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Status of Special Reactor Process Tube Loadings

Description: The pages of the report show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.
Date: July 12, 1966
Creator: Walton, R. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Douglas United Nuclear, Inc., sponsored research and development programs, FY-1967

Description: Douglas United Nuclear, Inc., has allocated to the Pacific Northwest Laboratory $542,000 of 02 Research and Development funds and $455,000 of Process Technology funds for FY-1967. Of these, $392,000 of 02 Research and Development funds and $420,000 of Process Technology funds are the responsibility of the Research and Engineering Section. The balance in each case is the responsibility of the Production Fuels Section. Representatives of these Sections have met with Pacific Northwest Laboratory p… more
Date: July 12, 1966
Creator: Reid, R. W. & Stringer, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TWODANT benchmark. Progress report

Description: TWODANT (Two-Dimensional, Diffusion-Accelerated, Neutral-Particle Transport) code has been benchmarked against 6 critical experiments (Jezebel plutonium critical assembly) and their k effective values compared with those of KENO and MCNP codes.
Date: January 11, 1994
Creator: Lee, Sung
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Data processing unit and power system for the LANL REM instrument package. Final report

Description: The NEPSTP spacecraft needs highly reliable instrumentation to measure the nuclear reactor health and performance. These reactor measurements are essential for initial on-orbit phase operations and documentation of performance over time. Los Alamos National Laboratory (LANL), under the guidance of W. C. Feldman, principal investigator, has designed the Radiation Environment Monitoring (REM) package to meet these needs. The instrumentation package contains two neutron detectors, one gamma-ray de… more
Date: March 1994
Creator: Lockhart, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A three-dimensional transient neutronics routine for the TRAC-PF1 reactor thermal hydraulic computer code

Description: No present light water reactor accident analysis code employs both high state of the art neutronics and thermal-hydraulics computational algorithms. Adding a modern three-dimensional neutron kinetics model to the present TRAC-PFI/MOD2 code would create a fully up to date pressurized water reactor accident evaluation code. After reviewing several options, it was decided that the Nodal Expansion Method would best provide the basis for this multidimensional transient neutronic analysis capability.… more
Date: May 1, 1990
Creator: Bandini, B.R.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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L-Lake macroinvertebrate community

Description: To characterize the present benthic macroinvertebrate community of L-Lake, Regions 5 and 7 of the reservoir were sampled in September 1995 at the same locations sampled in 1988 and 1989 during the L-Lake monitoring program. The macroinvertebrate community of 1995 is compared to that of 1988 and 1989. The species composition of L-Lake`s macroinvertebrate community has changed considerably since 1988-1989, due primarily to maturation of the reservoir ecosystem. L-Lake contains a reasonably divers… more
Date: June 1996
Creator: Specht, Winona L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results of submerged sediment core sampling and analysis on Par Pond, Pond C, and L Lake: July 1995

Description: Sediment cores from shallow and deep water locations in Par Pond, Pond C, and L Lake were collected and analyzed in 1995 for radioactive and nonradioactive constituents. This core analysis was conducted to develop a defensible characterization of contaminants found in the sediments of Par Pond, Pond C, and L Lake. Mercury was the only nonradiological constituent with a nonestimated quantity that was detected above the U.S Environmental Protection Agency Region IV potential contaminants of conce… more
Date: June 1996
Creator: Koch, J. W., II; Martin, F. D. & Friday, G. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental observations of the breakup of multiple metal jets in a volatile liquid

Description: A postulated severe loss of coolant accident in a nuclear reactor can lead to significant core damage due to residual heat generation. Subsequently, melted core materials (i.e.; corium) could migrate downward and impinge upon the lower head of the reactor pressure vessel (RPV). During this relocation, the complexity of the reactor structure could segregate the molten corium into various flow paths. A perforated flow plate could readily provide the mechanism to segregate the molten corium. The r… more
Date: July 1, 1995
Creator: Marciniak, M.J.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

Description: This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quanti… more
Date: June 1996
Creator: Gates, R.; Glukhov, A. & Markowski, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review guidelines on software languages for use in nuclear power plant safety systems. Final report

Description: Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada, C/C++, Programmable Logic Controller (PLC) Ladder Logic, International Electrotechnical Commission (IEC) Standard 11… more
Date: June 1996
Creator: Hecht, H.; Hecht, M.; Graff, S.; Green, W.; Lin, D.; Koch, S. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electricity Market Module: Electricity finance and pricing submodule

Description: The purpose of this report is to document the updates to the Electricity Financial Pricing Module (EFP) to reflect the rate impacts of nuclear decommissioning. The EFP is part of the National Energy Modeling System (NEMS). The updates to the EFP related to nuclear decommissioning include both changes to the underlying data base and the methodology. Nuclear decommissioning refers to the activities performed to take a nuclear plant permanently out of service. The costs of nuclear decommissioning … more
Date: June 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Regulatory and technical reports (abstract index journal): Compilation for first quarter 1996, January--March. Volume 21, Number 1

