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Environmentally Assisted Cracking in Light Water Reactors - Annual Report, January-December 2001.

Description: This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from January to December 2001. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of austenitic stainless steels (SSs), (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic SSs, and (c) EAC of Alloy 600. The effects of key material and loading variables, such as strain amplitude, s… more
Date: June 1, 2003
Creator: Chopra, O. K.; Chung, H. M.; Clark, R. W.; Gruber, E. E; Hiller, R. W.; Shack, W. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimating Loss-of-Coolant Accident Frequencies for the Standardized Plant Analysis Risk Models

Description: The U.S. Nuclear Regulatory Commission maintains a set of risk models covering the U.S. commercial nuclear power plants. These standardized plant analysis risk (SPAR) models include several loss-of-coolant accident (LOCA) initiating events such as small (SLOCA), medium (MLOCA), and large (LLOCA). All of these events involve a loss of coolant inventory from the reactor coolant system. In order to maintain a level of consistency across these models, initiating event frequencies generally are base… more
Date: September 1, 2008
Creator: Eide, S. A.; Rasmuson, D. M. & Atwood, C. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Flooding Experiments and Modeling for Improved Reactor Safety

Description: Countercurrent two-phase flow and “flooding” phenomena in light water reactor systems are being investigated experimentally and analytically to improve reactor safety of current and future reactors. The aspects that will be better clarified are the effects of condensation and tube inclination on flooding in large diameter tubes. The current project aims to improve the level of understanding of flooding mechanisms and to develop an analysis model for more accurate evaluations of flooding in the … more
Date: September 14, 2008
Creator: Solmos, M., Hogan, K.J., VIerow, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Assessment of Crack Detection in Heavy-Walled Cast Stainless Steel Piping Welds Using Advanced Low-Frequency Ultrasonic Methods

Description: Studies conducted at the Pacific Northwest National Laboratory in Richland, Washington, have focused on assessing the effectiveness and reliability of novel approaches to nondestructive examination (NDE) for inspecting coarse-grained, cast stainless steel reactor components. The primary objective of this work is to provide information to the U.S. Nuclear Regulatory Commission on the effectiveness and reliability of advanced NDE methods as related to the inservice inspection of safety-related co… more
Date: March 1, 2007
Creator: Anderson, Michael T.; Crawford, Susan L.; Cumblidge, Stephen E.; Denslow, Kayte M.; Diaz, Aaron A. & Doctor, Steven R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Standardized Probabilistic Risk Assessment Models for Shutdown Operations Integrated in SPAR Level 1 Model

Description: Nuclear plant operating experience and several studies show that the risk from shutdown operation during Modes 4, 5, and 6 at pressurized water reactors and Modes 4 and 5 at boiling water reactors can be significant. This paper describes using the U.S. Nuclear Regulatory Commission’s full-power Standardized Plant Analysis Risk (SPAR) model as the starting point for development of risk evaluation models for commercial nuclear power plants. The shutdown models are integrated with their respective… more
Date: May 1, 2008
Creator: Khericha, S. T. & Mitman, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Proceedings of the USNRC/EPRI/ANL heated crevice seminar.

Description: An international Heated Crevice Seminar, sponsored by the Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Argonne National Laboratory, and the Electric Power Research Institute, was held at Argonne National Laboratory on October 7-11, 2002. The objective of the seminar was to provide a working forum for the exchange of information by contributing experts on current issues related to corrosion in heated crevices, particularly as it r… more
Date: August 31, 2003
Creator: Park, J. Y.; Fruzzetti, K.; Muscara, J.; Diercks, D. R.; Technology, Energy; EPRI et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Assessment of Fission Product Cross-Section Data for Burnup Credit Applications

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Environmentally Assisted Cracking in Light Water Reactors Annual Report January - December 2005.A

Description: This report summarizes work performed from January to December 2005 by Argonne National Laboratory on fatigue and environmentally assisted cracking in light water reactors (LWRs). Existing statistical models for estimating the fatigue life of carbon and low-alloy steels and austenitic stainless steels (SSs) as a function of material, loading, and environmental conditions were updated. Also, the ASME Code fatigue adjustment factors of 2 on stress and 20 on life were critically reviewed to assess… more
Date: August 31, 2007
Creator: Alexandreanu, B.; Chen, Y.; Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Shack, W. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Crack growth rates and metallographic examinations of Alloy 600 and Alloy 82/182 from field components and laboratory materials tested in PWR environments.

