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Clinch River breeder reactor sodium fire protection system design and development

Description: To assure the protection of the public and plant equipment, improbable accidents were hypothesized to form the basis for the design of safety systems. One such accident is the postulated failure of the Intermediate Heat Transfer System (IHTS) piping within the Steam Generator Building (SGB), resulting in a large-scale sodium fire. This paper discusses the design and development of plant features to reduce the consequences of the accident to acceptable levels. Additional design solutions were ma… more
Date: April 13, 1984
Creator: Foster, K.W.; Boasso, C.J. & Kaushal, N.N.
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.
Partner: UNT Libraries Government Documents Department
open access

MONITORING WASTE HEAT REJECTION TO THE ENVIRONMENT VIA REMOTE SENSING

Description: Nuclear power plants typically use waste heat rejection systems such as cooling lakes and natural draft cooling towers. These systems are designed to reduce cooling water temperatures sufficiently to allow full power operation even during adverse meteorological conditions. After the power plant is operational, the performance of the cooling system is assessed. These assessments usually rely on measured temperatures of the cooling water after it has lost heat to the environment and is being pump… more
Date: January 13, 2009
Creator: Garrett, A
Partner: UNT Libraries Government Documents Department
open access

Impact analyses after pipe rupture. [PWR; BWR]

Description: Two of the French pipe whip experiments are reproduced with the computer code WIPS. The WIPS results are in good agreement with the experimental data and the French computer code TEDEL. This justifies the use of its pipe element in conjunction with its U-bar element in a simplified method of impact analyses.
Date: December 13, 1983
Creator: Chun, R. C. & Chuang, T. Y.
Partner: UNT Libraries Government Documents Department
open access

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

Description: The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable e… more
Date: October 13, 2010
Creator: Jones, R. & Carter, J.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

Measurement of theta{sub 13} with reactor neutrinos

Description: Recent experimental results have provided unambiguous evidence that neutrinos have a small but finite mass and mix from one type into another. The phenomenon of neutrino mixing is characterized by the coupling between the neutrino flavor (nu{sub e,mu,tau}) and mass eigenstates (nu{sub 1,2,3}) and the associated mixing angles. Previous neutrino oscillation experiments have determined two of the three mixing angles in the neutrino mixing matrix, U{sub MNSP}. Using multiple neutrino detectors plac… more
Date: July 13, 2004
Creator: Heeger, Karsten M.; Freedman, Stuart J.; Kadel, Richard W. & Luk, Kam-Biu
Partner: UNT Libraries Government Documents Department
open access

Organization and management of the plant safety evaluation of the VVER-440/230 units at Novovoronezh.

Description: As part of the Soviet-Designed Reactor Safety (SDRS) element of the International Nuclear Safety Program (INSP), the US Department of Energy (US DOE) is funding a plant safety evaluation (PSE) project for the Novovoronezh Nuclear Power Plant (NvNPP). The Novovoronezh PSE Project is a multi-faceted project with participants from sixteen different international organizations from five different countries scattered across eleven time zones. The purpose of this project is to provide a thorough Prob… more
Date: May 13, 1999
Creator: Afshar, C. M.; Pizzica, P.; Puglia, W. J. & Rozin, V.
Partner: UNT Libraries Government Documents Department
open access

Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

Description: This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristic… more
Date: March 13, 2011
Creator: Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F. et al.
Partner: UNT Libraries Government Documents Department
open access

Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade

Description: The regulatory requirement to develop an upgraded safety basis for a DOE Nuclear Facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830). Subpart B of 10 CFR 830, ''Safety Basis Requirements,'' requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, … more
Date: May 13, 2003
Creator: Sharp, Gregg L. & McCracken, Richard T.
Partner: UNT Libraries Government Documents Department
open access

An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design

Description: An attractive blanket concept for the fusion reactor is the dual coolant Pb-17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb-17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetohydrodynamic (MHD) insulation to reduce the impact from the MHD pressure drop of the circulating Pb-17L… more
Date: May 13, 2005
Creator: Wong, C. C.; Malang, S.; Sawan, M.; Dagher, M.; Smolentsev, S.; Merrill, B. et al.
Partner: UNT Libraries Government Documents Department
open access

Building Public Confidence in Nuclear Activities

Description: Achieving public acceptance has become a central issue in discussions regarding the future of nuclear power and associated nuclear activities. Effective public communication and public participation are often put forward as the key building blocks in garnering public acceptance. A recent international workshop in Finland provided insights into other features that might also be important to building and sustaining public confidence in nuclear activities. The workshop was held in Finland in close… more
Date: February 13, 2002
Creator: Isaacs, T
Partner: UNT Libraries Government Documents Department
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HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

Description: The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is loc… more
Date: October 13, 2011
Creator: Austin, W. & Brinkley, D.
Partner: UNT Libraries Government Documents Department
open access

Clinch River Breeder Reactor Plant steam generator: FEW tube test model post test examination

Description: The Steam Generator Few Tube Test (FTT) is part of an extensive testing program being carried out in support of the Clinch River Breeder Reactor Plant (CRBRP) steam generator design. The testing of full-length seven-tube evaporator and three-tube superheater models of the CRBRP design was conducted to provide steady-state thermal/hydraulic performance data to full power per tube and to verify the absence of multi-year endurance problems. The problems encountered with the mechanical features of … more
Date: September 13, 1979
Creator: Impellezzeri, J. R. & Camaret, T. L.
Partner: UNT Libraries Government Documents Department
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Investigation of vessel exterior air cooling for a HLMC reactor

Description: The Secure Transportable Autonomous Reactor (STAR) concept under development at Argonne National Laboratory provides a small (300 MWt) reactor module for steam supply that incorporates design features to attain proliferation resistance, heightened passive safety, and improved cost competitiveness through extreme simplification. Examples are the achievement of 100%+ natural circulation heat removal from the low power density/low pressure drop ultra-long lifetime core and utilization of lead-bism… more
Date: January 13, 2000
Creator: Sienicki, J. J. & Spencer, B. W.
Partner: UNT Libraries Government Documents Department
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