Description: This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceedings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.
Date: June 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Hydrogen Depletion Using a Scaled Passive Autocatalytic Recombiner

Description: Hydrogen depletion tests of a scaled passive autocatalytic recombine (pAR) were performed in the Surtsey test vessel at Sandia National Laboratories (SNL). The experiments were used to determine the hydrogen depletion rate of a PAR in the presence of steam and also to evaluate the effect of scale (number of cartridges) on the PAR performance at both low and high hydrogen concentrations.
Date: October 28, 1998
Creator: Blanchat, Thomas K. & Malliakos, Asimios
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of a J-estimation scheme for internal circumferential and axial surface cracks in elbows

Description: This report summarizes efforts to develop elastic and elastic-plastic fracture mechanics analyses for internal surface cracks in elbows. The analyses involved development of a GE/EPRI type J-estimation scheme which requires an elastic and fully plastic contribution to crack-driving force in terms of the J-integral parameter. The elastic analyses require the development of F-function values to relate the J{sub e} term to applied loads. Similarly, the fully plastic analyses require the developmen… more
Date: June 1996
Creator: Mohan, R.; Brust, F.W.; Ghadiali, N. & Wilkowski, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dose commitments due to radioactive releases from nuclear power plant sites: Methodology and data base. Supplement 1

Description: This manual describes a dose assessment system used to estimate the population or collective dose commitments received via both airborne and waterborne pathways by persons living within a 2- to 80-kilometer region of a commercial operating power reactor for a specific year of effluent releases. Computer programs, data files, and utility routines are included which can be used in conjunction with an IBM or compatible personal computer to produce the required dose commitments and their statistica… more
Date: June 1996
Creator: Baker, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Human-system interface design review guideline -- Reviewer`s checklist: Final report. Revision 1, Volume 2

Description: NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidan… more
Date: June 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modeling patterns in data using linear and related models

Description: This report considers the use of linear models for analyzing data related to reliability and safety issues of the type usually associated with nuclear power plants. The report discusses some of the general results of linear regression analysis, such as the model assumptions and properties of the estimators of the parameters. The results are motivated with examples of operational data. Results about the important case of a linear regression model with one covariate are covered in detail. This ca… more
Date: June 1996
Creator: Engelhardt, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Risk-based maintenance modeling. Prioritization of maintenance importances and quantification of maintenance effectiveness

Description: This report describes methods for prioritizing the risk importances of maintenances using a Probabilistic Risk Assessment (PRA). Approaches then are described for quantifying their reliability and risk effects. Two different PRA importance measures, minimal cutset importances and risk reduction importances, were used to prioritize maintenances; the findings show that both give similar results if appropriate criteria are used. The justifications for the particular importance measures also are de… more
Date: September 1995
Creator: Vesely, W. E. & Rezos, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear reactors built, being built, or planned, 1994

Description: This document contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1994. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US … more
Date: July 1995
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Summary of results. Volume 1

Description: During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to examine the potential risks during low power and shutdown operations. Two plants, Surry and Grand Gulf, were selected as the plants to be studied by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). This report documents the work performed during the analysis of the Grand Gulf plant. A phased approach was used for the overall study. In Phase 1, the objectives were to identif… more
Date: July 1995
Creator: Whitehead, D. W.; Staple, B. D. & Daniel, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Adequacy of the 123-group cross-section library for criticality analyses of water-moderated uranium systems

Description: In a recent criticality analysis for an array of water-moderated packages containing highly enriched uranium, the 123-group cross-section library in the SCALE system was observed to have a nonconservative discrepancy of approximately 3 to 3.5% when compared with more recently developed libraries. A simple representative system of UO{sub 2}F{sub 2}-H{sub 2}O was used to identify that the problem results from a lack of resonance data for {sup 235}U. Only a single set of self-shielded cross sectio… more
Date: August 1995
Creator: Parks, C. V.; Wright, R. Q. & Jordan, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface interactions of cesium and boric acid with stainless steel

Description: In this report, the effects of cesium hydroxide and boric acid on oxidized stainless steel surfaces at high temperatures and near one atmosphere of pressure are investigated. This is the first experimental investigation of this chemical system. The experimental investigations were performed using a mass spectrometer and a mass electrobalance. Surfaces from the different experiments were examined using a scanning electron microscope to identify the presence of deposited species, and electron spe… more
Date: August 1995
Creator: Grossman-Canfield, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Assessment of the IVA3 code for multifield flow simulation. Formal report

Description: This report presents an assessment of the IVA3 computer code for multifield flow simulation, as applied to the premixing phase of a hypothetical steam explosion in a water-cooled power reactor. The first section of this report reviews the derivation of the basic partial differential equations of multifield modeling, with reference to standard practices in the multiphase flow literature. Basic underlying assumptions and approximations are highlighted, and comparison is made between IVA3 and othe… more
Date: July 1995
Creator: Stewart, H. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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