Description: In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C… more
Date: May 5, 2008
Creator: Alexandreanu, B.; Chopra, O. K. & Shack, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Computational Neutronics Methods and Transmutation Performance Analyses for Light Water Reactors

Description: The urgency for addressing repository impacts has grown in the past few years as a result of Spent Nuclear Fuel (SNF) accumulation from commercial nuclear power plants. One obvious path that has been explored by many is to eliminate the transuranic (TRU) inventory from the SNF thus reducing the need for additional long term repository storage sites. One strategy for achieving this is to burn the separated TRU elements in the currently operating U.S. Light Water Reactor (LWR) fleet. Many studies… more
Date: March 1, 2007
Creator: Asgari, M.; Forget, B.; Piet, S.; Ferrer, R. & Bays, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Multivariate Time Series Method for Monte Carlo Reactor Analysis

Description: A robust multivariate time series method has been established for the Monte Carlo calculation of neutron multiplication problems. The method is termed Coarse Mesh Projection Method (CMPM) and can be implemented using the coarse statistical bins for acquisition of nuclear fission source data. A novel aspect of CMPM is the combination of the general technical principle of projection pursuit in the signal processing discipline and the neutron multiplication eigenvalue problem in the nuclear engine… more
Date: August 14, 2008
Creator: Ueki, Taro
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data

Description: In the 1980s, a series of critical experiments referred to as the Haut Taux de Combustion (HTC) experiments was conducted by the Institut de Radioprotection et de Surete Nucleaire (IRSN) at the experimental criticality facility in Valduc, France. The plutonium-to- uranium ratio and the isotopic compositions of both the uranium and plutonium used in the simulated fuel rods were designed to be similar to what would be found in a typical pressurized-water reactor fuel assembly that initially had a… more
Date: September 1, 2008
Creator: Mueller, Don; Elam, Karla Riggle & Fox, Patricia B
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Influence of the In-Situ Clad Staining on the Corrosion of Zircaloy in PWR Water Environment

Description: Zircaloy cladding tubes strain in-situ during service life in the corrosive environment of a Pressurized Water Reactor for a variety of reasons. First, the tube undergoes stress free growth due to the preferential alignment of irradiation induced vacancy loops on basal planes. Positive strains develop in the textured tubes along prism orientations while negative strains develop along basal orientations (Reference (a)). Second, early in life, free standing tubes will often shrink by creep in the… more
Date: June 21, 2001
Creator: Kammenzind, B.F., Eklund, K.L. and Bajaj, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Field Evaluations of Low-Frequency SAFT-UT on Cast Stainless Steel and Dissimilar Metal Weld Components

Description: This report documents work performed at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington, and at the Electric Power Research Institute's (EPRI) Nondestructive Examination (NDE) Center in Charlotte, North Carolina, on evalutating a low frequency ultrasonic inspection technique used for examination of cast stainless steel (CSS) and dissimilar metal (DMW) reactor piping components. The technique uses a zone-focused, multi-incident angle, low frequency (250-450 kHz) inspecti… more
Date: November 1, 2008
Creator: Diaz, Aaron A.; Harris, R. V. & Doctor, Steven R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Program for the Inspection of Nickel Alloy Components Report from the Program’s Steering Committee: Inspection of Bottom-Mounted Instrumentation Nozzles Round Robin

Description: The U.S. Nuclear Regulatory Commission (NRC) executed agreements with organizations in Japan, Sweden, South Korea, Finland, and the United States to establish the Program for the Inspection of Nickel Alloy Components (PINC).
Date: November 13, 2009
Creator: Cumblidge, Stephen E.; Heasler, Patrick G.; Doctor, Steven R. & Taylor, Theodore T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility of Recycling Plutonium and Minor Actinides in Light Water Reactors Using Hydride Fuel

Description: The objective of this DOE NERI program sponsored project was to assess the feasibility of improving the plutonium (Pu) and minor actinide (MA) recycling capabilities of pressurized water reactors (PWRs) by using hydride instead of oxide fuels. There are four general parts to this assessment: 1) Identifying promising hydride fuel assembly designs for recycling Pu and MAs in PWRs 2) Performing a comprehensive systems analysis that compares the fuel cycle characteristics of Pu and MA recycling in … more
Date: March 10, 2009
Creator: Greenspan, Ehud; Todreas, Neil & Taiwo, Temitope
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Letter Report, An Evaluation of Ultrasonic Phased Array Testing for Reactor Piping System Components Containing Dissimilar Metal Welds, JCN N6398, Task 2A

