Sustaining the Landscape: A Method for Comparing Current and Desired Future Conditions of Forest Ecosystems in the North Cumberland Plateau and Mountains (open access)

Sustaining the Landscape: A Method for Comparing Current and Desired Future Conditions of Forest Ecosystems in the North Cumberland Plateau and Mountains

This project initiates an integrated-landscape conservation approach within the Northern Cumberlands Project Area in Tennessee and Kentucky. The mixed mesophytic forests within the Cumberland Plateau and Mountains are among the most diverse in North America; however, these forests have been impacted by and remain threatened from changes in land use across this landscape. The integrated-landscape conservation approach presented in this report outlines a sequence of six conservation steps. This report considers the first three of these steps in two, successive stages. Stage 1 compares desired future conditions (DFCs) and current prevailing conditions (CPCs) at the landscape-scale utilizing remote sensing imagery, remnant forests, and descriptions of historical forest types within the Cumberland Plateau. Subsequently, Stage 2 compares DFCs and CPCs for at-risk forest types identified in Stage 1 utilizing structural, compositional, or functional attributes from USFS Forest Inventory and Analysis data. Ecological indicators will be developed from each stage that express the gaps between these two realizations of the landscape. The results from these first three steps will directly contribute to the final three steps of the integrated-landscape conservation approach by providing guidance for the generation of new conservation strategies in the Northern Cumberland Plateau and Mountains.
Date: December 22, 2004
Creator: Druckenbrod, D. L.
System: The UNT Digital Library
Ultrasonic Examination of Double-Shell Tank 241-SY-101. Examination Completed March 2004. (open access)

Ultrasonic Examination of Double-Shell Tank 241-SY-101. Examination Completed March 2004.

COGEMA Engineering Corporation (COGEMA), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic nondestructive examination of selected portions of Double-Shell Tank 241-SY-101. The purpose of this examination was to provide information that could be used to evaluate the integrity of the wall of the primary tank. The requirements for the ultrasonic examination of Tank 241-SY-101 were to detect, characterize (identify, size, and locate), and record measurements made of any wall thinning, pitting, or cracks that might be present in the wall of the primary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plan (ETP), RPP-17750 (Jensen 2003) and summarized on page 1 of this document, are reported to CH2M Hill and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M Hill, all data is to be recorded on disk and paper copies of all measurements are provided to PNNL for third-party evaluation. PNNL is responsible for preparing a report that describes the results of the COGEMA ultrasonic examinations.
Date: July 22, 2004
Creator: Pardini, Allan F. & Posakony, Gerald J.
System: The UNT Digital Library
Design of a 2 Slot VLPC Cryostat Cooled by a Cryocooler (open access)

Design of a 2 Slot VLPC Cryostat Cooled by a Cryocooler

The conceptual design and preliminary engineering calculations have been completed for a two cassette cryostat. This report summarizes the design. A cryocooler is permanently mounted in the center of a stainless steel, 0.75 inch thick top lid. The cryocooler sits upon a spacer which raises the cooling stage elevations to favorably match the cassette heat intercept elevations. The top lid (32.0-inch outside diameter) mates to a 24-inch pipe size flange with o-ring. The 24-inch pipe size vacuum vessel with end plate has a minimum internal depth of 16-inch to give adequate clearance for the depth of the cryocooler and multilayer insulation blankets. Support stand legs elevate the container to a convenient height and allow for placement of the AFE power supply underneath. Two cassette slots are located on either side of the cryocooler. The slots are positioned parallel to each other, 10.5-inch center to center (6 standard cassette slot widths) so that the standard 8 slot AFE backplane can be used. The slot opening through the lid is approximately 1.422-inch x 16.782-inch. A 0.016-inch thick titanium (Ti-6AI-4V) envelope with sealing lip is inserted through lid and defines the gas helium boundary that the VLPC cassette resides. The internal dimensions of …
Date: April 22, 2004
Creator: Rucinski, Russell A.
System: The UNT Digital Library
Whole-Core Depletion Studies in Support of Fuel Specification for the Nextgeneration Nuclear Plant (NGNP) Core. (open access)

Whole-Core Depletion Studies in Support of Fuel Specification for the Nextgeneration Nuclear Plant (NGNP) Core.

