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FY2012 Summary of Tasks Completed on Proteus-Thermal Work.

Description: PROTEUS is a suite of the neutronics codes, both old and new, that can be used within the SHARP codes being developed under the NEAMS program. Discussion here is focused on updates and verification and validation activities of the SHARP neutronics code, DeCART, for application to thermal reactor analysis. As part of the development of SHARP tools, the different versions of the DeCART code created for PWR, BWR, and VHTR analysis were integrated. Verification and validation tests for the integrat… more
Date: June 6, 2012
Creator: Lee, C.H. & Smith, M.A. (Nuclear Engineering Division)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ASSESSMENT OF POSSIBLE CYCLE LENGTHS FOR FULLY-CERAMIC MICRO-ENCAPSULATED FUEL-BASED LIGHT WATER REACTOR CONCEPTS

Description: The use of TRISO-particle-based dispersion fuel within SiC matrix and cladding materials has the potential to allow the design of extremely safe LWRs with failure-proof fuel. This paper examines the feasibility of LWR-like cycle length for such a low enriched uranium fuel with the imposed constraint of strictly retaining the original geometry of the fuel pins and assemblies. The motivation for retaining the original geometry is to provide the ability to incorporate the fuel 'as-is' into existin… more
Date: April 1, 2012
Creator: Sen, R. Sonat; Pope, Michael A.; Ougouag, Abderrafi M.; Pasamehmetoglu, Kemal & Venneri, Francesco
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A COUPLED TH/NEUTRONICS/CRUD FRAMEWORK IN PREDICTION OF CIPS PHENOMENON

Description: A coupled TH/Neutronics/CRUD framework, which is able to simulate the CRUD deposits impact on CIPS phenomenon, was described in this paper. This framework includes the coupling among three essential physics, thermal-hydraulics, CRUD and neutronics. The overall framework was implemented by using the CFD software STAR-CCM+, developing CRUD codes, and using the neutronics code DeCART. The coupling was implemented by exchanging data between softwares using intermediate exchange files. A typical 3 b… more
Date: April 1, 2012
Creator: Zou, Ling; Zhang, Hongbin; Gehin, Jess & Kochunas, Brendan
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reactor Physics Behavior of Transuranic-Bearing TRISO-Particle Fuel in a Pressurized Water Reactor

Description: Calculations have been performed to assess the neutronic behavior of pins of Fully-Ceramic Micro-encapsulated (FCM) fuel in otherwise-conventional Pressurized Water Reactor (PWR) fuel pins. The FCM fuel contains transuranic (TRU)-only oxide fuel in tri-isotropic (TRISO) particles with the TRU loading coming from the spent fuel of a conventional LWR after 5 years of cooling. Use of the TRISO particle fuel would provide an additional barrier to fission product release in the event of cladding fai… more
Date: April 1, 2012
Creator: Pope, Michael A.; Sen, R. Sonat; Ougouag, Abderrafi M.; Youinou, Gilles & Boer, Brian
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Advanced Fuels for LWRs: Fully-Ceramic Microencapsulated and Related Concepts FY 2012 Interim Report

Description: This report summarizes the progress in the Deep Burn project at Idaho National Laboratory during the first half of fiscal year 2012 (FY2012). The current focus of this work is on Fully-Ceramic Microencapsulated (FCM) fuel containing low-enriched uranium (LEU) uranium nitride (UN) fuel kernels. UO2 fuel kernels have not been ruled out, and will be examined as later work in FY2012. Reactor physics calculations confirmed that the FCM fuel containing 500 mm diameter kernels of UN fuel has positive … more
Date: March 1, 2012
Creator: Sen, R. Sonat; Boer, Brian; Bess, John D.; Pope, Michael A. & Ougouag, Abderrafi M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NEAMS Update. Quarterly Report for October - December 2011.

