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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
ZAP user's manual
The use and content of Phase I of the accelerator physics code ZAP, which calculates the performance of a storage ring in terms of the effects of beam intensity dependent phenomena and the limitations they impose. A brief overview is provided of the code and the types of calculations that can be performed with it. The types of calculations available include: single bunch thresholds, single bunch longitudinal parameters and energy scaling tables, longitudinal coupled-bunch instabilities, transverse coupled-bunch instabilities, gas scattering lifetime, free electron laser formulae, intrabeam scattering, Touschek scattering, and ion trapping formulae. Examples of the required inputs and resultant outputs for each of the options are given. The theoretical foundations behind ZAP are summarized, providing the relevant formulations, physical models, and particularly the equations used in the code in evaluating the various effects that are computed. (LEW)
Date:
December 1, 1986
Creator:
Zisman, M. S.; Chattopadhyay, S. & Bisognano, J. J.
Object Type:
Report
System:
The UNT Digital Library
INGEN: A COBRA-NC input generator user's manual
The INGEN (INput GENerator) computer program has been developed as a preprocessor to simplify input generation for the COBRA-NC computer program. INGEN uses several empirical correlations and geometric assumptions to simplify the data input requirements for the COBRA-NC computer code. The simplified input scheme is obtained at the expense of much flexibility provided by COBRA-NC. For more complex problems requiring additional flexibility however, INGEN may be used to provide a skeletal input file to which the more detailed input may be added. This report describes the input requirements for INGEN and describes the algorithms and correlations used to generate the COBRA-NC input. 9 refs., 3 figs., 6 tabs.
Date:
December 1, 1986
Creator:
Wheeler, C.L. & Dodge, R.E.
Object Type:
Report
System:
The UNT Digital Library
Modified hazard ranking system for sites with mixed radioactive and hazardous wastes. User manual.
This document describes both the original Hazard Ranking System and the modified Hazard Ranking System as they are to be used in evaluating the relative potential for uncontrolled hazardous substance facilities to cause human health or safety problems or ecological or environmental damage. Detailed instructions for using the mHRS/HRS computer code are provided, along with instructions for performing the calculations by hand. Uniform application of the ranking system will permit the DOE to identify those releases of hazardous substances that pose the greatest hazard to humans or the environment. However, the mHRS/HRS by itself cannot establish priorities for the allocation of funds for remedial action. The mHRS/HRS is a means for applying uniform technical judgment regarding the potential hazards presented by a facility relative to other facilities. It does not address the feasibility, desirability, or degree of cleanup required. Neither does it deal with the readiness or ability of a state to carry out such remedial action, as may be indicated, or to meet other conditions prescribed in CERCLA. 13 refs., 13 figs., 27 tabs.
Date:
April 1, 1986
Creator:
Hawley, K. A.; Peloquin, R. A. & Stenner, R. D.
Object Type:
Report
System:
The UNT Digital Library
WASTES: Wastes system transportation and economic simulation: Version 2, Programmer's reference manual
The WASTES Version II (WASTES II) Programmer's Reference Manual was written to document code development activities performed under the Monitored Retrievable Storage (MRS) Program at Pacific Northwest Laboratory (PNL). The manual will also serve as a valuable tool for programmers involved in maintenance of and updates to the WASTES II code. The intended audience for this manual are experienced FORTRAN programmers who have only a limited knowledge of nuclear reactor operation, the nuclear fuel cycle, or nuclear waste management practices. It is assumed that the readers of this manual have previously reviewed the WASTES II Users Guide published as PNL Report 5714. The WASTES II code is written in FORTRAN 77 as an extension to the SLAM commercial simulation package. The model is predominately a FORTRAN based model that makes extensive use of the SLAM file maintenance and time management routines. This manual documents the general manner in which the code is constructed and the interactions between SLAM and the WASTES subroutines. The functionality of each of the major WASTES subroutines is illustrated with ''block flow'' diagrams. The basic function of each of these subroutines, the algorithms used in them, and a discussion of items of particular note in the …
Date:
November 1, 1986
Creator:
Buxbaum, M. E. & Shay, M. R.
Object Type:
Report
System:
The UNT Digital Library
[Program Manual for the Links, Inc.]
Program manual for the Links, Inc. - a national community service organization founded by professional women with various state and local branches. The lengthy text discusses various national and local programs, educational and youth outreach, organizational structure and its hierarchy of members, and a plethora of other administrative information.
