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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

Description: A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of Nonmetallic Liquid Coolants for Nuclear-Power Piles

Description: A comprehensive survey of the literature was made in an effort to identify nonmetallic materials of possible usefulness as liquid coolants. Materials having maximum melting points of 1000 deg F and boiling points of l200 deg F were considered, but boiling points above 2200 deg F were preferred. Melting points, boiling points, densities, heat capacities, and thermal conductivities were tabulated. Approximately 190 materials appeared to have melting and boiling temperatures in a suitable range. A… more
Date: May 26, 1950
Creator: Shaw, H.L. & Boulger, F.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant

Description: An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MODIFICATION OF THE EXPERIMENTAL BOILING WATER REACTOR (EBWR) FOR HIGHER- POWER OPERATION

Description: Supplement to ANL-5607. Alterations and additions made to the Experimental Boiling Water Reactor (EBWR) plant to permit operation at power levels up to I00 Mw(t) are described. Topics covered include over-all system modifications and additions, nuclear component modifications and additions, and reboiler plant component description. (M.C.G.)
Date: April 1, 1962
Creator: Matousek, J.F. comp.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validation of neutron-transport calculations in benchmark facilities for improved damage-fluence predictions

Description: An accurate determination of damage fluence accumulated by reactor pressure vessels (RPV) as a function of time is essential in order to evaluate the vessel integrity for both pressurized thermal shock (PTS) transients and end-of-life considerations. The desired accuracy for neutron exposure parameters such as displacements per atom or fluence (E > 1 MeV) is of the order of 20 to 30%. However, these types of accuracies can only be obtained realistically by validation of nuclear data and calcula… more
Date: January 1, 1983
Creator: Williams, M.L.; Stallmann, F.W.; Maerker, R.E. & Kam, F.B.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A Mechanism Explaining the Instability of EBR-I, Mark III

Description: Presented at the International Atomic Energy Agencysponsored Seminar on the Physics of Fast and Intermediate Reactors. Vienna, August 3-11, 196l. A feedback model, was developed to account for resonant instabilities in the Mark II core. In this model, the prompt positive power coefficient effect is ascribed to fuel rod bowing and the delayed negative power coefficient effect to thermally lnduced motions in the lower shield plate. Since this model is supported by observations, it is concluded th… more
Date: September 1, 1961
Creator: Smith, R. R.; Matlock, R. G.; McGinnis, F. D.; Novick, M. & Thalgott, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor technology. Progress report, January-March 1980

Description: Progress is reported concerning space reactor (SPAR) electric power supply; GCFR reactor safety experiments; structural analysis of HTGR, PWR, and BWR containment vessels and pressure vessels; heat pipe technology development; and nuclear criticality experiments and safety.
Date: June 1, 1980
Creator: Breslow, M. & Sullivan, S. (eds.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2

Description: This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-… more
Date: February 25, 2008
Creator: Winterholler, Kirk
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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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FABRICATION PROCESS AND PRODUCT QUALITY IMPROVEMENTS IN ADVANCED GAS REACTOR UCO KERNELS

Description: A major element of the Advanced Gas Reactor (AGR) program is developing fuel fabrication processes to produce high quality uranium-containing kernels, TRISO-coated particles and fuel compacts needed for planned irradiation tests. The goals of the AGR program also include developing the fabrication technology to mass produce this fuel at low cost. Kernels for the first AGR test (“AGR-1) consisted of uranium oxycarbide (UCO) microspheres that werre produced by an internal gelation process followe… more
Date: September 1, 2008
Creator: Barnes, Charles M
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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NGNP Process Heat Utilization: Liquid Metal Phase Change Heat Exchanger

Description: One key long-standing issue that must be overcome to fully realize the successful growth of nuclear power is to determine other benefits of nuclear energy apart from meeting the electricity demands. The Next Generation Nuclear Plant (NGNP) will most likely be producing electricity and heat for the production of hydrogen and/or oil retrieval from oil sands and oil shale to help in our national pursuit of energy independence. For nuclear process heat to be utilized, intermediate heat exchange is … more
Date: September 1, 2008
Creator: Sabharwall, Piyush; Patterson, Mike; Utgikar, Vivek & Gunnerson, Fred
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Hydrogen Production via a Commerically Ready Inorganic membrane Reactor

