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Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Furth… more

Date: August 1, 2007

Creator: Kisner, Roger A; Mullens, James Allen; Wilson, Thomas L; Wood, Richard Thomas; Korsah, Kofi; Qualls, A L et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Data Compilation for AGR-3/4 Designed-to-Fail (DTF) Fuel Particle Batch LEU04-02DTF

This document is a compilation of coating and characterization data for the AGR-3/4 designed-to-fail (DTF) particles. The DTF coating is a high density, high anisotropy pyrocarbon coating of nominal 20 {micro}m thickness that is deposited directly on the kernel. The purpose of this coating is to fail early in the irradiation, resulting in a controlled release of fission products which can be analyzed to provide data on fission product transport. A small number of DTF particles will be included … more

Date: October 1, 2008

Creator: Hunn, John D & Miller, James Henry

Item Type: Report

Partner: UNT Libraries Government Documents Department

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A Physically Based Correlation of Irradiation-Induced Transition Temperature Shifts for RPV Steels

The reactor pressure vessels (RPVs) of commercial nuclear power plants are subject to embrittlement due to exposure to high-energy neutrons from the core, which causes changes in material toughness properties that increase with radiation exposure and are affected by many variables. Irradiation embrittlement of RPV beltline materials is currently evaluated using Regulatory Guide 1.99 Revision 2 (RG1.99/2), which presents methods for estimating the shift in Charpy transition temperature at 30 ft-… more

Date: November 1, 2007

Creator: Eason, Ernest D.; Odette, George Robert; Nanstad, Randy K & Yamamoto, Takuya

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs

Here we report the outcome of the application of the Nuclear Regulatory Commission (NRC) Phenomena Identification and Ranking Table (PIRT) process to the issue of nuclear-grade graphite for the moderator and structural components of a next generation nuclear plant (NGNP), considering both routine (normal operation) and postulated accident conditions for the NGNP. The NGNP is assumed to be a modular high-temperature gas-cooled reactor (HTGR), either a gas-turbine modular helium reactor (GTMHR) v… more

Date: March 1, 2008

Creator: Burchell, Timothy D; Bratton, Rob; Marsden, Barry; Srinivasan, Makuteswara; Penfield, Scott; Mitchell, Mark et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Reliability of Current Biokinetic and Dosimetric Models for Radionuclides: A Pilot Study

This report describes the results of a pilot study of the reliability of the biokinetic and dosimetric models currently used by the U.S. Nuclear Regulatory Commission (NRC) as predictors of dose per unit internal or external exposure to radionuclides. The study examines the feasibility of critically evaluating the accuracy of these models for a comprehensive set of radionuclides of concern to the NRC. Each critical evaluation would include: identification of discrepancies between the models and… more

Date: October 1, 2008

Creator: Leggett, Richard Wayne; Eckerman, Keith F & Meck, Robert A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel

The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform postclosure criticality calculations. The validation process applies the criticality analysis methodology approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report. The application systems for this validation consist of waste packages containing transpor… more

Date: October 1, 2007

Creator: Radulescu, Georgeta; Mueller, Don; Goluoglu, Sedat; Hollenbach, Daniel F & Fox, Patricia B

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Final Report - Assessment of Potential Phosphate Ion-Cementitious Materials Interactions

The objectives of this limited study were to: (1) review the potential for degradation of cementitious materials due to exposure to high concentrations of phosphate ions; (2) provide an improved understanding of any significant factors that may lead to a requirement to establish exposure limits for concrete structures exposed to soils or ground waters containing high levels of phosphate ions; (3) recommend, as appropriate, whether a limitation on phosphate ion concentration in soils or ground w… more

Date: June 1, 2007

Creator: Naus, Dan J; Mattus, Catherine H & Dole, Leslie Robert

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Assessment of Fission Product Cross-Section Data for Burnup Credit Applications

Past efforts by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), the Nuclear Regulatory Commission (NRC), and others have provided sufficient technical information to enable the NRC to issue regulatory guidance for implementation of pressurized-water reactor (PWR) burnup credit; however, consideration of only the reactivity change due to the major actinides is recommended in the guidance. Moreover, DOE, NRC, and EPRI have noted the need for additional scientific and… more

Date: December 1, 2007

Creator: Leal, Luiz C.; Derrien, Herve; Dunn, Michael E. & Mueller, Don

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Validation Testing of Hydrogen Generation Technology