Date:
1986/1988
Creator:
Links, Inc. San Antonio Chapter.
Object Type:
Text
System:
The Portal to Texas History
Procedure manual for the estimation of average indoor radon-daughter concentrations using the radon grab-sampling method
The US Department of Energy (DOE) Office of Remedial Action and Waste Technology established the Technical Measurements Center to provide standardization, calibration, comparability, verification of data, quality assurance, and cost-effectiveness for the measurement requirements of DOE remedial action programs. One of the remedial-action measurement needs is the estimation of average indoor radon-daughter concentration. One method for accomplishing such estimations in support of DOE remedial action programs is the radon grab-sampling method. This manual describes procedures for radon grab sampling, with the application specifically directed to the estimation of average indoor radon-daughter concentration (RDC) in highly ventilated structures. This particular application of the measurement method is for cases where RDC estimates derived from long-term integrated measurements under occupied conditions are below the standard and where the structure being evaluated is considered to be highly ventilated. The radon grab-sampling method requires that sampling be conducted under standard maximized conditions. Briefly, the procedure for radon grab sampling involves the following steps: selection of sampling and counting equipment; sample acquisition and processing, including data reduction; calibration of equipment, including provisions to correct for pressure effects when sampling at various elevations; and incorporation of quality-control and assurance measures. This manual describes each of the above …
Date:
April 1, 1986
Creator:
George, J. L.
Object Type:
Report
System:
The UNT Digital Library
User's manual for FENAT: a two-dimensional multigroup diffusion theory Finite Element Neutral Atom Transport code
FENAT solves the two-dimensional energy dependent diffusion equation in Cartesian (X-Y) and cylindrical/toroidal (R-Z) coordinates. The boundary conditions allowed are: vacuum, reflection, albedo and surface source. The energy variable is treated by multigroup method. The resulting multigroup diffusion equation is solved by finite element Galerkin's method with triangular element discretization of the spatial domain. The algebraic matrix equation is solved by the direct method of Crout variation of Gauss' elimination. Dynamic memory allocation has been used so that the maximum problem size is limited by the size of active core storage of the machine. When necessary, the global matrix is stored in a binary disk file. FENAT is particularly suitable for the transport of neutral atoms in fusion plasmas.
Date:
July 1, 1986
Creator:
Hasan, M.Z.
Object Type:
Report
System:
The UNT Digital Library
COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 2, User's manual
COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Department of Energy's Commercial Spent Fuel Management Program. The finite-volume equations governing mass, momentum, and energy conservation are written for an incompressible, single-phase fluid. The flow equations model a wide range of conditions including natural circulation. The energy equations include the effects of solid and fluid conduction, natural convection, and thermal radiation. The COBRA-SFS code is structured to perform both steady-state and transient calculations; however, the transient capability has not yet been validated. This volume contains the input instructions for COBRA-SFS and an auxiliary radiation exchange factor code, RADX-1. It is intended to aid the user in becoming familiar with the capabilities and modeling conventions of the code.
Date:
November 1, 1986
Creator:
Rector, D. R.; Cuta, J. M.; Lombardo, N. J.; Michener, T. E. & Wheeler, C. L.
Object Type:
Report
System:
The UNT Digital Library
Automated Measurement of Frequency Response of Frequency-Modulated Generators Using the Bessel Null Method
From abstract: This paper describes a Bessel null technique to measure the frequency response of a frequency-modulated rf carrier and a program to automate frequency response measurements of signal generators with output frequencies from 0.450 to 2000 MHz. The measurements obtained using this technique are more precise than those obtained by a highly trained technician using a manual system.
Date:
March 1986
Creator:
Major, J. R.; Livingston, E. M. & Adair, Robert T.
Object Type:
Report
System:
The UNT Digital Library
Technical documentation and user's guide for City-County Allocation Model (CCAM). Version 1. 0
The City-County Allocation Model (CCAM) was developed as part of the Monitored Retrievable Storage (MRS) Program. The CCAM model was designed to allocate population changes forecasted by the MASTER model to specific local communities within commuting distance of the MRS facility. The CCAM model was designed to then forecast the potential changes in demand for key community services such as housing, police protection, and utilities for these communities. The CCAM model uses a flexible on-line data base on demand for community services that is based on a combination of local service levels and state and national service standards. The CCAM model can be used to quickly forecast the potential community service consequence of economic development for local communities anywhere in the country. The remainder of this document is organized as follows. The purpose of this manual is to assist the user in understanding and operating the City-County Allocation Model (CCAM). The annual explains the data sources for the model and code modifications as well as the operational procedures.
