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Fresh-Core Reload of the Neutron Radiography (NRAD) Reactor with Uranium(20)-Erbium-Zirconium-Hydride Fuel

Description: The neutron radiography (NRAD) reactor is a 250 kW TRIGA® (Training, Research, Isotopes, General Atomics) Mark II , tank-type research reactor currently located in the basement, below the main hot cell, of the Hot Fuel Examination Facility (HFEF) at the Idaho National Laboratory (INL). It is equipped with two beam tubes with separate radiography stations for the performance of neutron radiography irradiation on small test components. The initial critical configuration developed during the fuel … more
Date: March 1, 2013
Creator: Bess, John D.; Maddock, Thomas L.; Marshall, Margaret A. & Montierth, Leland M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Technical Basis and Guidance for Advanced SMR Function Allocation

Description: This report presents the results from three key activities for FY13 that influence the definition of new concepts of operations for advanced Small Modular Reactors (AdvSMR: a) the development of a framework for the analysis of the functional environmental, and structural attributes, b) the effect that new technologies and operational concepts would have on the way functions are allocated to humans or machines or combinations of the two, and c) the relationship between new concepts of operations… more
Date: September 1, 2013
Creator: Hugo, Jacques; Gertman, David; Joe, Jeffrey; Farris, Ronal; Whaley, April & Medema, Heather
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HTR-PROTEUS Pebble Bed Experimental Program Cores 1, 1A, 2, and 3: Hexagonal Close Packing with a 1:2 Moderator-to-Fuel Pebble Ratio

Description: In its deployment as a pebble bed reactor (PBR) critical facility from 1992 to 1996, the PROTEUS facility was designated as HTR-PROTEUS. This experimental program was performed as part of an International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) on the Validation of Safety Related Physics Calculations for Low Enriched HTGRs. Within this project, critical experiments were conducted for graphite moderated LEU systems to determine core reactivity, flux and power profiles, rea… more
Date: March 1, 2013
Creator: Bess, John D.; Dolphin, Barbara H.; Sterbentz, James W.; Snoj, Luka; Lengar, Igor & Köberl, Oliver
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CRITICAL CONFIGURATION AND PHYSICS MEASUREMENTS FOR BERYLLIUM REFLECTED ASSEMBLIES OF U(93.15)O2 FUEL RODS (1.506-CM PITCH)

Description: Cadmium ratios were measured with enriched uranium metal foils at various locations in the assembly with the fuel tube at the 1.506-cm spacing. They are described in the following subsections. The experiment configuration was the same as the first critical configuration described in HEU-COMP-FAST-004 (Case 1). The experimenter placed 0.75-cm-diameter × 0.010-cm-thick 93.15%-235U-enriched uranium metal foils with and without 0.051-cm-thick cadmium covers at various locations in the core and top … more
Date: March 1, 2013
Creator: Marshall, Margaret A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report - Assessment of Testing Options for the NTR at the INL

Description: One of the main technologies that can be developed to dramatically enhance the human exploration of space is the nuclear thermal rocket (NTR). Several studies over the past thirty years have shown that the NTR can reduce the cost of a lunar outpost, reduce the risk of a human mission to Mars, enable fast transits for most missions throughout the solar system, and reduce the cost and time for robotic probes to deep space. Three separate committees of the National Research Council of the National… more
Date: February 1, 2013
Creator: Howe, Steven D; McLing, Travis L; McCurry, Michael & Plummer, Mitchell A
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validation of FSP Reactor Design with Sensitivity Studies of Beryllium-Reflected Critical Assemblies

Description: The baseline design for space nuclear power is a fission surface power (FSP) system: sodium-potassium (NaK) cooled, fast spectrum reactor with highly-enriched-uranium (HEU)-O2 fuel, stainless steel (SS) cladding, and beryllium reflectors with B4C control drums. Previous studies were performed to evaluate modeling capabilities and quantify uncertainties and biases associated with analysis methods and nuclear data. Comparison of Zero Power Plutonium Reactor (ZPPR)-20 benchmark experiments with th… more
Date: February 1, 2013
Creator: Bess, John D. & Marshall, Margaret A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Benchmark Evaluation of the Medium-Power Reactor Experiment Program Critical Configurations

Description: A series of small, compact critical assembly (SCCA) experiments were performed in 1962-1965 at the Oak Ridge National Laboratory Critical Experiments Facility (ORCEF) for the Medium-Power Reactor Experiment (MPRE) program. The MPRE was a stainless-steel clad, highly enriched uranium (HEU)-O2 fuelled, BeO reflected reactor design to provide electrical power to space vehicles. Cooling and heat transfer were to be achieved by boiling potassium in the reactor core and passing vapor directly through… more
Date: February 1, 2013
Creator: Marshall, Margaret A. & Bess, John D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Critical Configuration and Physics Measurements for Assemblies of U(93.15)O2 Fuel Rods (1.506-cm Pitch)

