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THE COMPONENT TEST FACILITY – A NATIONAL USER FACILITY FOR TESTING OF HIGH TEMPERATURE GAS-COOLED REACTOR (HTGR) COMPONENTS AND SYSTEMS

Description: The Next Generation Nuclear Plant (NGNP) and other High-Temperature Gas-cooled Reactor (HTGR) Projects require research, development, design, construction, and operation of a nuclear plant intended for both high-efficiency electricity production and high-temperature industrial applications, including hydrogen production. During the life cycle stages of an HTGR, plant systems, structures and components (SSCs) will be developed to support this reactor technology. To mitigate technical, schedule, … more
Date: September 1, 2008
Creator: Duncan, David S.; Balls, Vondell J. & Austad, Stephanie L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The Advanced Test Reactor Irradiation Capabilities Available as a National Scientific User Facility

Description: The Advanced Test Reactor (ATR) is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. The ATR is a very versatile facility with a wide variety of experimental test capabilities for providing the environment needed in an irradiation experiment. These capabilities include simple capsule experiments, instrumented and/or temperature-controlled experiments, and pressurized water loop experiment facilities. Monitoring systems … more
Date: September 1, 2008
Creator: Grover, S. Blaine
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SYSTEM ANALYSIS OF NUCLEAR-ASSISTED SYNGAS PRODUCTION FROM COAL

Description: A system analysis has been performed to assess the efficiency and carbon utilization of a nuclear-assisted coal gasification process. The nuclear reactor is a high-temperature helium-cooled reactor that is used primarily to provide power for hydrogen production via high-temperature electrolysis. The supplemental hydrogen is mixed with the outlet stream from an oxygen-blown coal gasifier to produce a hydrogen-rich gas mixture, allowing most of the carbon dioxide to be converted into carbon monox… more
Date: September 1, 2008
Creator: Harvego, E. A.; McKellar, M. G. & O'Brien, J. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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HIGHLY ENRICHED URANIUM BLEND DOWN PROGRAM AT THE SAVANNAH RIVER SITE PRESENT AND FUTURE

Description: The Department of Energy (DOE) and Tennessee Valley Authority (TVA) entered into an Interagency Agreement to transfer approximately 40 metric tons of highly enriched uranium (HEU) to TVA for conversion to fuel for the Browns Ferry Nuclear Power Plant. Savannah River Site (SRS) inventories included a significant amount of this material, which resulted from processing spent fuel and surplus materials. The HEU is blended with natural uranium (NU) to low enriched uranium (LEU) with a 4.95% 235U iso… more
Date: June 5, 2008
Creator: Magoulas, V; Charles Goergen, C & Ronald Oprea, R
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Requirements for Reactor Physics Design

Description: It has been recognized that there is a need for requirements and guidance for design and operation of nuclear power plants. This is becoming more important as more reactors are being proposed to be built. In parallel with activities in individual countries are norms established by international organizations. This paper discusses requirements/guidance for neutronic design and operation as promulgated by the U.S. Nuclear Regulatory Commission (NRC). As an example, details are given for one react… more
Date: April 11, 2008
Creator: Diamond, D. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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INL Reactor Technology Complex Out-of-Service Buried Piping Hazards

Description: Idaho National Laboratory (INL) Reactor Technology Complex (RTC) buried piping and components are being characterized to determine if they should be managed as hazardous waste and subject to the Hazardous Waste Management Act /Resource Conservation and Recovery Act (RCRA). RTC buried piping and components involve both active piping and components from currently operating nuclear facilities, such as the Advanced Test Reactor (ATR), and inactive lines from facilities undergoing D&D activities. Th… more
Date: May 1, 2008
Creator: Gerstner, Douglas M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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MARKOV Model Application to Proliferation Risk Reduction of an Advanced Nuclear System

Description: The Generation IV International Forum (GIF) emphasizes proliferation resistance and physical protection (PR&PP) as a main goal for future nuclear energy systems. The GIF PR&PP Working Group has developed a methodology for the evaluation of these systems. As an application of the methodology, Markov model has been developed for the evaluation of proliferation resistance and is demonstrated for a hypothetical Example Sodium Fast Reactor (ESFR) system. This paper presents the case of diver… more
Date: July 13, 2008
Creator: Bari, R. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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PR-EDB: Power Reactor Embrittlement Database - Version 3

Description: The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel em… more
Date: March 1, 2008
Creator: Wang, Jy-An John & Subramani, Ranjit
Item Type: Refine your search to only Report
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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Vital area identification for U.S. Nuclear Regulatory Commission nuclear power reactor licensees and new reactor applicants.

