: Report
System: The UNT Digital Library
SNAP operating system reference manual (open access)

SNAP operating system reference manual

The SNAP Operating System (SOS) is a FORTRAN 77 program which provides assistance to the safeguards analyst who uses the Safeguards Automated Facility Evaluation (SAFE) and the Safeguards Network Analysis Procedure (SNAP) techniques. Features offered by SOS are a data base system for storing a library of SNAP applications, computer graphics representation of SNAP models, a computer graphics editor to develop and modify SNAP models, a SAFE-to-SNAP interface, automatic generation of SNAP input data, and a computer graphic post-processor for SNAP. The SOS Reference Manual provides detailed application information concerning SOS as well as a detailed discussion of all SOS components and their associated command input formats. SOS was developed for the US Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the US Naval Surface Weapons Center by Pritsker and Associates, Inc., under contract to Sandia National Laboratories.
Date: March 1, 1982
Creator: Sabuda, J.D.; Polito, J.; Walker, J.L. & Grant, F. H., III
Object Type: Report
System: The UNT Digital Library
Birdcage neutron coincidence counter manual (open access)

Birdcage neutron coincidence counter manual

A thermal neutron coincidence counter has been constructed for the assay of fast critical assembly fuel plates stored in birdcages. Standard coincidence counting electronics are used. This manual describes the birdcage, the measurement system, and its performance characteristics. 3 refs.
Date: July 1, 1985
Creator: Krick, M. S.; Menlove, H. O. & Ramalho, A.
Object Type: Report
System: The UNT Digital Library
Uranium concentration monitor manual: 2300 system (open access)

Uranium concentration monitor manual: 2300 system

This manual describes the design, operation, and procedures for measurement control for the automated uranium concentration monitor on the 2300 solvent extraction system at the Oak Ridge Y-12 Plant. The nonintrusive monitor provides a near-real time readout of uranium concentration at two locations simultaneously in the solvent extraction system for process monitoring and control. Detectors installed at the top of the extraction column and at the bottom of the backwash column acquire spectra of gamma rays from the solvent extraction solutions in the columns. Pulse-height analysis of these spectra gives the concentration of uranium in the organic product of the extraction column and in the aqueous product of the solvent extraction system. The visual readouts of concentrations for process monitoring are updated every 2 min for both detection systems. Simultaneously, the concentration results are shipped to a remote computer that has been installed by Y-12 to demonstrate automatic control of the solvent extraction system based on input of near-real time process operation information. 8 refs., 13 figs., 4 tabs.
Date: April 1, 1985
Creator: Russo, P. A.; Sprinkle, J. K. Jr. & Stephens, M. M.
Object Type: Report
System: The UNT Digital Library
Plutonium Canister Counter operations and procedures manual (open access)

Plutonium Canister Counter operations and procedures manual

A neutron coincidence counter has been designed for the measurement of plutonium powder contained in storage canisters. Each canister contains from one to four cans of mixed oxide. The neutron counter measures the spontaneous fission rate from the plutonium, and when this is combined with the plutonium isotopic ratios, the plutonium mass is determined. The system can accommodate plutonium loadings up to 8 kg, with 4 kg being a typical loading. This manual describes the system and its operation and gives performance and calibration parameters for typical applications. 5 refs., 10 figs., 8 tabs.
Date: February 1, 1986
Creator: Menlove, H. O.; Adams, E. L.; Dahn, E. & Ramalho, A.
Object Type: Report
System: The UNT Digital Library
Fast-neutron coincidence-counter manual (open access)

Fast-neutron coincidence-counter manual

The fast neutron counter (FNC) described in this report is a computer-based assay system employing fast-pulse counting instrumentation. It is installed below a glove box in the metal electrorefining area of the Los Alamos National Laboratory Plutonium Processing Facility. The instrument was designed to assay plutonium salts and residues from this process and to verify the mass of electrorefined metal. Los Alamos National Laboratory Groups Q-1, Q-3, and CMB-11 carried out a joint test and evaluation plan of this instrument between May 1978 and May 1979. The results of that evaluation, a description of the FNC, and operating instructions for further use are given in this report.
Date: March 1, 1982
Creator: Ensslin, N.; Atwell, T. L.; Lee, D. M.; Erkkila, B.; Marshall, R. S.; Morgan, A. et al.
Object Type: Report
System: The UNT Digital Library
L/sub III/-edge densitometer operations manual (open access)

L/sub III/-edge densitometer operations manual

This report describes briefly the operation and maintenance of an L/sub III/-edge densitometer. The instrument is optimized for 50 g/l of special nuclear material, but yields better than 0.5% precision in 1000-s assays over a concentration range of 10 to 90 g/l. It can determine uranium and plutonium concentrations in a 2-ml sample cell and has been designed for both static and flowing solution measurements.
Date: October 1, 1981
Creator: Sprinkle, J. K. Jr.; Johnson, S. S.; Langner, D. G. & Russo, P. A.
Object Type: Report
System: The UNT Digital Library
Instructor training manual: For use with energy conservation practices participant manual (open access)

Instructor training manual: For use with energy conservation practices participant manual