None
Date: November 22, 2004
Creator: Kim, T. K.; Yang, W. S.; Taiwo, T. A. & Khalil, H. S.
System: The UNT Digital Library
Modeling Production Plant Forming Processes (open access)

Modeling Production Plant Forming Processes

Engineering has simulation tools and experience in modeling forming processes. Y-12 personnel have expressed interest in validating our tools and experience against their manufacturing process activities such as rolling, casting, and forging etc. We have demonstrated numerical capabilities in a collaborative DOE/OIT project with ALCOA that is nearing successful completion. The goal was to use ALE3D to model Alcoa's slab rolling process in order to demonstrate a computational tool that would allow Alcoa to define a rolling schedule that would minimize the probability of ingot fracture, thus reducing waste and energy consumption. It is intended to lead to long-term collaboration with Y-12 and perhaps involvement with other components of the weapons production complex. Using simulations to aid in design of forming processes can: decrease time to production; reduce forming trials and associated expenses; and guide development of products with greater uniformity and less scrap.
Date: September 22, 2004
Creator: Rhee, M; Becker, R; Couch, R & Li, M
System: The UNT Digital Library
Demonstration of Smart Building Controls to Manage Building Peak Loads: Innovative Non-Wires Technologies (open access)

Demonstration of Smart Building Controls to Manage Building Peak Loads: Innovative Non-Wires Technologies

As a part of the non-wires solutions effort, BPA in partnership with Pacific Northwest National Laboratory (PNNL) is exploring the use of two distributed energy resources (DER) technologies in the City of Richland. In addition to demonstrating the usefulness of the two DER technologies in providing peak demand relief, evaluation of remote direct load control (DLC) is also one of the primary objectives of this demonstration. The concept of DLC, which is used to change the energy use profile during peak hours of the day, is not new. Many utilities have had success in reducing demand at peak times to avoid building new generation. It is not the need for increased generation that is driving the use of direct load control in the Northwest, but the desire to avoid building additional transmission capacity. The peak times at issue total between 50 and 100 hours a year. A transmission solution to the problem would cost tens of millions of dollars . And since a ?non wires? solution is just as effective and yet costs much less, the capital dollars for construction can be used elsewhere on the grid where building new transmission is the only alternative. If by using DLC, the …
Date: December 22, 2004
Creator: Katipamula, Srinivas & Hatley, Darrel D.
System: The UNT Digital Library
Shared Communications: Volume 2. In-Depth Systems Research (open access)

Shared Communications: Volume 2. In-Depth Systems Research

This report is the second of two documents that examine the literature for actual examples of organizations and agencies that share communications resources. While the primary emphasis is on rural, intelligent transportation system (ITS) communications involving transit, examples will not be limited to rural activities, nor to ITS implementation, nor even to transit. In addition, the term ''communication'' will be broadly applied to include all information resources. The first document of this series, ''Shared Communications: Volume I. A Summary and Literature Review'', defines the meaning of the term ''shared communication resources'' and provides many examples of agencies that share resources. This document, ''Shared Communications: Volume II. In-Depth Systems Research'', reviews attributes that contributed to successful applications of the sharing communication resources concept. A few examples of each type of communication sharing are provided. Based on the issues and best practice realworld examples, recommendations for potential usage and recommended approaches for field operational tests are provided.
Date: September 22, 2004
Creator: Truett, LF
System: The UNT Digital Library
TRANSPORTATION SYSTEM REQUIREMENTS DOCUMENT (open access)

TRANSPORTATION SYSTEM REQUIREMENTS DOCUMENT

None
Date: December 22, 2004
Creator: /a, n
System: The UNT Digital Library
Shared Communications: Volume 1. A Summary and Literature Review (open access)

Shared Communications: Volume 1. A Summary and Literature Review

This paper provides a review of examples from the literature of shared communication resources and of agencies and/or organizations that share communication resources. The primary emphasis is on rural, intelligent transportation system communications involving transit. Citations will not be limited, however, to rural activities, or to ITS implementation, or even to transit. In addition, the term ''communication'' will be broadly applied to include all information resources. Literature references to issues that contribute to both successful and failed efforts at sharing communication resources are reviewed. The findings of this literature review indicate that: (1) The most frequently shared communication resources are information/data resources, (2) Telecommunications infrastructure and technologies are the next most frequently shared resources, (3) When resources are successfully shared, all parties benefit, (4) A few unsuccessful attempts of sharing resources have been recorded, along with lessons learned, (5) Impediments to sharing include security issues, concerns over system availability and reliability, service quality and performance, and institutional barriers, (6) Advantages of sharing include financial benefits to agencies from using shared resources and benefits to the public in terms of congestion mitigation, information transfer (e.g., traveler information systems), mobility (e.g., welfare-to-work paratransit), and safety (e.g., speed of incident response, incident avoidance), …
Date: September 22, 2004
Creator: Franzese, O
System: The UNT Digital Library
Report of the Solar and Atmospheric Neutrino Working Group (open access)

