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INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

Description: Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and… more
Date: September 1, 2008
Creator: Briggs, J. Blair; Scott, Lori; Sartori, Enrico & Rugama, Yolanda
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A Virtual Reality Framework to Optimize Design, Operation and Refueling of GEN-IV Reactors.

Description: many GEN-IV candidate designs are currently under investigation. Technical issues related to material, safety and economics are being addressed at research laboratories, industry and in academia. After safety, economic feasibility is likely to be the most important crterion in the success of GEN-IV design(s). Lessons learned from the designers and operators of GEN-II (and GEN-III) reactors must play a vital role in achieving both safety and economic feasibility goals.
Date: April 23, 2008
Creator: Rizwan-uddin; Karancevic, Nick; Markidis, Stefano; Dixon, Joel; Luo, Cheng & Reynolds, Jared
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication Flaw Density and Distribution In Repairs to Reactor Pressure Vessel and Piping Welds

Description: The Pacific Northwest National Laboratory is developing a generalized fabrication flaw distribution for the population of nuclear reactor pressure vessels and for piping welds in U.S. operating reactors. The purpose of the generalized flaw distribution is to predict component-specific flaw densities. The estimates of fabrication flaws are intended for use in fracture mechanics structural integrity assessments. Structural integrity assessments, such as estimating the frequency of loss-of-coolant… more
Date: April 1, 2008
Creator: Schuster, G. J.; Simonen, F. A. & Doctor, S. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NGNP Process Heat Utilization: Liquid Metal Phase Change Heat Exchanger

Description: One key long-standing issue that must be overcome to fully realize the successful growth of nuclear power is to determine other benefits of nuclear energy apart from meeting the electricity demands. The Next Generation Nuclear Plant (NGNP) will most likely be producing electricity and heat for the production of hydrogen and/or oil retrieval from oil sands and oil shale to help in our national pursuit of energy independence. For nuclear process heat to be utilized, intermediate heat exchange is … more
Date: September 1, 2008
Creator: Sabharwall, Piyush; Patterson, Mike; Utgikar, Vivek & Gunnerson, Fred
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The Emma Commissioning Procedure

Description: The author begins with a brief review of the goals of the EMMA experiment. He then describe two stages of EMMA commissioning. The first stage is simply to get the beam to circulate a full turn in the ring, and is done only once during the course of the experiment. The second stage will be repeated several times, at least once for each lattice configuration, and involves two parts: setting the required values for the machine parameters, and determining the tunes and time of flight as a function … more
Date: November 5, 2007
Creator: Berg, J. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Estimating Loss-of-Coolant Accident Frequencies for the Standardized Plant Analysis Risk Models

Description: The U.S. Nuclear Regulatory Commission maintains a set of risk models covering the U.S. commercial nuclear power plants. These standardized plant analysis risk (SPAR) models include several loss-of-coolant accident (LOCA) initiating events such as small (SLOCA), medium (MLOCA), and large (LLOCA). All of these events involve a loss of coolant inventory from the reactor coolant system. In order to maintain a level of consistency across these models, initiating event frequencies generally are base… more
Date: September 1, 2008
Creator: Eide, S. A.; Rasmuson, D. M. & Atwood, C. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cobra-IE Evaluation by Simulation of the NUPEC BWR Full-Size Fine-Mesh Bundle Test (BFBT)

Description: The COBRA-IE computer code is a thermal-hydraulic subchannel analysis program capable of simulating phenomena present in both PWRs and BWRs. As part of ongoing COBRA-IE assessment efforts, the code has been evaluated against experimental data from the NUPEC BWR Full-Size Fine-Mesh Bundle Tests (BFBT). The BFBT experiments utilized an 8 x 8 rod bundle to simulate BWR operating conditions and power profiles, providing an excellent database for investigation of the capabilities of the code. Benchm… more
Date: April 26, 2006
Creator: Burns, C. J. and Aumiler, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Monitoring the Thermal Power of Nuclear Reactors with a Prototype Cubic Meter Antineutrino Detector