Date:
May 1, 1986
Creator:
Clark Jr., L. T.; Scott, M. J. & Hammer, P.
Object Type:
Report
System:
The UNT Digital Library
The Regulatory environment for science
This technical memorandum, requested by the Task Force on Science Policy of the House Committee on Science and Technology, provides a “snapshot” of factors affecting science in the 1980s, and focuses on emerging issues that will require consideration by Congress.
Date:
February 1986
Creator:
United States. Congress. Office of Technology Assessment.
Object Type:
Report
System:
The UNT Digital Library
LADTAP II: technical reference and user guide
This report describes the US Nuclear Regulatory Commission computer program LADTAP II, which performs environmental dose analyses for releases of radioactive effluents from nuclear power plants into surface waters. The analyses estimate radiation dose to individuals, population groups, and biota from ingestion (aquatic foods, water, and terrestrial irrigated foods) and external exposure (shoreline, swimming, and boating) pathways. The calculated doses provide information for National Environmental Policy Act (NEPA) evaluations and for determining compliance with Appendix I of 10 CFR 50 (the ''ALARA'' philosophy). The report also instructs the user in preparing input to the program, describes the mathematical models that are used, and supplies detailed information on program structure and parameters used to modify the program.
Date:
April 1, 1986
Creator:
Strenge, D.L.; Peloquin, R.A. & Whelan, G.
Object Type:
Report
System:
The UNT Digital Library
Overview of decommissioning and decontamination technical information support activities funded by the US Department of Energy's remedial action programs
In 1979 the US Department of Energy (DOE) established the Remedial Action Program Information Center (RAPIC) at the Oak Ridge National Laboratory to provide technical information support to the Surplus Facilities Management Program, DOE's national decommissioning and decontamination (D and D) program which is managed by DOE's Richland Operations Office and UNC Nuclear Industries, Inc., and to the other DOE remedial action programs. Specific information activities that RAPIC performs to support the DOE's programs and the D and D community include: maintaining a computerized bibliographic database containing about 4500 annotated citations (about 2000 on D and D) and a database of 1800 contacts involved with remedial action work at radioactively contaminated sites; publishing an annual bibliography, ''Nuclear Facility Decommissioning and Site Remedial Actions, A Selected Bibliography,'' ORNL/EIS-154 (six volumes published); maintaining a document repository and providing copies of requested publications; and performing manual and computerized searches of the technical literature. The most significant RAPIC function is serving as a focal point for D and D information. With the extensive resources at its command, RAPIC is in a unique position to provide a comprehensive information base to the D and D community. DOE makes these services available to foster good public …
Date:
January 1, 1986
Creator:
Owen, P.T.
Object Type:
Article
System:
The UNT Digital Library
Policies and procedures of the Office of Technology Assessment : communication with Congress and the public
A manual for OTA employees, providing guidance for drafting proposals and reports. Includes standards and procedures for communicating with Congress.
Date:
February 1986
Creator:
United States. Office of Technology Assessment.
Object Type:
Book
System:
The UNT Digital Library
Mesorad dose assessment model. Volume 1. Technical basis
MESORAD is a dose assessment model for emergency response applications. Using release data for as many as 50 radionuclides, the model calculates: (1) external doses resulting from exposure to radiation emitted by radionuclides contained in elevated or deposited material; (2) internal dose commitment resulting from inhalation; and (3) total whole-body doses. External doses from airborne material are calculated using semi-infinite and finite cloud approximations. At each stage in model execution, the appropriate approximation is selected after considering the cloud dimensions. Atmospheric processes are represented in MESORAD by a combination of Lagrangian puff and Gaussian plume dispersion models, a source depletion (deposition velocity) dry deposition model, and a wet deposition model using washout coefficients based on precipitation rates.
Date:
March 1, 1986
Creator:
Scherpelz, R. I.; Bander, T. J.; Athey, G. F. & Ramsdell, J. V.
