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Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ATWS Transients for the 2400 MWt Gas-Cooled Fast Reactor

Description: Reactivity transients have been analyzed with an updated RELAPS-3D (ver. 2.4.2) system model of the pin core design for the 2400MWt gas-cooled fast reactor (GCFR). Additional reactivity parameters were incorporated in the RELAP5 point-kinetics model to account for reactivity feedbacks due to axial and radial expansion of the core, fuel temperature changes (Doppler effect), and pressure changes (helium density changes). Three reactivity transients without scram were analyzed and the incidents we… more
Date: August 5, 2007
Creator: Cheng, L. Y. & Ludewig, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mechanism and Estimation of Fatigue Crack Initiation in Austenitic Stainless Steels in LWR Environments.

Description: The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the f… more
Date: August 1, 2002
Creator: Chopra, O. K. & Technology, Energy
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility study for use of the natural convection shutdown heat removal test facility (NSTF) for VHTR water-cooled RCCS shutdown.

Description: In summary, a scaling analysis of a water-cooled Reactor Cavity Cooling System (RCCS) system was performed based on generic information on the RCCS design of PBMR. The analysis demonstrates that the water-cooled RCCS can be simulated at the ANL NSTF facility at a prototypic scale in the lateral direction and about half scale in the vertical direction. Because, by necessity, the scaling is based on a number of approximations, and because no analytical information is available on the performance … more
Date: August 31, 2007
Creator: Tzanos, C. P. & Farmer, M. T.
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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Final Report-Passive Safety Optimization in Liquid Sodium-Cooled Reactors.

Description: This report summarizes the results of a three-year collaboration between Argonne National Laboratory (ANL) and the Korea Atomic Energy Research Institute (KAERI) to identify and quantify the performance of innovative design features in metallic-fueled, sodium-cooled fast reactor designs. The objective of the work was to establish the reliability and safety margin enhancements provided by design innovations offering significant potential for construction, maintenance, and operating cost reductio… more
Date: August 13, 2007
Creator: Cahalana, J. E. & Hahn, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF THE MIGRATION POTENTIAL FOR 60Co AND 137Cs AT THE MAINE YANKEE SITE.

Description: The objective of this report is to discuss the degree of sorption and desorption of {sup 137}Cs and {sup 60}Co that may be associated with the granite bedrock and the ''popcorn'' cement drain system that underlie the Maine Yankee Containment Foundation. The purpose is to estimate how much retardation of these two radionuclides takes place in groundwater that flows in the near-field of the Containment Foundation, specifically with respect to contamination originating at the PAB Test Pit. Specifi… more
Date: August 8, 2002
Creator: FUHRMANN,M. SULLIVAN,T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

Description: The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-m… more
Date: August 1, 2009
Creator: Rosenthal, Murray Wilford
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EXAMINATION OF A PROPOSED VALIDATION DATA SET USING CFD CALCULATIONS

Description: The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for both electrical power generation and production of process heat required for industrial processes such as the manufacture of hydrogen for use as a fuel in automobiles. The DOE project is called the next generation nuclear plant (NGNP) and is based on a Generation IV reactor concept called the very high temperature reactor (VHTR), which will use helium as the coolant at temperatures ranging from … more
Date: August 1, 2009
Creator: Johnson, Richard W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials

Description: Since 2002, the Department of Energy's (DOE's) Generation IV Nuclear Energy Systems (Gen IV) Program has addressed the research and development (R&D) necessary to support next-generation nuclear energy systems. The six most promising systems identified for next-generation nuclear energy are described within this roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor-SC… more
Date: August 1, 2008
Creator: Corwin, William R; Burchell, Timothy D; Katoh, Yutai; McGreevy, Timothy E; Nanstad, Randy K; Ren, Weiju et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of Generation-IV transmutation impacts.

Description: An assessment of the potential role of Generation IV nuclear systems in an advanced fuel cycle has been performed. The Generation IV systems considered are the thermal-spectrum VHTR and SCWR, and the fast-spectrum GFR, LFR, and SFR. This report addresses the impact of each system on advanced fuel cycle goals, particularly related to waste management and resource utilization. The transmutation impact of each system was also assessed, along with variant designs for transuranics (TRU) burning. The… more
Date: August 3, 2005
Creator: Taiwo, T. A. & Hill, R. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Robust Tri-Carbide Fueled Reactor for Multimegawatt Space Power and Propulsion Applications

Description: An innovative reactor core design based on advanced, mixed carbide fuels was analyzed for nuclear space power applications. Solid solution, mixed carbide fuels such as (U,Zr,Nb)c and (U,Zr, Ta)C offer great promise as an advanced high temperature fuel for space power reactors.
Date: August 11, 2004
Creator: Anghaie, Samim; Knight, Travis W.; Plancher, Johann & Gouw, Reza
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Initial Cladding Condition

Description: The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is received at the Yucca Mountain Project (YMP) site. Most commercial nuclear fuel is encased in Zircaloy cladding. This analysis is developed to describe cladding degradation from the expected failure modes. This includes reactor operation impacts including incipient failures, potential degradation after reactor operation during spent fuel storage in pool and dry storage and impacts due to transpor… more
Date: August 22, 2000
Creator: Siegmann, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scientific Analysis Cover Sheet for Radionuclide Screening