Report of the Solar and Atmospheric Neutrino Working Group

The highest priority of the Solar and Atmospheric Neutrino Experiment Working Group is the development of a real-time, precision experiment that measures the pp solar neutrino flux. A measurement of the pp solar neutrino flux, in comparison with the existing precision measurements of the high energy {sup 8}B neutrino flux, will demonstrate the transition between vacuum and matter-dominated oscillations, thereby quantitatively testing a fundamental prediction of the standard scenario of neutrino flavor transformation. The initial solar neutrino beam is pure {nu}{sub e}, which also permits sensitive tests for sterile neutrinos. The pp experiment will also permit a significantly improved determination of {theta}{sub 12} and, together with other solar neutrino measurements, either a measurement of {theta}{sub 13} or a constraint a factor of two lower than existing bounds. In combination with the essential pre-requisite experiments that will measure the {sup 7}Be solar neutrino flux with a precision of 5%, a measurement of the pp solar neutrino flux will constitute a sensitive test for non-standard energy generation mechanisms within the Sun. The Standard Solar Model predicts that the pp and {sup 7}Be neutrinos together constitute more than 98% of the solar neutrino flux. The comparison of the solar luminosity measured via neutrinos …
Date: October 22, 2004
Creator: Back, H.; Bahcall, J. N.; Bernabeu, J.; Boulay, M. G.; Bowles, T.; Calaprice, F. et al.
System: The UNT Digital Library
Development of a Novel Catalyst for NO Decomposition (open access)

Development of a Novel Catalyst for NO Decomposition

Air pollution arising from the emission of nitrogen oxides as a result of combustion taking place in boilers, furnaces and engines, has increasingly been recognized as a problem. New methods to remove NO{sub x} emissions significantly and economically must be developed. The current technology for post-combustion removal of NO is the selective catalytic reduction (SCR) of NO by ammonia or possibly by a hydrocarbon such as methane. The catalytic decomposition of NO to give N{sub 2} will be preferable to the SCR process because it will eliminate the costs and operating problems associated with the use of an external reducing species. The most promising decomposition catalysts are transition metal (especially copper)-exchanged zeolites, perovskites, and noble metals supported on metal oxides such as alumina, silica, and ceria. The main shortcoming of the noble metal reducible oxide (NMRO) catalysts is that they are prone to deactivation by oxygen. It has been reported that catalysts containing tin oxide show oxygen adsorption behavior that may involve hydroxyl groups attached to the tin oxide. This is different than that observed with other noble metal-metal oxide combinations, which have the oxygen adsorbing on the noble metal and subsequently spilling over to the metal oxide. This observation …
Date: October 22, 2004
Creator: Akyurtlu, Ates & Akyurtlu, Jale F.
System: The UNT Digital Library
Final Report for Sheet Beam Klystron Program (open access)

Final Report for Sheet Beam Klystron Program

The Phase I program demonstrated feasibility of the RF circuit, periodic permanent magnet focusing and beam transport. Computer simulations indicate that the device should meet the goals of the program with the anticipated power and efficiency. The electron gun is currently under construction in another program, and the collector is a simple design based on existing technology.
Date: September 22, 2004
Creator: Read, Michael; Ives, Lawrence & Phillips, Purobi
System: The UNT Digital Library
Probability Distribution for Flowing Interval Spacing (open access)

Probability Distribution for Flowing Interval Spacing

Fracture spacing is a key hydrologic parameter in analyses of matrix diffusion. Although the individual fractures that transmit flow in the saturated zone (SZ) cannot be identified directly, it is possible to determine the fractured zones that transmit flow from flow meter survey observations. The fractured zones that transmit flow as identified through borehole flow meter surveys have been defined in this report as flowing intervals. The flowing interval spacing is measured between the midpoints of each flowing interval. The determination of flowing interval spacing is important because the flowing interval spacing parameter is a key hydrologic parameter in SZ transport modeling, which impacts the extent of matrix diffusion in the SZ volcanic matrix. The output of this report is input to the ''Saturated Zone Flow and Transport Model Abstraction'' (BSC 2004 [DIRS 170042]). Specifically, the analysis of data and development of a data distribution reported herein is used to develop the uncertainty distribution for the flowing interval spacing parameter for the SZ transport abstraction model. Figure 1-1 shows the relationship of this report to other model reports that also pertain to flow and transport in the SZ. Figure 1-1 also shows the flow of key information among the SZ …
Date: September 22, 2004
Creator: Kuzio, S.
System: The UNT Digital Library
EMSP Project 70070: Reactivity of Primary Soil Minerals and Secondary Precipitates Beneath Leaking Hanford Waste Tanks - Final Report (open access)