Description: U.S. Nuclear Regulatory Commission nuclear power plant licensees and new reactor applicants are required to provide protection of their plants against radiological sabotage, including the placement of vital equipment in vital areas. This document describes a systematic process for the identification of the minimum set of areas that must be designated as vital areas in order to ensure that all radiological sabotage scenarios are prevented. Vital area identification involves the use of logic mode… more
Date: September 1, 2008
Creator: Whitehead, Donnie Wayne & Varnado, G. Bruce
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor

Description: The Department of Energy’s Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at Purdue University Reactor. With this work completed and in anticipation of other impending conversion projects, the INL convened and engaged the project participants in a structured discussion to capture the lessons learned. The lessons learned process has allowed us to capture gaps, opportunities, an… more
Date: September 1, 2008
Creator: Woolstenhulme, Eric C. & Hewit, Dana M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TMIST-2 Transport Test

Description: In anticipation of the TMIST-2 experiment in the Advanced Test Reactor, there was a need to determine if the tritium that is expected to be observed at the outlet of the experiment would be seen or if it may be lost on its way from the experiment in the core to the measurement station. To assist in resolving that issue, a bench-scale experiment was conducted in the Idaho National Laboratory’s Safety and Tritium Applied Research (STAR) facility using deuterium and a mass spectrometer in lieu of … more
Date: February 1, 2008
Creator: Longhurst, Glen R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Dosimetry Studies at Rhode Island Nuclear Science Center.

Description: The RINSC is a 2 mega-watt, light water and graphite moderated and cooled reactor that has a graphite thermal column built as a user facility for sample irradiation. Over the past decade, after the reactor conversion from a highly-enriched uranium core to a low-enriched one, flux and dose measurements and calculations had been performed in the thermal column to update the ex-core parameters and to predict the effect from in-core fuel burn-up and rearrangement. The most recent data from measurem… more
Date: May 5, 2008
Creator: Reciniello, R. N.; Holden, N. E.; Hu, J. P.; Johnson, D. G.; Meddleton, M. & Tehan, T. N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of Surplus Plutonium for Disposition Options

Description: The United States (U.S.) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Except for materials that remain in use for programs outside of national defense, including programs for nuclear-energy development, the surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. Some ite… more
Date: July 15, 2008
Creator: Allender, Jeffrey S.; Moore, Edwin N. & Davies, Scott H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Optimized, Competitive Supercritical-CO2 Cycle GFR for Gen IV Service

Description: An overall plant design was developed for a gas-cooled fast reactor employing a direct supercritical Brayton power conversion system. The most important findings were that (1) the concept could be capital-cost competitive, but startup fuel cycle costs are penalized by the low core power density, specified in large part to satisfy the goal of significatn post-accident passive natural convection cooling; (2) active decay heat removal is preferable as the first line of defense, with passive perfor… more
Date: September 8, 2008
Creator: Driscoll, M.J.; Hejzlar, P. & Apostolakis, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim Status Report on Lead-Cooled Fast Reactor (Lfr) Research and Development.

Description: This report discusses the status of Lead-Cooled Fast Reactor (LFR) research and development carried out during the first half of FY 2008 under the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. Lead-Cooled Fast Reactor research and development has recently been transferred from Generation IV to the Reactor Campaign of the Global Nuclear Energy Partnership (GNEP). Another status report shall be issued at the end of FY 2008 covering all of the LFR activities carried ou… more
Date: March 31, 2008
Creator: Tzanos, C. P.; Sienicki, J. J.; Moisseytsev, A.; Smith, C. F.; de Caro, M.; Halsey, W. G. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental and Thermalhydraulic Code Assessment of the Transient Behavior of the Passive Condenser System in an Advanced Boiling Water Reactor