Description: The Advanced Modeling and Simulation Office within the DOE Office of Nuclear Energy (NE) has been charged with revolutionizing the design tools used to build nuclear power plants during the next 10 years. To accomplish this, the DOE has brought together the national laboratories, U.S. universities, and the nuclear energy industry to establish the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program. The mission of NEAMS is to modernize computer modeling of nuclear energy systems and … more
Date: February 16, 2012
Creator: Bradley, K. (Nuclear Engineering Division)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

Description: The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting the temperature and strain within a nuclear fuel assembly to evaluate the performance and safety of existing and advanced nuclear fuel bundles within existing and advanced nuclear reactors. AMPFuel was extended to include an integrated nuclear fuel assembly capability for (one-way) coupled radiation transport and nuclear fuel assembly thermo-mechanics. This capability is the initial step toward inc… more
Date: February 1, 2012
Creator: Clarno, Kevin T; Hamilton, Steven P; Philip, Bobby; Berrill, Mark A; Sampath, Rahul S; Allu, Srikanth et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lead Slowing-Down Spectrometry Time Spectral Analysis for Spent Fuel Assay: FY11 Status Report

Description: Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R&D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration, of which PNNL is a part, to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nond… more
Date: September 30, 2011
Creator: Kulisek, Jonathan A.; Anderson, Kevin K.; Bowyer, Sonya M.; Casella, Andrew M.; Gesh, Christopher J. & Warren, Glen A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Performance of Transuranic-Loaded Fully Ceramic Micro-Encapsulated Fuel in LWRs Final Report, Including Void Reactivity Evaluation

Description: The current focus of the Deep Burn Project is on once-through burning of transuranics (TRU) in light-water reactors (LWRs). The fuel form is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the tri-isotropic (TRISO) fuel particle design from high-temperature reactor technology. In the Deep Burn LWR (DB-LWR) concept, these fuel particles are pressed into compacts using SiC matrix material and loaded into fuel pins for use in conventional LWRs. The TRU loading comes from… more
Date: September 1, 2011
Creator: Pope, Michael A.; Sen, R. Sonat; Boer, Brian; Ougouag, Abderrafi M. & Youinou, Gilles
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lead Slowing-Down Spectrometry for Spent Fuel Assay: FY11 Status Report

Description: Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R&D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive a… more
Date: August 1, 2011
Creator: Warren, Glen A.; Casella, Andrew M.; Haight, R. C.; Anderson, Kevin K.; Danon, Yaron; Hatchett, D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of the INSTANT-HPS PN Transport Code to the C5G7 Benchmark Problem

Description: INSTANT is the INL's next generation neutron transport solver to support high-fidelity multi-physics reactor simulation INSTANT is in continuous development to extend its capability Code is designed to take full advantage of middle to large cluster (10-1000 processors) Code is designed to focus on method adaptation while also mesh adaptation will be possible. It utilizes the most modern computing techniques to generate a neutronics tool of full-core transport calculations for reactor analysis a… more
Date: June 1, 2011
Creator: Wang, Y.; Zhang, H.; Szilard, R. H. & Martineau, R. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Performance of Trasuranic-Loaded Fully Ceramic Micro-Encapsulated Fuel in LWRs Interim Report, Including Void Reactivity Evaluation

Description: The current focus of the Deep Burn Project is on once-through burning of transuranice (TRU) in light water reactors (LWRs). The fuel form is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the tri-isotropic (TRISO) fuel particle design from high-temperature reactor technology. In the Deep Burn LWR (DB-LWR) concept, these fuel particles would be pressed into compacts using SiC matrix material and loaded into fuel pins for use in conventional LWRs. The TRU loading comes… more
Date: March 1, 2011
Creator: Pope, Michael A.; Boer, Brian; Youinou, Gilles & Ougouag, Abderrafi M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Study of the Efficacy of Using Nuclear Resonance Fluorescence with Quasi-Monoenergetic Gamma-Ray Sources for Nuclear Safeguards Assay