EMSP Project 70070: Reactivity of Primary Soil Minerals and Secondary Precipitates Beneath Leaking Hanford Waste Tanks - Final Report

Since the late 1950s, leaks from 67 single-shell tanks at the Hanford Site have released about 1 million curies to the underlying sediments. The radioactive material was contained in water-based solutions generally characterized as having high pH values (basic solutions), high nitrate and nitrite concentrations, and high aluminum concentrations. The solutions were also hot, in some cases at or near boiling, as well as complex and highly variable in composition reflecting solutions obtained from multiple methods of reprocessing spent nuclear fuel. In order to understand the observed and probable distribution of radionuclides in the ground at Hanford, major reactions that likely occurred between the leaked fluids and the sediment minerals were investigated in laboratory experiments simulating environmental conditions. Reactions involving the dissolution of quartz and biotite and the simultaneous formation of new minerals were quantified at controlled pH values and temperature. Result s show that the dissolution of quartz and formation of new zeolite-like minerals could have altered the flow path of ground water and contaminant plumes and provided an uptake mechanism for positively-charged soluble radionuclides, such as cesium. The dissolution of biotite, a layered-iron-aluminum-silicate mineral, provided iron in a reduced form that could have reacted with negatively-charged soluble chromium, …
Date: April 22, 2004
Creator: Nagy, Kathryn L.
System: The UNT Digital Library
Melt Rate Assessment of SB/2/3 with Frit 418 - Effects of Waste Loading and Acid Addition (open access)

Melt Rate Assessment of SB/2/3 with Frit 418 - Effects of Waste Loading and Acid Addition

Preparations are being made by the Defense Waste Processing Facility (DWPF) to blend Sludge Batch 2 (SB2) with Sludge Batch 3 (SB3) (blend referred to as SB2/3), and implement a frit change from Frit 320 to Frit 418. A series of dry-fed tests have been performed to investigate the effect of waste loading (WL) on the melt rate of the SB2/3-Frit 418 system. As was observed in the SB2-Frit 320 system, dry-fed melt rate furnace (MRF) tests of the SB2/3-Frit 418 system showed that melt rate decreased as the waste loading increased (WL range of 31-43 per cent tested). In addition, waste throughput of the SB2/3-Frit 418 system reached a peak (at approximately 34 per cent WL) with increased waste loading before steadily decreasing (based on MRF tests). Based on this testing, the Immobilization Technology Section (ITS) recommends that the waste loading starting point for DWPF should be approximately 34 per cent when the processing of the SB2/3 begins with Frit 418. The current target waste loading for DWPF is 34 per cent with SB2-Frit 320, and the results from this testing do not indicate any reasons to reduce this target. Then after a period of steady processing,incrementally higher waste …
Date: July 22, 2004
Creator: LORIER, TROYH.
System: The UNT Digital Library
Special Analysis: Radionuclides Screening Analysis for E Area (open access)

Special Analysis: Radionuclides Screening Analysis for E Area

It was recently discovered that waste being disposed of onsite contained radionuclides that had not been analyzed by the Performance Assessment (PA). These radionuclides had been eliminated from the PA in an earlier screening evaluation because they were not expected to be contained in SRS-generated waste or that received from offsite generators. This Special Analysis (SA) is being prepared to establish the screening criteria and level of evaluation for all radionuclides potentially significant to a Low Level Waste PA or Composite Analysis (CA). The screening methodology recommended by the National Council on Radiological Protection and Measurements (NCRP) has been used to identify those radionuclides that require detailed analysis to derive disposal limits. Of the approximately 2800 radionuclides, a total of 826 were considered by the NCRP to be potentially significant. Approximately 686 radionuclides were eliminated from this analysis due to their short half-life or other properties. Approximately 40 of the 140 remaining radionuclides have been analyzed in the existing PA and waste acceptance criteria established. This SA develops the screening criteria and establishes trigger values to be used to determine the level of analysis required for those radionuclides not analyzed in PA. The results of the SA identified 20 radionuclides …
Date: July 22, 2004
Creator: COOK, JAMES
System: The UNT Digital Library
Drift-Scale Radionuclide Transport (open access)