Object Type:
Report
System:
The UNT Digital Library
Comparison of methods applicable to evaluation of nuclear power plant technical specifications
The sample problem devised in this study is to calculate core damage frequencies for different allowed outage times (AOTs) from an accident sequence using the three methods: (1) static fault tree approach, (2) time-dependent unavailability analysis, and (3) Markov analysis. The results obtained in this study give useful insights and lend confidence to the conclusion that the static fault tree approach can be used by NRC for the AOT problem when the quantified higher level measures, e.g., core damage frequency and health risks, turn out to be unequivocally below the criteria (e.g., the safety goals). However, when the higher level measures corresponding to the proposed AOTs are in the range of the criteria, the Markov analysis or the time-dependent unavailability analysis would be attractive to owners of the plants who bear the burden of proof in AOT relaxation. 7 refs., 2 figs.
Date:
January 1, 1986
Creator:
Cho, N. Z.; Bozoki, G. E. & Youngblood, R. W.
Object Type:
Article
System:
The UNT Digital Library
Technical reference book for the Energy Economic Data Base Program (EEDB)
This distribution is the latest in a series published since 1978. The overall program purpose is to provide periodically updated, detailed base construction cost estimates for large nuclear electric operating plants. These data, which are representative of current US powerplant construction cost experience, are a useful contribution to program planning by the Office of the Assistant Secretary for Nuclear Energy. The eighth update incorporates the results of a comprehensive update of the technical and cost information for the pressurized water reactor (PWR), large scale prototype breeder reactor nuclear powerplant (LSPB), and 488 MWe high sulfur, coal-fired powerplant (HS5) data models. During the Phase VIII update, the LSPB, which was first incorporated into the previous update, was brought into full conformance with EEDB ground rules, and the level of detail of the data models was extended to the EEDB fully detailed level. We remind the user that the LSPB must still be considered a second-of-a-kind, pre-commercial unit, and any comparisons of it with other EEDB data models should be carefully made recognizing dissimilarity achievement of design and cost maturity, particularly for the nuclear steam supply system and other equipment.
Date:
December 1, 1986
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Mechanical Engineering Department technical abstracts for the period January-June 1985
None
Date:
January 1, 1986
Creator:
Woo, H.H. (ed.)
Object Type:
Report
System:
The UNT Digital Library
Waste Management Program. Technical progress report, July-December, 1984
This report provides information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, other support, in situ storage or disposal, waste form development and characterization, process and equipment development, and the Defense Waste Processing Facility are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations: tank farm operation, inspection program, burial ground operations, and waste transfer/tank replacement.
Date:
October 1, 1986
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Environmental Research Division technical progress report, January 1984-December 1985
Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter.
Date:
May 1, 1986
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Electromagnetic Compatibility and Interference Metrology
From abstract: The material included in this report is intended for a short course on electromagnetic compatibility/interference (EMC/EMI) metrology to be offered jointly by the staff of the Fields Characterization Group (723.03) and the Interference Characterization Group (723.04) of the Electromagnetic Fields Division (723). The purpose of this short course is to present a review of some of the radiated EMC/EMI measurement methods, to which the National Bureau of Standards (NBS) at Boulder, Colorado, has made significant contributions during the past two decades.
Date:
July 1986
Creator:
Ma, Mark T. & Kanda, M.
Object Type:
Report
System:
The UNT Digital Library
U.S. Access to Japanese Technical Literature: Electronics and Electrical Engineering, Selected Presentations, Volume 1
Abstract: On June 24-25, 1985, NBS and IEEE cosponsored a seminar at NBS to examine the need fox improved access to Japanese technical information and to explore possible app. aches to satisfy those needs. To limit the discussion to practical dimensions, the technical subject matter was restricted to electrical and electronics engineering. The program was designed to provide an opportunity for individuals representing Congress, the practicing engineering community, industry, and the educational community to voice their concerns and their needs. This proceedings volume contains selected presentations made at the seminar plus the visual aids used by each speaker.
Date:
January 1986
Creator:
Brady, Edward L.
Object Type:
Report
System:
The UNT Digital Library
Environmental Research Division Technical Progress Report: January 1984-December 1985
Report on technical progress in the various research and assessment activities of Argonne National Laboratory.
Date:
May 1986
Creator:
Beasley, T. M.
Object Type:
Report
System:
The UNT Digital Library