Description: The main goal of the project was to study analytically and experimentally the condensation heat transfer for the passive condenser system such as GE Economic Simplified Boiling Water Reactor (ESBWR). The effect of noncondensable gas in condenser tube and the reduction of secondary pool water level to the condensation heat transfer coefficient was the main focus in this research. The objectives of this research were to : 1) obtain experimental data on the local and tube averaged condensation hea… more
Date: July 8, 2008
Creator: Revankar, S.T.; Zhou, W. & Henderson, Gavin
Item Type: Refine your search to only 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

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pebble Bed Reactor Dust Production Model

Description: The operation of pebble bed reactors, including fuel circulation, can generate graphite dust, which in turn could be a concern for internal components; and to the near field in the remote event of a break in the coolant circuits. The design of the reactor system must, therefore, take the dust into account and the operation must include contingencies for dust removal and for mitigation of potential releases. Such planning requires a proper assessment of the dust inventory. This paper presents a … more
Date: September 1, 2008
Creator: Ougouag, Abderrafi M. & Cogliati, Joshua J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SHIELDING ANALYSIS FOR X-RAY SOURCES GENERATED IN TARGET CHAMBER OF THE NATIONAL IGNITION FACILITY

Description: Prompt doses from x-rays generated as result of laser beam interaction with target material are calculated at different locations inside the National Ignition Facility (NIF). The maximum dose outside a Target Chamber diagnostic port is {approx} 1 rem for a shot utilizing the 192 laser beams and 1.8 MJ of laser energy. The dose during a single bundle shot (8 laser beams) drops to {approx} 40 mrem. Doses calculated outside the Target Bay doors and inside the Switchyards (except for the 17 ft.-6 i… more
Date: March 27, 2008
Creator: Khater, H Y; Brereton, S J & Singh, M S
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Status report on the Small Secure Transportable Autonomous Reactor (SSTAR) /Lead-cooled Fast Reactor (LFR) and supporting research and development.

Description: This report provides an update on development of a pre-conceptual design for the Small Secure Transportable Autonomous Reactor (SSTAR) Lead-Cooled Fast Reactor (LFR) plant concept and supporting research and development activities. SSTAR is a small, 20 MWe (45 MWt), natural circulation, fast reactor plant for international deployment concept incorporating proliferation resistance for deployment in non-fuel cycle states and developing nations, fissile self-sufficiency for efficient utilization o… more
Date: June 23, 2008
Creator: Sienicki, J. J.; Moisseytsev, A.; Yang, W. S.; Wade, D. C.; Nikiforova, A.; Hanania, P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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E AREA LOW LEVEL WASTE FACILITY DOE 435.1 PERFORMANCE ASSESSMENT

Description: This Performance Assessment for the Savannah River Site E-Area Low-Level Waste Facility was prepared to meet requirements of Chapter IV of the Department of Energy Order 435.1-1. The Order specifies that a Performance Assessment should provide reasonable assurance that a low-level waste disposal facility will comply with the performance objectives of the Order. The Order also requires assessments of impacts to water resources and to hypothetical inadvertent intruders for purposes of establishin… more
Date: March 31, 2008
Creator: Wilhite, E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials Degradation in Light Water Reactors: Life After 60,???

Description: Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high temperature water, stress, vibration, and an intense neutron field. Degradation of materials in this environment can lead to reduced performance, and in some cases, sudden failure. A recent EPRI-led study interviewed 47 US nuclear utility executives to gauge perspectives on long-term operation of nuclear reactors. Nearly 90% indicated that extensions of reactor lifetimes… more
Date: April 1, 2008
Creator: Busby, Jeremy T.; Nanstad, Randy K.; Stoller, Roger E.; Feng, Zhili & Naus, Dan J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Design, Construction, and Operation of Long-Distance High-Voltage Electricity Transmission Technologies.

Description: This report focuses on transmission lines, which operate at voltages of 115 kV and higher. Currently, the highest voltage lines comprising the North American power grid are at 765 kV. The grid is the network of transmission lines that interconnect most large power plants on the North American continent. One transmission line at this high voltage was built near Chicago as part of the interconnection for three large nuclear power plants southwest of the city. Lines at this voltage also serve mark… more
Date: March 3, 2008
Creator: Molburg, J. C.; Kavicky, J. A. & Picel, K. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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