Drift-Scale Radionuclide Transport

The purpose of this model report is to document the drift scale radionuclide transport model, taking into account the effects of emplacement drifts on flow and transport in the vicinity of the drift, which are not captured in the mountain-scale unsaturated zone (UZ) flow and transport models ''UZ Flow Models and Submodels'' (BSC 2004 [DIRS 169861]), ''Radionuclide Transport Models Under Ambient Conditions'' (BSC 2004 [DIRS 164500]), and ''Particle Tracking Model and Abstraction of Transport Process'' (BSC 2004 [DIRS 170041]). The drift scale radionuclide transport model is intended to be used as an alternative model for comparison with the engineered barrier system (EBS) radionuclide transport model ''EBS Radionuclide Transport Abstraction'' (BSC 2004 [DIRS 169868]). For that purpose, two alternative models have been developed for drift-scale radionuclide transport. One of the alternative models is a dual continuum flow and transport model called the drift shadow model. The effects of variations in the flow field and fracture-matrix interaction in the vicinity of a waste emplacement drift are investigated through sensitivity studies using the drift shadow model (Houseworth et al. 2003 [DIRS 164394]). In this model, the flow is significantly perturbed (reduced) beneath the waste emplacement drifts. However, comparisons of transport in this perturbed …
Date: September 22, 2004
Creator: Houseworth, J.
System: The UNT Digital Library
Statistical Tools for Forensic Analysis of Toolmarks (open access)

Statistical Tools for Forensic Analysis of Toolmarks

Recovery and comparison of toolmarks, footprint impressions, and fractured surfaces connected to a crime scene are of great importance in forensic science. The purpose of this project is to provide statistical tools for the validation of the proposition that particular manufacturing processes produce marks on the work-product (or tool) that are substantially different from tool to tool. The approach to validation involves the collection of digital images of toolmarks produced by various tool manufacturing methods on produced work-products and the development of statistical methods for data reduction and analysis of the images. The developed statistical methods provide a means to objectively calculate a ''degree of association'' between matches of similarly produced toolmarks. The basis for statistical method development relies on ''discriminating criteria'' that examiners use to identify features and spatial relationships in their analysis of forensic samples. The developed data reduction algorithms utilize the same rules used by examiners for classification and association of toolmarks.
Date: April 22, 2004
Creator: Baldwin, David; Morris, Max; Bajic, Stan; Zhou, Zhigang & Kreiser, James
System: The UNT Digital Library
A COMPUTATIONAL WORKBENCH ENVIRONMENT FOR VIRTUAL POWER PLANT SIMULATION (open access)

A COMPUTATIONAL WORKBENCH ENVIRONMENT FOR VIRTUAL POWER PLANT SIMULATION

In this report is described the work effort to develop and demonstrate a software framework to support advanced process simulations to evaluate the performance of advanced power systems. Integrated into the framework are a broad range of models, analysis tools, and visualization methods that can be used for the plant evaluation. The framework provides a tightly integrated problem-solving environment, with plug-and-play functionality, and includes a hierarchy of models, ranging from fast running process models to detailed reacting CFD models. The framework places no inherent limitations on the type of physics that can be modeled, numerical techniques, or programming languages used to implement the equipment models, or the type or amount of data that can be exchanged between models. Tools are provided to analyze simulation results at multiple levels of detail, ranging from simple tabular outputs to advanced solution visualization methods. All models and tools communicate in a seamless manner. The framework can be coupled to other software frameworks that provide different modeling capabilities. Three software frameworks were developed during the course of the project. The first framework focused on simulating the performance of the DOE Low Emissions Boiler System Proof of Concept facility, an advanced pulverized-coal combustion-based power plant. The …
Date: December 22, 2004
Creator: Bockelie, Mike; Swensen, Dave; Denison, Martin; Sarofim, Adel & Senior, Connie
System: The UNT Digital Library
Princeton Plasma Physics Laboratory Annual Site Environmental Report for Calendar Years 2002 and 2003 (open access)

Princeton Plasma Physics Laboratory Annual Site Environmental Report for Calendar Years 2002 and 2003