This manual is a tool for instruction to residential building tenants who are interested in enhancing energy conservation practices in their homes. (BCS)
Date: May 1, 1988
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Dounreay Shuffler diagnostic software operations manual (open access)

Dounreay Shuffler diagnostic software operations manual

This operations manual describes the test software for the Dounreay Shuffler. The Shuffler is an assay system, controlled by a Commodore PET computer, that measures the plutonium content in leached hulls at the fuel reprocessing plant in Dounreay, Scotland. The Shuffler contains a /sup 252/Cf neutron source that is moved between storage and irradiation locations to obtain measurement data. A stepping motor control (SMC) module operates the Shuffler and accepts commands from the PET to move the source. This manual briefly describes the Shuffler and provides details on running and using the diagnostic software program. The communications protocol for message transmittal between the PET and SMC is defined and a detailed example of message sending is presented in an appendix.
Date: July 1, 1985
Creator: Eccleston, G. W.; Stuewe, B.; Klosterbuer, S. & Van Lyssel, T.
Object Type: Report
System: The UNT Digital Library
RCS auditor trainee manual: renewable resource measures (revised). United States Department of Energy Technical Assistance Program for the Residential Conservation Service Program (open access)

RCS auditor trainee manual: renewable resource measures (revised). United States Department of Energy Technical Assistance Program for the Residential Conservation Service Program

This manual describes the use of renewable measures and the procedures used to audit for them. Included are active solar space and water heating systems, passive solar space and water heating systems, and wind energy systems. Sample audit forms are completed for a house in Oklahoma City, Oklahoma. A summary of installation standards for active solar systems is included. (WHK)
Date: October 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Universal Fast Breeder Reactor Subassembly Counter manual (open access)

Universal Fast Breeder Reactor Subassembly Counter manual

A neutron coincidence counter has been designed for the measurement of fast breeder reactor fuel assemblies. This assay system can accommodate the full range of geometries and masses found in fast breeder subassemblies under IAEA safeguards. The system's high-performance capability accommodates high plutonium loadings of up to 16 kg. This manual describes the system and its operation and gives performance and calibration parameters for typical applications.
Date: August 1, 1984
Creator: Menlove, H. O.; Eccleston, G. W.; Swansen, J. E.; Goris, P.; Abedin-Zadeh, R. & Ramalho, A.
Object Type: Report
System: The UNT Digital Library
Ziptrack manual (open access)

Ziptrack manual

A phenolic cart holding 3 mutually perpendicular search coils is moved through an luminum beam into the magnetic field. Coil voltages re integrated and digitized through a Data Translation 1712 ADC. The cart is controlled and the data is processed by an on-line PDP-11/05 computer. The results are displayed on a Tektronix 4010 terminal, stored on 9 track, 800 bpi tapes, and optionally recorded on a hard copy. Software on a floppy disk controls the system. The position of the cart is located by an encoder and is checked along the beam line by optical switches. One encoder count equals 0.01945 in.. The X and Y positions are changed by manipulators at each end of the beam. 625 horizontal or 500 vertical counts equal 1 in.. The desired field mapping can be automatically set up by programming a grid of encoder counts on the ''SHOW STATUS'' chart. A ziptrack command summary is given. Following that is a typical procedure for ziptrack operations. Also attached are time constants for the integrators and coil calibrations for 30 ft. and 100 ft. long cables.
Date: July 1, 1983
Creator: Ito, A.; Bosworth, W.; Rutherford, J.; Lynch, A.; Tung, L. & Yang, W.
Object Type: Report
System: The UNT Digital Library
RAVEN physics manual (open access)

RAVEN physics manual

This document is an exposition of the physics in the RAVEN code and the numerical methods used in implementing the physics.
Date: June 1, 1981
Creator: Oliphant, Thomas A.
Object Type: Report
System: The UNT Digital Library
TART input manual (open access)

TART input manual

The TART code is a Monte Carlo neutron/photon transport code that is only on the CRAY computer. All the input cards for the TART code are listed, and definitions for all input parameters are given. The execution and limitations of the code are described, and input for two sample problems are given. (WHK)
Date: April 1, 1982
Creator: Kimlinger, J.R. & Plechaty, E.F.
Object Type: Report
System: The UNT Digital Library
IPCS user's manual (open access)

IPCS user's manual

The Interprocess Communications System (IPCS) was written to provide a virtual machine upon which the Supervisory Control and Diagnostic System (SCDS) for the Mirror Fusion Test Facility (MFTF) could be built. The hardware upon which the IPCS runs consists of nine minicomputers sharing some common memory.
Date: December 11, 1980
Creator: McGoldrick, P.R.
Object Type: Report
System: The UNT Digital Library
Tokai densitometer manual (open access)

Tokai densitometer manual

In 1979, the Tokai densitometer was installed at the Tokai Reprocessing Plant in Tokai, Japan. It uses a nondestructive active technique (K-edge absorption densitometry) to assay solutions for plutonium content. The original hardware was upgraded in 1984 and 1985. This manual describes the instrument's operation after the upgrade. 2 refs.
Date: January 1, 1987
Creator: Sprinkle, J. K. Jr.; Hsue, S. T. & Junck, K.
Object Type: Report
System: The UNT Digital Library