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Laser ablation of concrete.

Description: Laser ablation is effective both as an analytical tool and as a means of removing surface coatings. The elemental composition of surfaces can be determined by either mass spectrometry or atomic emission spectroscopy of the atomized effluent. Paint can be removed from aircraft without damage to the underlying aluminum substrate, and environmentally damaged buildings and sculptures can be restored by ablating away deposited grime. A recent application of laser ablation is the removal of radioacti… more
Date: October 5, 1998
Creator: Savina, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Appendix A - A Summary of the Shutdown and Decommissioning Experience for Nuclear Power Plants in the United States and the Russian Federation. Appendix B - A Summary of the Regulatory Environment for the Shutdown and Decommissioning of Nuclear Power Plants in the United States and the Russian Federation. Appendix C - Recommended Outlines for Decommissioning Documentation

Description: No Description Available.
Date: October 20, 1998
Creator: Garrett, S.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP

Description: The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability… more
Date: October 20, 1999
Creator: Milchikov, A.; Hund, G. & Davidko, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NRC Support for the Kalinin (Vver) Probabilistic Risk Assessment

Description: The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed p… more
Date: October 26, 1998
Creator: Bley, D.; Diamond, D. J.; Chu, T. L.; Azarm, A.; Pratt, W. T.; Johnson, D. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparisons of HELIOS Calculated Isotope Concentrations to Measured Values for Several Reactor Systems

Description: Heavy metal and fission product noble gas concentrations in spent fuel from two different PWR'S were calculated using HELIOS and compared to measured results from the literature. It was found that for the U-235/U-238 and Pu-240/Pu-239 isotopic ratios, the HELIOS calculation agreed to within the experimental uncertainty. For the Xe-131/Xe-134 isotopic ratios, HELIOS tended to overestimate the result by up to 4%. Conversely for the Xe-132/Xe-134 ratios, HELIOS underestimated the result by a sligh… more
Date: October 21, 1998
Creator: Charlton, W. S.; Perry, R. T.; Fearey, B. L. & Parish, T. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Economic Study of Spent Nuclear Fuel Storage and Reprocessing Practices in Russia

Description: This report describes a study of nuclear power economics in Russia. It addresses political and institutional background factors which constrain Russia's energy choices in the short and intermediate run. In the approach developed here, political and institutional factors might dominate short-term decisions, but the comparative costs of Russia's fuel-cycle options are likely to constrain her long-term energy strategy. To this end, the authors have also formulated a set of policy questions which s… more
Date: October 1, 1997
Creator: Singer, C. E. & Miley, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium removal process development for LMFBR fuel subassemblies

Description: Two 37-pin scale models of Clinch River Breeder Reactor Plant fuel subassemblies were designed, fabricated and used at Westinghouse Advanced Reactors Division in the development and proof-testing of a rapid water-based sodium removal process for the ORNL Hot Experimental Facility, Liquid Metal Fast Breeder Reactor Fuel Reprocessing Cycle. Through a series of development tests on one of the models, including five (5) sodium wettings and three (3) high temperature sodium removal operations, optim… more
Date: October 1, 1981
Creator: Simmons, C.R. & Taylor, G.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Intercomparison of Results for a Pwr Rod Ejection Accident

Description: This study is part of an overall program to understand the uncertainty in best-estimate calculations of the local fuel enthalpy during the rod ejection accident. Local fuel enthalpy is used as the acceptance criterion for this design-basis event and can also be used to estimate fuel damage for the purpose of determining radiological consequences. The study used results from neutron kinetics models in PARCS, BARS, and CRONOS2, codes developed in the US, the Russian Federation, and France, respec… more
Date: October 1, 1999
Creator: Diamond, D. J.; Aronson, A.; Jo, J.; Avvakumov, A.; Malofeev, V.; Sidorov, V. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Synergistic failure of BWR internals

Description: Boiling Water Reactor (BWR) core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible … more
Date: October 25, 1999
Creator: Ware, A. G. & Chang, T. Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Estimating the Uncertainty in Reactivity Accident Neutronic Calculations

Description: A study of the uncertainty in calculations of the rod ejection accident in a pressurized water reactor is being carried out for the US Nuclear Regulatory Commission. This paper is a progress report on that study. Results are presented for the sensitivity of core energy deposition to the key parameters: ejected rod worth, delayed neutron fraction, Doppler reactivity coefficient, and fuel specific heat. These results can be used in the future to estimate the uncertainty in local fuel enthalpy giv… more
Date: October 26, 1998
Creator: Diamond, D. J.; Yang, C. Y. & Aronson, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The corrosion behavior of hafnium in high-temperature-water environments