This report provides the U.S. Department of Energy (DOE) and the public with information on the level of radioactive and non-radioactive pollutants (if any) that are added to the environment as a result of Princeton Plasma Physics Laboratory's (PPPL) operations. The results of the 2002 and 2003 environmental surveillance and monitoring program for PPPL are presented and discussed. The report also summarizes environmental initiatives, assessments, and programs that were undertaken in 2002 and 2003.
Date: December 22, 2004
Creator: Virginia L. Finley, Editor
System: The UNT Digital Library
NOVEL IN-SITU METAL AND MINERAL EXTRACTION TECHNOLOGY (open access)

NOVEL IN-SITU METAL AND MINERAL EXTRACTION TECHNOLOGY

This white paper summarizes the state of art of in-situ leaching of metals and minerals, and describes a new technology concept employing improved fragmentation of ores underground in order to prepare the ore for more efficient in-situ leaching, combined with technology to continuously improve solution flow patterns through the ore during the leaching process. The process parameters and economic benefits of combining the new concept with chemical and biological leaching are described. A summary is provided of the next steps required to demonstrate the technology with the goal of enabling more widespread use of in-situ leaching.
Date: September 22, 2004
Creator: O'Gorman, Glenn; Michaelis, Hans von & Olson, Gregory J.
System: The UNT Digital Library
Nonlinear Turbulence Simulations for NSTX H-modes (open access)

Nonlinear Turbulence Simulations for NSTX H-modes

Present evidence points to remarkably resilient electron temperature profiles in high-density H-mode plasmas on the National Spherical Torus Experiment (NSTX), suggesting that the underlying electron thermal transport mechanisms respond in a highly nonlinear fashion to changes in the gradients. This paper uses measured plasma profiles as input to linear gyrokinetic analysis to identify candidate micro-instabilities that may be responsible for the electron thermal transport. The criteria for useful nonlinear micro-stability analyses are discussed along with necessary approximations and computational issues.
Date: June 22, 2004
Creator: Redi, M. H.; Kaye, S.; Dorland, W.; Bell, R.; Bourdelle, C.; Ethier, S. et al.
System: The UNT Digital Library
The coming revolution in particle physics: Report of the Fermilab Long Range Planning Committee (open access)

The coming revolution in particle physics: Report of the Fermilab Long Range Planning Committee

In early 2003, the Fermilab Director formed a committee (Appendix A) to examine options for the long-range future of Fermilab. Specifically, the committee was asked to respond to a charge (Appendix B), which laid out the assumptions, which were to underlie our discussions. The committee met a few times during the spring of 2003 and formulated a plan of action. It identified a number of issues that deserved attention, and a subcommittee was formed to focus on each. We agreed that in addressing these key issues, a broader participation was appropriate. The manner in which that was achieved varied from subcommittee to subcommittee to group. In some cases the expanded membership participated in all the discussions, in others, particular presentations were solicited and heard. Some subgroups met regularly over several months, others convened only for a small number of discussions. We have attempted to list participants in Appendix C. General presentations indicating the purpose of the work were given, for example at the Fermilab Users Annual Meeting. Towards the end of the summer some sense of direction developed and a series of open meetings was organized by the different subgroups. These meetings of two and more hour's duration gave the …
Date: June 22, 2004
Creator: al., Jeff Appel et
System: The UNT Digital Library
High strength and heat resistant chromium steels for sodium-cooled fast reactors. (open access)

High strength and heat resistant chromium steels for sodium-cooled fast reactors.

This report provides the results of a preliminary phase of a project supporting the Advanced Nuclear Fuel Cycle Technology Initiative at ANL. The project targets the Generation IV nuclear energy systems, particularly the area of reducing the cost of sodium-cooled fast-reactors by utilizing innovative materials. The main goal of the project is to provide the nuclear heat exchanger designers a simplified means to quantify the cost advantages of the recently developed high strength and heat resistant ferritic steels with 9 to 13% chromium content. The emphasis in the preliminary phase is on two steels that show distinctive advantages and have been proposed as candidate materials for heat exchangers and also for reactor vessels and near-core components of Gen IV reactors. These steels are the 12Cr-2W (HCM12A) and 9Cr-1MoVNb (modified 9Cr-1Mo). When these steels are in tube form, they are referred to in ASTM Standards as T122 and T91, respectively. A simple thermal-hydraulics analytical model of a counter-flow, shell-and-tube, once-through type superheated steam generator is developed to determine the required tube length and tube wall temperature profile. The single-tube model calculations are then extended to cover the following design criteria: (i) ratio of the tube stress due to water/steam pressure to …
Date: December 22, 2004
Creator: Kamal, S.; Grandy, C.; Farmer, M. & Brunsvold, A.
System: The UNT Digital Library