Description: A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (ORNL’s) Critical Experiments Facility (CEF) in support of the Medium-Power Reactor Experiments (MPRE) program. In the late 1950s, efforts were made to study “power plants for the production of electrical power in space vehicles.”(a) The MPRE program was a part of those efforts and studied the feasibility of a stainless-steel system, boiling potassium 1 MW(t), or about 140 kW(e), reactor. The progr… more
Date: March 1, 2013
Creator: Marshall, Margaret A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preconceptual Feasibility Study to Evaluate Alternative Means to Produce Plutonium-238

Description: There is currently no large-scale production of 238Pu in the United States. Feasibility studies were performed at the Idaho National Laboratory to assess the capability of developing alternative 238Pu production strategies. Initial investigations indicate potential capability to provision radioisotope-powered systems for future space exploration endeavors. For the short term production of 238Pu, sealed canisters of dilute 237Np solution in nitric acid could be irradiated in the Advanced Test Re… more
Date: February 1, 2013
Creator: Bess, John D. & Everson, Matthew S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

Description: At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commissi… more
Date: December 17, 2013
Creator: Chopra, Omesh K.; Diercks, Dwight R.; Ma, David Chia-Chiun & Garud, Yogendra S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

Description: The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale… more
Date: March 1, 2013
Creator: Boring, Ronald L.; Agarwal, Vivek; Fitzgerald, Kirk; Hugo, Jacques & Hallbert, Bruce
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORES 9 & 10: COLUMNAR HEXAGONAL POINT-ON-POINT PACKING WITH A 1:1 MODERATOR-TO-FUEL PEBBLE RATIO

Description: PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PR… more
Date: March 1, 2013
Creator: Bess, John D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORES 5, 6, 7, & 8: COLUMNAR HEXAGONAL POINT-ON-POINT PACKING WITH A 1:2 MODERATOR-TO-FUEL PEBBLE RATIO

Description: PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PR… more
Date: March 1, 2013
Creator: Bess, John D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORE 4: RANDOM PACKING WITH A 1:1 MODERATOR-TO-FUEL PEBBLE RATIO

Description: In its deployment as a pebble bed reactor (PBR) critical facility from 1992 to 1996, the PROTEUS facility was designated as HTR-PROTEUS. This experimental program was performed as part of an International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) on the Validation of Safety Related Physics Calculations for Low Enriched HTGRs. Within this project, critical experiments were conducted for graphite moderated LEU systems to determine core reactivity, flux and power profiles, rea… more
Date: March 1, 2013
Creator: Bess, John D. & Montierth, Leland M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Concepts for Mulitiple Application Thermal Reactor for Irradiation eXperiments (MATRIX)

Description: The Advanced Test Reactor (ATR) is a high power density test reactor specializing in fuel and materials irradiation. For more than 45 years, the ATR has provided irradiations of materials and fuels testing along with radioisotope production. Originally operated primarily in support of the Offcie of Naval Reactors (NR), the mission has gradually expanded to cater to other customers, such as the DOE Office of Nuclear Energy (NE), private industry, and universities. Unforeseen circumstances may le… more
Date: September 1, 2013
Creator: Pope, Michael A.; Gougar, Hans D. & Ryskamp, John M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Additions to the ICSBEP and IRPhEP Handbooks since NCSD 2009

Description: High-quality integral benchmark experiments have always been a priority for criticality safety. However, interest in integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of future criticality safety needs to support next generation reactor and advanced fuel cycle concepts. The importance of drawing upon existing benchmark data is becoming more apparent because of dwindling availability of critical facilities worldwide… more
Date: October 1, 2013
Creator: Bess, John D.; Briggs, J. Blair; Gulliford, Jim & Hill, Ian
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Wetland Water Cooling Partnership: The Use of Constructed Wetlands to Enhance Thermoelectric Power Plant Cooling and Mitigate the Demand of Surface Water Use

Description: Through the Phase I study segment of contract #DE-NT0006644 with the U.S. Department of Energy’s National Energy Technology Laboratory, Applied Ecological Services, Inc. and Sterling Energy Services, LLC (the AES/SES Team) explored the use of constructed wetlands to help address stresses on surface water and groundwater resources from thermoelectric power plant cooling and makeup water requirements. The project objectives were crafted to explore and develop implementable water conservation and … more
Date: September 30, 2013
Creator: Apfelbaum, Steven; Duvall, Kenneth; Nelson, Theresa; Mensing, Douglas; Bengtson, Harlan; Eppich, John et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Study of Air Ingress Across the Duct During the Accident Conditions

Description: The goal of this project is to study the fundamental physical phenoena associated with air ingress in very high temperature reactors (VHTRs). Air ingress may occur due to a nupture of primary piping and a subsequent breach in the primary pressure boundary in helium-cooled and graphite-moderated VHTRs. Significant air ingress is a concern because it introduces potential to expose the fuel, graphite support rods, and core to a risk of severe graphite oxidation. Two of the most probable air ingres… more
Date: May 6, 2013
Creator: Hassan, Yassin
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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