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Addendum to NuMI shielding assessment

Description: The original safety assessment and the Safety Envelope for the NuMI beam line corresponds to 400 kW of beam power. The Main Injector is currently capable of and approved for producing 500 kW of beam power2. However, operation of the NuMI beam line at 400 kW of power brings up the possibility of an occasional excursion above 400 kW due to better than usual tuning in one of the machines upstream of the NuMI beam line. An excursion above the DOE approved Safety Envelope will constitute a safety vi… more
Date: October 1, 2007
Creator: Vaziri, Kamran
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AECL/US INERI - Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in Power Reactors -- Fuel Requirements and Down-Select Report

Description: The U.S. Advanced Fuel Cycle Program and the Atomic Energy Canada Ltd (AECL) seek to develop and demonstrate the technologies needed to minimize the overall Pu and minor actinides present in the light water reactor (LWR) nuclear fuel cycles. It is proposed to reuse the Pu from LWR spent fuel both for the energy it contains and to decrease the hazard and proliferation impact resulting from storage of the Pu and minor actinides. The use of fuel compositions with a combination of U and Pu oxide (M… more
Date: June 1, 2005
Creator: Carmack, William; Lee, Randy D.; Medvedev, Pavel; Meyer, Mitch; Todosow, Michael; Hamilton, Holly B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN C-REACTOR DISASSEMBLY BASIN

Description: C-reactor disassembly basin is being prepared for deactivation and decommissioning (D and D). D and D activities will consist primarily of immobilizing contaminated scrap components and structures in a grout-like formulation. The disassembly basin will be the first area of the C-reactor building that will be immobilized. The scrap components contain aluminum alloy materials. Any aluminum will corrode very rapidly when it comes in contact with the very alkaline grout (pH > 13), and as a resul… more
Date: July 12, 2011
Creator: Wiersma, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN THE R AND P REACTOR VESSELS

Description: The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it comes in contact with the alkaline grout materials and as a result produces hydrogen gas. To address this potential deflagration/explosion hazard, the Materials Science and Technology Directorate (MS&am… more
Date: October 29, 2009
Creator: Wiersma, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN THE R- AND P-REACTOR VESSELS

Description: The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it comes in contact with the alkaline grout materials and as a result produces hydrogen gas. To address this potential deflagration/explosion hazard, the Materials Science and Technology Directorate (MS&am… more
Date: December 29, 2009
Creator: Wiersma, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Assessment of the Potential for Hydrogen Generation During Grouting Operations in the R and P Reactor Vessels

Description: The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D and D). D and D activities consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it comes in contact with the alkaline grout materials and as a result produces hydrogen gas. To address this potential deflagration/explosion hazard, the Materials Science and Technology Directorate (MS and T) … more
Date: May 24, 2010
Creator: Wiersma, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Benchmark Evaluation of Plutonium Hemispheres Reflected by Steel and Oil

Description: During the period from June 1967 through September 1969 a series of critical experiments was performed at the Rocky Flats Critical Mass Laboratory with spherical and hemispherical plutonium assemblies as nested hemishells as part of a Nuclear Safety Facility Experimental Program to evaluate operational safety margins for the Rocky Flats Plant. These assemblies were both bare and fully or partially oil-reflected. Many of these experiments were subcritical with an extrapolation to critical config… more
Date: June 1, 2008
Creator: Bess, John Darrell
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Code Qualification of Structural Materials for AFCI Advanced Recycling Reactors.

Description: This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Ca… more
Date: May 31, 2012
Creator: Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R. K. & Sham, T.-L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Computational fluid dynamics analyses of lateral heat conduction, coolant azimuthal mixing and heat transfer predictions in a BR2 fuel assembly geometry.