This report describes the results of testing performed by ORNL for Photech Energies, Inc. The objective of the testing was to evaluate the efficacy of Photech's hydrogen generation reactor technology, which produces gaseous hydrogen through electrolysis. Photech provided several prototypes of their proprietary reactor for testing and the ancillary equipment, such as power supplies and electrolyte solutions, required for proper operation of the reactors. ORNL measured the production of hydrogen … more

Date: December 1, 2007

Creator: Smith, Barton & Toops, Todd J

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Scoping Study on the Safety Impact of Valve Spacing in Natural Gas Pipelines

The U.S. Department of Transportation's Pipeline and Hazardous Materials Safety Administration (PHMSA) is responsible for ensuring the safe, reliable, and environmentally sound operation of the nation's natural gas and hazardous liquid pipelines. Regulations adopted by PHMSA for gas pipelines are provided in 49 CFR 192, and spacing requirements for valves in gas transmission pipelines are presented in 49 CFR 192.179. The present report describes the findings of a scoping study conducted by Oak … more

Date: July 1, 2007

Creator: Sulfredge, Charles David

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Prediction of External Corrosion for Steel Cylinders--2007 Report

Depleted uranium hexafluoride (DUF{sub 6}) is stored in over 62,000 containment cylinders at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and at the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. Over 4,800 of the cylinders at Portsmouth were recently moved there from the East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. The cylinders range in age up to 56 years and come in various models, but most are 48-inch diameter 'thin-wall'(312.5 mil) and… more

Date: January 1, 2008

Creator: Schmoyer, Richard L

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Requirements Definition for ORNL Trusted Corridors Project

The ORNL Trusted Corridors Project has several other names: SensorNet Transportation Pilot; Identification and Monitoring of Radiation (in commerce) Shipments (IMR(ic)S); and Southeastern Transportation Corridor Pilot (SETCP). The project involves acquisition and analysis of transportation data at two mobile and three fixed inspection stations in five states (Kentucky, Mississippi, South Carolina, Tennessee, and Washington DC). Collaborators include the State Police organizations that are respo… more

Date: February 1, 2008

Creator: Walker, Randy M; Hill, David E; Smith, Cyrus M; DeNap, Frank A; White, James D; Gross, Ian G et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Prototype Weigh-In-Motion Performance

Oak Ridge National Laboratory (ORNL) has developed and patented methods to weigh slowly moving vehicles. We have used this technology to produce a portable weigh-in-motion system that is robust and accurate. This report documents the performance of the second-generation portable weigh-in-motion prototype (WIM Gen II). The results of three modes of weight determination are compared in this report: WIM Gen II dynamic mode, WIM Gen II stop-and-go mode, and static (parked) mode on in-ground, static… more

Date: October 1, 2006

Creator: Abercrombie, Robert K; Beshears, David L; Hively, Lee M; Scudiere, Matthew B & Sheldon, Frederick T

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Prognostic Analysis of the Tactical Quiet Generator

The U.S. Army needs prognostic analysis of mission-critical equipment to enable condition-based maintenance before failure. ORNL has developed and patented prognostic technology that quantifies condition change from noisy, multi-channel, time-serial data. This report describes an initial application of ORNL's prognostic technology to the Army's Tactical Quiet Generator (TQG), which is designed to operate continuously at 10 kW. Less-than-full power operation causes unburned fuel to accumulate on… more

Date: September 1, 2008

Creator: Hively, Lee M

Item Type: Report

Partner: UNT Libraries Government Documents Department

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High Strain Rate Tensile Testing of DOP-26 Iridium

The iridium alloy DOP-26 was developed through the Radioisotope Power Systems Program in the Office of Nuclear Energy of the Department of Energy. It is used for clad vent set cups containing radioactive fuel in radioisotope thermoelectric generator (RTG) heat sources which provide electric power for spacecraft. This report describes mechanical testing results for DOP-26. Specimens were given a vacuum recrystallization anneal of 1 hour at 1375 C and tested in tension in orientations parallel an… more

Date: November 1, 2007

Creator: Schneibel, Joachim H; Carmichael Jr, Cecil Albert & George, Easo P

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors

The objective of this study was to provide a primer on the environmental effects that can affect the durability of nuclear power plant concrete structures. As concrete ages, changes in its properties will occur as a result of continuing microstructural changes (i.e., slow hydration, crystallization of amorphous constituents, and reactions between cement paste and aggregates), as well as environmental influences. These changes do not have to be detrimental to the point that concrete will not be … more

Date: February 1, 2007

Creator: Naus, Dan J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Next Generation Nuclear Plant GAP Analysis Report