Description: In this paper, we estimate how quickly and how precisely a reactor's operational status and thermal power can be monitored over hour to month time scales, using the antineutrino rate as measured by a cubic meter scale detector. Our results are obtained from a detector we have deployed and operated at 25 meter standoff from a reactor core. This prototype can detect a prompt reactor shutdown within five hours, and monitor relative thermal power to 3.5% within 7 days. Monitoring of short-term powe… more
Date: June 27, 2007
Creator: Bernstein, A; Bowden, N; Misner, A & Palmer, T
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fission Product Gamma-Ray Line Pairs Sensitive to Fissile Material and Neutron Energy

Description: The beta-delayed gamma-ray spectra from the fission of {sup 235}U, {sup 238}U, and {sup 239}Pu by thermal and near-14-MeV neutrons have been measured for delay times ranging from 1 minute to 14 hours. Spectra at all delay times contain sets of prominent gamma-ray lines with intensity ratios that identify the fissile material and distinguish between fission induced by low-energy or high-energy neutrons.
Date: November 15, 2007
Creator: Marrs, R. E.; Norman, E. B.; Burke, J. T.; Macri, R. A.; Shugart, H. A.; Browne, E. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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High Brightness Neutron Source for Radiography

Description: This research and development program was designed to improve nondestructive evaluation of large mechanical objects by providing both fast and thermal neutron sources for radiography. Neutron radiography permits inspection inside objects that x-rays cannot penetrate and permits imaging of corrosion and cracks in low-density materials. Discovering of fatigue cracks and corrosion in piping without the necessity of insulation removal is possible. Neutron radiography sources can provide for the non… more
Date: December 8, 2008
Creator: Cremer, J. T.; Piestrup, Melvin A.; Gary, Charles K.; Harris, Jack L.; Williams, David J.; Jones, Glenn E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of Pillar-Structured Thermal Neutron Detectors

Description: Pillar detector is an innovative solid state device structure that leverages advanced semiconductor fabrication technology to produce a device for thermal neutron detection. State-of-the-art thermal neutron detectors have shortcomings in achieving simultaneously high efficiency, low operating voltage while maintaining adequate fieldability performance. By using a 3-dimensional silicon PIN diode pillar array filled with isotopic boron 10, ({sup 10}B) a high efficiency device is theoretically pos… more
Date: November 19, 2007
Creator: Nikolic, R. J.; Conway, A. M.; Reinhardt, C. E.; Graff, R. T.; Wang, T. F.; Deo, N. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Sensitivity and representativity analysis of past experiments with respect to ABTR system.

Description: A comprehensive validation analysis has been performed that incorporates representativity of multiple parameters, experiments, reference designs, and adjustment of the nuclear data. The work involves a new representativity study among selected reactor designs and several experiments. Application, using existing experiments, to reference design like the ABTR and the SFR has demonstrated that it is possible to achieve a significant reduction of uncertainty on the main integral parameters of inter… more
Date: August 29, 2007
Creator: Aliberti, G.; Palmiotti, G. & Salvatores, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Over Batch Analysis for the LLNL Plutonium Packaging System (PuPS)

Description: This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria (Reference 1, Section 6.a.3) about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Live… more
Date: November 19, 2007
Creator: Riley, D & Dodson, K
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2

Description: This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-… more
Date: February 25, 2008
Creator: Winterholler, Kirk
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results of LLNL investigation of NYCT data sets

Description: Upon examination we have concluded that none of the alarms indicate the presence of a real threat. A brief history and results from our examination of the NYCT ASP occupancy data sets dated from 2007-05-14 19:11:07 to 2007-06-20 15:46:15 are presented in this letter report. When the ASP data collection campaign at NYCT was completed, rather than being shut down, the Canberra ASP annunciator box was unplugged leaving the data acquisition system running. By the time it was discovered that the ASP… more
Date: August 1, 2007
Creator: Sale, K.; Harrison, M.; Guo, M. & Groza, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alloys for 1000 degree C service in the Next Generation Nuclear Plant NERI 05-0191