Description: To support the analyses related to the conversion of the BR2 core from highly-enriched (HEU) to low-enriched (LEU) fuel, the thermal-hydraulics codes PLTEMP and RELAP-3D are used to evaluate the safety margins during steady-state operation (PLTEMP), as well as after a loss-of-flow, loss-of-pressure, or a loss of coolant event (RELAP). In the 1-D PLTEMP and RELAP simulations, conduction in the azimuthal and axial directions is not accounted. The very good thermal conductivity of the cladding and… more
Date: May 23, 2011
Creator: Tzanos, C. P. & Dionne, B. (Nuclear Engineering Division)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Critical Current Metrology for Nb3Sn Conductor Development: Final Technical Report

Description: NIST has played a key role in many of the one-on-one, domestic, and international interlaboratory comparisons of measurements on superconductors. The history of interlaboratory comparisons of measurements on superconductors tells us that careful measurement methods are needed to obtain consistent results. Inconsistent results can lead to many problems including: a mistrust of the results of others, unfair advantages in commerce, and erroneous feedback in the optimization of conductor performanc… more
Date: May 31, 2011
Creator: Goodrich, Loren F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Definition of a Twelve-Point Polygonal SAA Boundaryfor the GLAST Mission

Description: The Gamma-Ray Large Area Space Telescope (GLAST), set to launch in early 2008, detects gamma rays within a huge energy range of 100 MeV - 300 GeV. Background cosmic radiation interferes with such detection resulting in confusion over distinguishing cosmic from gamma rays encountered. This quandary is resolved by encasing GLAST's Large Area Telescope (LAT) with an Anti-Coincidence Detector (ACD), a device which identifies and vetoes charged particles. The ACD accomplishes this through plastic sc… more
Date: August 29, 2007
Creator: Djomehri, Sabra I. & /UC, Santa Cruz /SLAC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of in-pile degradation of the meat thermal conductivity on the maximum temperature of the plate-type U-Mo dispersion fuels

Description: Effect of in-pile degradation of thermal conductivity on the maximum temperature of the plate-type research reactor fuels has been assessed using the steady-state heat conduction equation and assuming convection cooling. It was found that due to very low meat thickness, characteristic for this type of fuel, the effect of thermal conductivity degradation on the maximum fuel temperature is minor. For example, the fuel plate featuring 0.635 mm thick meat operating at heat flux of 600 W/cm2 would e… more
Date: November 1, 2009
Creator: Medvedev, Pavel G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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ESTIMATED SIL LEVELS AND RISK COMPARISONS FOR RELIEF VALVES AS A FUNCTION OF TIME-IN-SERVICE

Description: Risk-based inspection methods enable estimation of the probability of spring-operated relief valves failing on demand at the United States Department of Energy's Savannah River Site (SRS) in Aiken, South Carolina. The paper illustrates an approach based on application of the Frechet and Weibull distributions to SRS and Center for Chemical Process Safety (CCPS) Process Equipment Reliability Database (PERD) proof test results. The methodology enables the estimation of ANSI/ISA-84.00.01 Safety Int… more
Date: March 26, 2012
Creator: Harris, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental Measurement of Flow Phenomena in a VHTR Lower Plenum Model

Description: The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further development by the Generation IV International Forum. In addition this system is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. In preparation for the thermal-hydraulics and safety analyses that will be required to confirm the performance of the NGNP, work has b… more
Date: June 1, 2006
Creator: Jr., Hugh M. McIlroy; Condie, Keith G.; McCreery, Glenn E.; McEligot, Donald M. & Pink, Robert J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents

Description: The US Department of Energy is performing research and development (R&D) that focuses on key phenomena that are important during challenging scenarios that may occur in the Next Generation Nuclear Plant (NGNP) Program / GEN-IV Very High Temperature Reactor (VHTR). Phenomena identification and ranking studies (PIRT) to date have identified the air ingress event, following on the heels of a VHTR depressurization, as very important (Schultz et al., 2006). Consequently, the development of advanced … more
Date: December 1, 2008
Creator: Oh, Chang Ho; Kim, Eung Soo; No, Hee Cheon & Cho, Nam Zin
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility analyses for HEU to LEU fuel conversion of the LAUE Langivin Institute (ILL) High Flux Reactor (RHF).