Description: The high-temperature-water corrosion performance of hafnium is evaluated. Corrosion kinetic data are used to develop correlations that are a function of time and temperature. The evaluation is based on corrosion tests conducted in out-of-pile autoclaves and in out-of-flux locations of the Advanced Test Reactor (ATR) at temperatures ranging from 288 to 360 C. Similar to the corrosion behavior of unalloyed zirconium, the high-temperature-water corrosion response of hafnium exhibits three corrosio… more
Date: October 1, 1999
Creator: Rishel, D.M.; Smee, J.D. & Kammenzind, B.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Final report of comprehensive testing program for concrete at elevated temperatures

Description: The objective of this program was to define the variations in physical (thermal) and mechanical (strength) properties of limestone aggregate concrete and lightweight insulating concrete exposed to elevated temperatures that could occur as a result of a postulated large sodium spill in a lined LMFBR equipment cell. To meet this objective, five test series were conducted: (1) unconfined compression, (2) shear, (3) rebar bond, (4) sustained loading (creep), and (5) thermal properties. Mechanical p… more
Date: October 1, 1980
Creator: Oland, C. B.; Naus, D. J. & Robinson, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Theory and application of deterministic multidimensional pointwise energy lattice physics method

Description: The theory and application of deterministic, multidimensional, pointwise energy lattice physics methods are discussed. These methods may be used to solve the neutron transport equation in multidimensional geometries using near-continuous energy detail to calculate equivalent few-group diffusion theory constants that rigorously account for spatial and spectral self-shielding effects. A dual energy resolution slowing down algorithm is described which reduces the computer memory and disk storage r… more
Date: October 5, 1999
Creator: Zerkle, M.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Accuracy of the Quasistatic Method for Two-Dimensional Thermal Reactor Transients with Feedback

Description: An important aspect in the design and safe operation of a nuclear reactor is the behavior of a reactor in a transient, or nonsteady state, condition. This study shows that the quasistatic method is capable of producing highly accurate results, relative to the direct finite-difference method, for two-dimensional thermal reactor transients with feedback.
Date: October 23, 2001
Creator: Dodds, H.L. Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TRANSPORT CHARACTERISTICS OF SELECTED PWR LOCA GENERATED DEBRIS.

Description: In the unlikely event of a Loss of Coolant Accident (LOCA) in a pressurized water reactor (PWR), break jet impingement would dislodge thermal insulation from nearby piping, as well as other materials within the containment, such as paint chips, concrete dust, and fire barrier materials. Steam/water flows induced by the break and by the containment sprays would transport debris to the containment floor. Subsequently, debris would likely transport to and accumulate on the suction sump screens of … more
Date: October 1, 2000
Creator: MAJI, A. K.; MARSHALL, B. & AL, ET
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Closed ThUOX Fuel Cycle for LWRs with ADTT (ATW) Backend for the 21st Century

Description: A future nuclear energy scenario with a closed, thorium-uranium-oxide (ThUOX) fuel cycle and new light water reactors (TULWRs) supported by Accelerator Transmutation of Waste (ATW) systems could provide several improvements beyond today's once-through, UO{sub 2}-fueled nuclear technology. A deployment scenario with TULWRs plus ATWs to burn the actinides produced by these LWRs and to close the back-end of the ThUOX fuel cycle was modeled to satisfy a US demand that increases linearly from 80 GWe… more
Date: October 6, 1998
Creator: Beller, D. E.; Sailor, W. C. & Venneri, F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Chemical and Radiochemical Constituents in Water from Wells in the Vicinity of the Naval Reactors Facility, Idaho National Engineering and Environmental Laboratory, Idaho, 1996

Description: The U.S. Geological Survey, in response to a request from the U.S. Department of Energy's Pittsburgh Naval Reactors Office, Idaho Branch Office (IBO), samples water from 13 wells during 1996 as part of a long-term project to monitor water quality to the Snake River Plain aquifer in the vicinity of the Naval Reactors Facility (NRF), Idaho National Engineering and Environmental Laboratory, Idaho. The IBO requires information about the mobility of radionuclide- and chemical-waste constituents in t… more
Date: October 1, 1999
Creator: Knobel, L. L.; Bartholomay, R. C.; Tucker, B. J. & Williams, L. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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YOUR DESIGN PROBABLY NEEDS MORE VDUs

Description: The most frequent complaint of operators in modern computer-based control rooms is that there just are not enough video display units (VDUs). In this paper we examine the basis for this concern and try to understand the technical and historical reasons for this complaint, and its implications for the design of complex human-machine systems, including the number of VDUs in the control room. The overall aim of our work is to develop human factors guidance for the review of computer-based and mode… more
Date: October 8, 2001
Creator: O'Hara, John; Brown, William; Lewis, Paul & Persensky, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effects of Water Radiolysis in Water Cooled Reactors - Nuclear Energy Research Initiative (NERI) Program

Description: OAK B188 Quarterly Progress Report on NERI Proposal No.99-0010 for the Development of an Experiment and Calculation Based Model to Describe the Effects of Radiation on Non-standard Aqueous Systems Like Those Encountered in the Advanced Light Water Reactor
Date: October 1, 2000
Creator: Pimblott, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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