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event prob… more

Date: December 1, 2008

Creator: Ball, Sydney J; Burchell, Timothy D; Corwin, William R; Fisher, Stephen Eugene; Forsberg, Charles W.; Morris, Robert Noel et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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INERI-2006-003-F FY07 Annual Report

Project Title: Comparison of Characterization Methods for Anisotropy and Microstructure of TRISO Particle Layers This INERI was created to support a comparative study between the newly developed two modulator generalized ellipsometry microscope (2-MGEM) at the Oak Ridge National Laboratory (ORNL) and the more traditional optical polarimeter (RAPAX) at the Commissariat l' nergie Atomique (CEA). These two systems are used to measure the anisotropy of the pyrocarbon layers in tri-isotropic (TRISO)… more

Date: October 1, 2007

Creator: Hunn, John D

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Data Compilation for AGR-3/4 Driver Particle Composite LEU03-09T

This document is a compilation of characterization data for the AGR-3/4 driver fuel coated particle composite LEU03-09T, a composite of four batches of TRISO-coated, nominally 350 {micro}m diameter, 19.7% low enrichment uranium oxide/uranium carbide kernels (LEUCO). The AGR-3/4 driver fuel particles were fabricated using the AGR-1 baseline coating conditions and consist of a spherical kernel coated with an {approx}50% dense carbon buffer layer (100 {micro}m nominal thickness) followed by a dens… more

Date: March 1, 2007

Creator: Hunn, John D & Lowden, Richard Andrew

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Behavior of Aqueous Electrolytes in Steam Cycles - The Final Report on the Solubility and Volatility of copper(I) and Copper(II) Oxides

Measurements were completed on the solubility of cupric and cuprous oxides in liquid water and steam at controlled pH conditions from 25 to 400 C (77 to 752 F). The results of this study have been combined with those reported from this laboratory in two previous EPRI reports to provide a complete description of the solubility of these oxides and the speciation of copper dissolved in liquid water and steam as a function of oxidation state, temperature, pH, and in the case of steam, pressure. The… more

Date: May 1, 2004

Creator: Palmer, Donald; Benezeth, Pascale & Simonson, J Michael {Mike}

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Characterization of Min-K TE-1400 Thermal Insulation

Min-K 1400TE insulation material was characterized at Oak Ridge National Laboratory for use in structural applications under gradient temperature conditions. Initial compression testing was performed at room temperature at various loading rates ranging between 5 and 500 psi/hour (≈35 and 3500 kPa/hour) to determine the effect of sample size and test specimen geometry on the compressive strength of Min-K. To determine the loading rates that would be used for stress relaxation testing, comp… more

Date: July 1, 2008

Creator: Hemrick, James Gordon; Lara-Curzio, Edgar & King, James

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 6: Process Heat and Hydrogen Co-Generation PIRTs

A Phenomena Identification and Ranking Table (PIRT) exercise was conducted to identify potential safety-0-related physical phenomena for the Next Generation Nuclear Plant (NGNP) when coupled to a hydrogen production or similar chemical plant. The NGNP is a very high-temperature reactor (VHTR) with the design goal to produce high-temperature heat and electricity for nearby chemical plants. Because high-temperature heat can only be transported limited distances, the two plants will be close to ea… more

Date: March 1, 2008

Creator: Forsberg, Charles W; Gorensek, M. B.; Herring, S. & Pickard, P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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A Preliminary Analysis of the Economics of Using Distributed Energy as a Source of Reactive Power Supply

A major blackout affecting 50 million people in the Northeast United States, where insufficient reactive power supply was an issue, and an increased number of filings made to the Federal Energy Regulatory Commission by generators for reactive power has led to a closer look at reactive power supply and compensation. The Northeastern Massachusetts region is one such area where there is an insufficiency in reactive power compensation. Distributed energy due to its close proximity to loads seems to… more

Date: April 1, 2006

Creator: Li, Fangxing; Kueck, John D; Rizy, D Tom & King, Thomas F

Item Type: Report

Partner: UNT Libraries Government Documents Department

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POPULATION DISTRIBUTION DURING THE DAY

Population distribution during the day can be defined as distribution of population in an area during the daytime hours. However, a precise definition of daytime hours is challenging given the geographic variability in the length of a day or daylight hours. The US Census Bureau used "normal business hours" as the span of time to describe daytime population. Given that Censuses typically estimates residential population, it represents a nighttime population distribution. In that respect, daytime… more

Date: January 1, 2008

Creator: Bhaduri, Budhendra L.

Item Type: Book

Partner: UNT Libraries Government Documents Department