Description: The objective of the proposed research is to define strategies for the improvement of alloys for structural components, such as the intermediate heat exchanger and primary-to-secondary piping, for service at 1000 degree C in the He environment of the NGNP. Specifically, we will investigate the oxidation/carburization behavior and microstructure stability and how these processes affect creep. While generating this data, the project will also develop a fundamental understanding of how impurities … more
Date: January 15, 2009
Creator: Was, Gary S.; Jones, J.W. & Pollock, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Data Compilation for AGR-3/4 Designed-to-Fail (DTF) Fuel Particle Batch LEU04-02DTF

Description: This document is a compilation of coating and characterization data for the AGR-3/4 designed-to-fail (DTF) particles. The DTF coating is a high density, high anisotropy pyrocarbon coating of nominal 20 {micro}m thickness that is deposited directly on the kernel. The purpose of this coating is to fail early in the irradiation, resulting in a controlled release of fission products which can be analyzed to provide data on fission product transport. A small number of DTF particles will be included … more
Date: October 1, 2008
Creator: Hunn, John D & Miller, James Henry
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Direct Numerical Simulation of Interfacial Flows: Implicit Sharp-Interface Method (I-SIM)

Description: In recent work (Nourgaliev, Liou, Theofanous, JCP in press) we demonstrated that numerical simulations of interfacial flows in the presence of strong shear must be cast in dynamically sharp terms (sharp interface treatment or SIM), and that moreover they must meet stringent resolution requirements (i.e., resolving the critical layer). The present work is an outgrowth of that work aiming to overcome consequent limitations on the temporal treatment, which become still more severe in the presence … more
Date: January 1, 2008
Creator: Nourgaliev, Robert; Theofanous, Theo; Park, HyeongKae; Mousseau, Vincent & Knoll, Dana
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Is there a low energy enhancement in the photon strength function in molybdenum?

Description: Recent claims of a low energy enhancement in the photon strength function of {sup 96}Mo are investigated. Using the DANCE detector the gamma-ray spectra following resonance neutron capture was measured. The spectrum fitting method was used to indirectly extract a photon strength function from the gamma-ray spectra. No strong low energy enhancement in the photon strength function was found.
Date: January 30, 2008
Creator: Sheets, S A
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Proactive Management of Materials Degradation - A Review of Principles and Programs

Description: The U.S. Nuclear Regulatory Commission (NRC) has undertaken a program to lay the technical foundation for defining proactive actions so that future degradation of materials in light water reactors (LWRs) is limited and, thereby, does not diminish either the integrity of important LWR components or the safety of operating plants. This technical letter report was prepared by staff at Pacific Northwest National Laboratory in support of the NRC Proactive Management of Materials Degradation (PMMD) p… more
Date: August 28, 2008
Creator: Bond, Leonard J.; Doctor, Steven R. & Taylor, Theodore T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Global Monte Carlo Simulation with High Order Polynomial Expansions

Description: The functional expansion technique (FET) was recently developed for Monte Carlo simulation. The basic idea of the FET is to expand a Monte Carlo tally in terms of a high order expansion, the coefficients of which can be estimated via the usual random walk process in a conventional Monte Carlo code. If the expansion basis is chosen carefully, the lowest order coefficient is simply the conventional histogram tally, corresponding to a flat mode. This research project studied the applicability of u… more
Date: December 13, 2007
Creator: Martin, William R.; Holloway, James Paul; Banerjee, Kaushik; Cheatham, Jesse & Conlin, Jeremy
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A New Class of Functionally Graded Cearamic-Metal Composites for Next Generation Very High Temperature Reactors

Description: Generation IV Very High Temperature power generating nuclear reactors will operate at temperatures greater than 900 oC. At these temperatures, the components operating in these reactors need to be fabricated from materials with excellent thermo-mechanical properties. Conventional pure or composite materials have fallen short in delivering the desired performance. New materials, or conventional materials with new microstructures, and associated processing technologies are needed to meet these ma… more
Date: May 1, 2008
Creator: Jain, Mohit; Skandan, Ganesh; Khose, Gordon E. & Maro, Judith
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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