Description: The High Flux Reactor (RHF) of the Laue Langevin Institute (ILL) based in Grenoble, France is a research reactor designed primarily for neutron beam experiments for fundamental science. It delivers one of the most intense neutron fluxes worldwide, with an unperturbed thermal neutron flux of 1.5 x 10{sup 15} n/cm{sup 2}/s in its reflector. The reactor has been conceived to operate at a nuclear power of 57 MW but currently operates at 52 MW. The reactor currently uses a Highly Enriched Uranium (H… more
Date: August 19, 2010
Creator: Stevens, J.; A., Tentner.; Bergeron, A. & Division, Nuclear Engineering
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FINAL REPORT on Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents

Description: The U.S. Department of Energy is performing research and development that focuses on key phenomena that are important during challenging scenarios that may occur in the Next Generation Nuclear Plant (NGNP)/Generation IV very high temperature reactor (VHTR). Phenomena Identification and Ranking studies to date have identified the air ingress event, following on the heels of a VHTR depressurization, as very important. Consequently, the development of advanced air ingress-related models and verifi… more
Date: January 1, 2011
Creator: Oh, Chang H.; Kim, Eung S.; NO, Hee C. & Cho, Nam Z.
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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Final Technical Report for the MIT Annular Fuel Research Project

Description: MIT-NFC-PR-082 (January 2006) Abstract This summary provides an overview of the results of the U.S. DOE funded NERI (Nuclear Research ENergy Initiative) program on development of the internally and externally cooled annular fuel for high power density PWRs. This new fuel was proposed by MIT to allow a substantial increase in poer density (on the order of 30% or higher) while maintaining or improving safety margins. A comprehensive study was performed by a team consisting of MIT (lead organizati… more
Date: January 31, 2008
Creator: Kazimi, Mujid S. & Hejzlar, Pavel
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Global nuclear energy partnership fuels transient testing at the Sandia National Laboratories nuclear facilities : planning and facility infrastructure options.

Description: The Global Nuclear Energy Partnership fuels development program is currently developing metallic, oxide, and nitride fuel forms as candidate fuels for an Advanced Burner Reactor. The Advance Burner Reactor is being designed to fission actinides efficiently, thereby reducing the long-term storage requirements for spent fuel repositories. Small fuel samples are being fabricated and evaluated with different transuranic loadings and with extensive burnup using the Advanced Test Reactor. During the … more
Date: October 1, 2007
Creator: Kelly, John E.; Wright, Steven Alan; Tikare, Veena; MacLean, Heather J. (Idaho National Laboratory, Idaho Falls, ID); Parma, Edward J., Jr.; Peters, Curtis D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heartbeat Model for Component Failure in Simulation of Plant Behavior

Description: As part of the Department of Energy’s “Light Water Reactor Sustainability Program” (LWRSP), tools and methodology for risk-informed characterization of safety margin are being developed for use in supporting decision-making on plant life extension after the first license renewal. Beginning with the traditional discussion of “margin” in terms of a “load” (a physical challenge to system or component function) and a “capacity” (the capability of that system or component to accommodate the challeng… more
Date: March 1, 2011
Creator: Youngblood, R. W.; Nourgaliev, R. R.; Kelly, D. L.; Smith, C. L. & Dinh, T-N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A High Temperature, non-TRISO Fuel and Clad Design with Commercial-Grade Enrichment for the Prismatic Block Very High Temperature Reactor

Description: The prismatic block Very High Temperature Reactor (VHTR) is a leading Generation IV reactor concept. This reactor with its relatively low core power density and large graphite mass currently satisfies the fundamental goals of the Generation IV charter. However, modifications can be made to the fuel and clad design, such that (1) VHTR uranium enrichment can be lowered to near commercial-grade pressurized water reactor (PWR) enrichments, (2) fuel burnups are extended, and (3) the thermal safety m… more
Date: November 1, 2005
Creator: Sterbentz, James W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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