Description: It has been known that use of the hydrogen selective membrane as a reactor (MR) could potentially improve the efficiency of the water shift reaction (WGS), one of the least efficient unit operations for production of high purity hydrogen from syngas. However, no membrane reactor technology has been reduced to industrial practice thus far, in particular for a large-scale operation. This implementation and commercialization barrier is attributed to the lack of a commercially viable hydrogen selec… more
Date: June 30, 2007
Creator: Liu, Paul
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RESULTS OF TESTS TO DEMONSTRATE A SIX-INCH-DIAMETER COATER FOR PRODUCTION OF TRISO-COATED PARTICLES FOR ADVANCED GAS REACTOR EXPERIMENTS

Description: The Next Generation Nuclear Plant (NGNP)/Advanced Gas Reactor (AGR) Fuel Development and Qualification Program includes a series of irradiation experiments in Idaho National Laboratory’s (INL’s) Advanced Test Reactor. TRISOcoated particles for the first AGR experiment, AGR-1, were produced at Oak Ridge National Laboratory (ORNL) in a two inch diameter coater. A requirement of the NGNP/AGR Program is to produce coated particles for later experiments in coaters more representative of industrial s… more
Date: September 1, 2008
Creator: Barnes, Charles M
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cynod: A Neutronics Code for Pebble Bed Modular Reactor Coupled Transient Analysis

Description: The Pebble Bed Reactor (PBR) is one of the two concepts currently considered for development into the Next Generation Nuclear Plant (NGNP). This interest is due, in particular, to the concept’s inherent safety characteristics. In order to verify and confirm the design safety characteristics of the PBR computational tools must be developed that treat the range of phenomena that are expected to be important for this type of reactors. This paper presents a recently developed 2D R-Z cylindrical nod… more
Date: September 1, 2008
Creator: Hiruta, Hikaru; Ougouag, Abderrafi M.; Gougar, Hans D. & Ortensi, Javier
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of a CFD Analysis Plan for the first VHTR Standard Problem

Description: Data from a scaled model of a portion of the lower plenum of the helium-cooled very high temperature reactor (VHTR) are under consideration for acceptance as a computational fluid dynamics (CFD) validation data set or standard problem. A CFD analysis will help determine if the scaled model is a suitable geometry for validation data. The present article describes the development of an analysis plan for the CFD model. The plan examines the boundary conditions that should be used, the extent of th… more
Date: September 1, 2008
Creator: Johnson, Richard W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Oak Ridge National Laboratory institutional plan, FY 1990--FY 1995

Description: The Oak Ridge National Laboratory is one of DOE's major multiprogram energy laboratories. ORNL's program missions are (1) to conduct applied research and engineering development in support of DOE's programs in fusion, fission, fossil, renewables (biomass), and other energy technologies, and in the more efficient conversion and use of energy (conservation) and (2) to perform basic scientific research in selected areas of the physical and life sciences. These missions are to be carried out in com… more
Date: November 1, 1989
Item Type: Refine your search to only Report
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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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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THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM

Description: Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor (HTGR) is one of the critical development activities being pursued within the Next Generation Nuclear Plant (NGNP) program. Graphite’s thermal stability (in an inert gas environment), high compressive strength, fabricability, and cost effective price make it an ideal core structural material for the HTGR reactor design. While the general characteristics necessary for producing nuclear grade graph… more
Date: September 1, 2008
Creator: Windes, William E.; Burchell, Timothy D. & Bratton, Robert L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.

Description: This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and … more
Date: February 14, 2008
Creator: O'Hara, John; Higgins, James C.; Brown, William S. & Fink, Robert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRA Closure Plan REV 0-9-20-06 HWMA/RCRA Closure Plan for the TRA/MTR Warm Waste System Voluntary Consent Order SITE-TANK-005 Tank System TRA-007

Description: This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for portions of the Test Reactor Area/Materials Test Reactor Warm Waste System located in the Materials Test Reactor Building (TRA-603) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan SITE-TANK-005 for Tank System TRA-007. The reactor drain tank and canal sump to be closed are included in the Te… more
Date: January 31, 2007
Creator: Winterholler, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validation Testing of Hydrogen Generation Technology

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Roadmapping – A Systematic Approach to Overcoming NGNP Challenges

Description: Changing requirements, programmatic challenges, and technical risk hinder even the best projects. The Next Generation Nuclear Plant (NGNP) is a complex project with technical and programmatic uncertainty. This paper presents the path forward, methods, and tools used to understand the requirements, manage the uncertainty, and mitigate the risk for the NGNP project. The key tool, technology development roadmaps, is described in detail as a means to facilitate NGNP risk-informed decision making, t… more
Date: September 1, 2008
Creator: Collins, John W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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