Description: The waste forms under consideration for disposal in the proposed repository at Yucca Mountain contain scores of radionuclides (Attachments V and VI). It would be impractical and highly inefficient to model all of these radionuclides in a total system performance assessment (TSPA). Thus, the purpose of this radionuclide screening analysis is to remove from further consideration (screen out) radionuclides that are unlikely to significantly contribute to radiation dose to the public from the propo… more
Date: August 9, 2002
Creator: Ragan, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Burnable Absorbers on PWR Spent Nuclear Fuel

Description: Burnup credit is an ongoing issue in designing and licensing transportation and storage casks for spent nuclear fuel (SNF). To address this issue, in July 1999, the U.S. Nuclear Regulatory Commission (NRC), Spent Fuel Project Office, issued Interim Staff Guidance-8 (ISG-8), Revision 1 allowing limited burnup credit for pressurized water reactor (PWR) spent nuclear fuel (SNF) to be used in transport and storage casks. However, one of the key limitations for a licensing basis analysis as stipulat… more
Date: August 21, 2000
Creator: O'Leary, P.M. & Pitts, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Packaging Design Criteria for the MCO Cask

Description: Approximately 2,100 metric tons of unprocessed, irradiated, nuclear fuel elements are presently stored in the K Basins (including approximately 700 additional elements from the Plutonium-Uranium Extraction Plant, N Reactor, and 327 Laboratory). To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East Area. The purpose of this packaging design criteria is to provide criteria for the design, fabr… more
Date: August 1, 2000
Creator: Flanagan, B. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RELAP5 / MOD3.2 analysis of INSC standard problem INSCSP - R7 : void fraction distribution over RBMK fuel channel height for experiments performed in the ENTEK BM test facility.

Description: The RELAP5/MOD3.2 computer program has been used to analyze a series of tests investigating void fraction distribution over height in RBMK fuel channels performed in Facility BM at the ENTEK. This is RBMK Standard Problem 7 in Joint Project 6, which is the investigation of Computer Code Validation for Transient Analysis of RBMK and VVER Reactors, between the United States and Russian Minatom International Nuclear Safety Centers. The experiment facility and data, RELAP5 nodalization, and results… more
Date: August 22, 2002
Creator: Garner, P. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

Description: The Overall project demonstrated that toxic metals (cesium Cs and strontium Sr) in aqueous and organic wastes can be isolated from the environment through reaction with kaolinite based sorbent substrates in high temperature reactor environments. In addition, a state-of-the art laser diagnostic tool to measure droplet characteristic in practical 'dirty' laboratory environments was developed, and was featured on the cover of a recent edition of the scientific journal ''applied Spectroscopy''. Fur… more
Date: August 6, 2003
Creator: Wendt, Jost O. L.; Kerstein, Alan R.; Scheeline, Alexander; Pearlstein, Arne & Linak, William
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation Analysis of San Onofre Depletion MOX Fuel Experiment

Description: The report provides calculation results of isotopic composition of spent MOX fuel irradiated in Sun Onofre PWR reactor. The calculation was performed by means of the MCU/BURNUP Monte Carlo code. The code is developed in Kurchatov Institute, Russia. The predicted isotope contents are compared with the measured ones. A purpose of this work is a verification both the code and the model of experiment description. Predicted plutonium content exceeds the measured one approximately by 3%. It is arise … more
Date: August 31, 2001
Creator: Pavlovichev, AM
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transition to a nuclear/hydrogen energy system.

Description: The paper explores the motivation for the transition to a nuclear/hydrogen system. For such a transition to be successful the technologies employed must be able to generate enough hydrogen to displace a significant fraction of the petroleum fuels used in the transportation and process heat sectors. This hydrogen must be generated in a manner that is compatible with the environment and independent of foreign fuels. Nuclear energy, along with contributions from wind, solar, and geothermal resourc… more
Date: August 13, 2002
Creator: Walters, L.; Wade, D. & Lewis, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear Isotopic Dilution of Highly Enriched Uranium by Dry Blending via the Rm-2 Mill Technology

Description: DOE has initiated numerous activities to focus on identifying material management strategies to disposition various excess fissile materials. In particular the INEEL has stored 1,700 Kg of offspec HEU at INTEC in CPP-651 vault facility. Currently, the proposed strategies for dispositioning are (a) aqueous dissolution and down blending to LEU via facilities at SRS followed by shipment of the liquid LEU to NFS for fabrication into LWR fuel for the TVA reactors and (b) dilution of the HEU to 0.9% … more
Date: August 1, 2003
Creator: Rajamani, Raj K.; Latchireddi, Sanjeeva; Devrani, Vikas; Sethi, Harappan; Henry, Roger & Chipman, Nate
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The future of reactor neutrino experiments: A novel approach to measuring theta{sub 13}

Description: Results from non-accelerator neutrino oscillation experiments have provided evidence for the oscillation of massive neutrinos. The subdominant oscillation, the coupling of the electron neutrino flavor to the third mass eigenstate, has not been measured yet. The size of this coupling U{sub e3} and its corresponding mixing angle theta{sub 13} are critical for CP violation searches in the lepton sector and will define the future of accelerator neutrino physics. The current best limit on U{sub e3} … more
Date: August 24, 2003
Creator: Heeger, Karsten M.; Freedman, Stuart J. & Luk, Kam-Biu
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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