Description: Research is being conducted for the U.S. Nuclear Regulatory Commission at the Pacific Northwest National Laboratory to assess the effectiveness and reliability of advanced nondestructive examination (NDE) methods for the inspection of light-water reactor components. The scope of this research encom¬passes primary system pressure boundary materials including dissimilar metal welds (DMWs), cast austenitic stainless steels (CASS), piping with corrosion-resistant cladding, weld overlays, inlays and… more
Date: November 30, 2009
Creator: Diaz, Aaron A.; Cinson, Anthony D.; Crawford, Susan L. & Anderson, Michael T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis and Measurement of Bubble Dynamics and Associated Flow Field in Subcooled Nucleate Boiling Flows

Description: In recent years, subooled nucleate boiling (SNB) has attrcted expanding research interest owing to the emergence of axial offset anomaly (AOA) or crud-induced power shigt (CIPS) in many operating US PWRs, which is an unexpected deviation in the core axial power distribution from the predicted power curves. Research indicates that the formation of the crud, which directly leads to AOA phenomena, results from the presence of the subcooled nucleate boiling, and is especially realted to bubble moti… more
Date: October 1, 2008
Creator: Jones, Barclay G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transmutation Performance Analysis for Inert Matrix Fuels in Light Water Reactors and Computational Neutronics Methods Capabilities at INL

Description: The urgency for addressing repository impacts has grown in the past few years as a result of Spent Nuclear Fuel (SNF) accumulation from commercial nuclear power plants. One path that has been explored by many is to eliminate the transuranic (TRU) inventory from the SNF, thus reducing the need for additional long term repository storage sites. One strategy for achieving this is to burn the separated TRU elements in the currently operating U.S. Light Water Reactor (LWR) fleet. Many studies have e… more
Date: May 1, 2009
Creator: Pope, Michael A.; Bays, Samuel E.; Piet, S.; Ferrer, R.; Asgari, Mehdi & Forget, Benoit
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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India's Worsening Uranium Shortage

Description: As a result of NSG restrictions, India cannot import the natural uranium required to fuel its Pressurized Heavy Water Reactors (PHWRs); consequently, it is forced to rely on the expediency of domestic uranium production. However, domestic production from mines and byproduct sources has not kept pace with demand from commercial reactors. This shortage has been officially confirmed by the Indian Planning Commission’s Mid-Term Appraisal of the country’s current Five Year Plan. The report stresses … more
Date: January 15, 2007
Creator: Curtis, Michael M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RELAP5-3D Code for Supercritical-Pressure Light-Water-Cooled Reactors

Description: The RELAP5-3D computer program has been improved for analysis of supercritical-pressure, light-water-cooled reactors. Several code modifications were implemented to correct code execution failures. Changes were made to the steam table generation, steam table interpolation, metastable states, interfacial heat transfer coefficients, and transport properties (viscosity and thermal conductivity). The code modifications now allow the code to run slow transients above the critical pressure as well as… more
Date: April 1, 2003
Creator: Riemke, Richard Allan; Davis, Cliff Bybee & Schultz, Richard Raphael
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A High Temperature, non-TRISO Fuel and Clad Design with Commercial-Grade Enrichment for the Prismatic Block Very High Temperature Reactor

Description: The prismatic block Very High Temperature Reactor (VHTR) is a leading Generation IV reactor concept. This reactor with its relatively low core power density and large graphite mass currently satisfies the fundamental goals of the Generation IV charter. However, modifications can be made to the fuel and clad design, such that (1) VHTR uranium enrichment can be lowered to near commercial-grade pressurized water reactor (PWR) enrichments, (2) fuel burnups are extended, and (3) the thermal safety m… more
Date: November 1, 2005
Creator: Sterbentz, James W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Margin for In-Vessel Retention in the APR1400 - VESTA and SCDAP/RELAP5-3D Analyses

Description: If cooling is inadequate during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the lower head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with such plants can reduce concerns about containment failure and associated risk. For example, the enhanced safe… more
Date: December 1, 2004
Creator: Rempe, Joy & Knudson, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Crack growth rates of nickel alloy welds in a PWR environment.

Description: In light water reactors (LWRs), vessel internal components made of nickel-base alloys are susceptible to environmentally assisted cracking. A better understanding of the causes and mechanisms of this cracking may permit less conservative estimates of damage accumulation and requirements on inspection intervals. A program is being conducted at Argonne National Laboratory to evaluate the resistance of Ni alloys and their welds to environmentally assisted cracking in simulated LWR coolant environm… more
Date: May 31, 2006
Creator: Alexandreanu, B.; Chopra, O. K.; Shack, W. J. & Technology, Energy
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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