Description: We have studied the efficacy of using nuclear resonance fluorescence (NRF)-based techniques to assay spent nuclear fuel for Pu content using quasi-monoenergetic sources. We have developed two techniques to precisely determine the Pu content in a fuel rod/pin. One of our approaches is virtually free of systematic uncertainties. Using analytical models, we have determined the amount of time required to measure the Pu content in spent nuclear fuel rods and spent fuel assemblies to within 1% precis… more
Date: February 17, 2011
Creator: Johnson, M. S.; McNabb, D. P.; Hall, J. M. & Gonzalez, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sustained Recycle in Light Water and Sodium-Cooled Reactors

Description: From a physics standpoint, it is feasible to sustain recycle of used fuel in either thermal or fast reactors. This paper examines multi-recycle potential performance by considering three recycling approaches and calculating several fuel cycle parameters, including heat, gamma, and neutron emission of fresh fuel; radiotoxicity of waste; and uranium utilization. The first recycle approach is homogeneous mixed oxide (MOX) fuel assemblies in a light water reactor (LWR). The transuranic portion of t… more
Date: November 1, 2010
Creator: Piet, Steven J.; Bays, Samuel E.; Pope, Michael A. & Youinou, Gilles J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Sandia National Laboratories Medical Isotope Reactor concept.

Description: This report describes the Sandia National Laboratories Medical Isotope Reactor and hot cell facility concepts. The reactor proposed is designed to be capable of producing 100% of the U.S. demand for the medical isotope {sup 99}Mo. The concept is novel in that the fuel for the reactor and the targets for the {sup 99}Mo production are the same. There is no driver core required. The fuel pins that are in the reactor core are processed on a 7 to 21 day irradiation cycle. The fuel is low enriched ur… more
Date: April 1, 2010
Creator: Coats, Richard Lee; Dahl, James J. & Parma, Edward J., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CFD Analysis of Core Bypass Phenomena

Description: The U.S. Department of Energy is exploring the potential for the VHTR which will be either of a prismatic or a pebble-bed type. One important design consideration for the reactor core of a prismatic VHTR is coolant bypass flow which occurs in the interstitial regions between fuel blocks. Such gaps are an inherent presence in the reactor core because of tolerances in manufacturing the blocks and the inexact nature of their installation. Furthermore, the geometry of the graphite blocks changes ov… more
Date: March 1, 2010
Creator: Johnson, Richard W.; Sato, Hiroyuki & Schultz, Richard R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mitigation of Severe Accident Consequences Using Inherent Safety Principles

Description: Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability of occurrence are typically handled without consequence through reliable engineering systems and good design practices. For accidents of lower probability, the initiating events are characterized by larger and more numerous challenges to the reactor system, such as failure of one or more major engineered systems and can also include a failure to scram the reactor in response. As the initiating co… more
Date: December 1, 2009
Creator: Wigeland, R. A. & Cahalan, J. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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CFD Analysis of Core Bypass Phenomena

Description: The U.S. Department of Energy is exploring the potential for the VHTR which will be either of a prismatic or a pebble-bed type. One important design consideration for the reactor core of a prismatic VHTR is coolant bypass flow which occurs in the interstitial regions between fuel blocks. Such gaps are an inherent presence in the reactor core because of tolerances in manufacturing the blocks and the inexact nature of their installation. Furthermore, the geometry of the graphite blocks changes ov… more
Date: November 1, 2009
Creator: Johnson, Richard W.; Sato, Hiroyuki & Schultz, Richard R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Reactor Subassembly Design Modifications for Increasing Electricity Generation Efficiency

Description: Suggested for Track 7: Advances in Reactor Core Design and In-Core Management _____________________________________________________________________________________ Fast Reactor Subassembly Design Modifications for Increasing Electricity Generation Efficiency R. Wigeland and K. Hamman Idaho National Laboratory Given the ability of fast reactors to effectively transmute the transuranic elements as are present in spent nuclear fuel, fast reactors are being considered as one element of future nucle… more
Date: September 1, 2009
Creator: Wigeland, R. & Hamman, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Minor Actinides Loading Optimization for Proliferation Resistant Fuel Design - BWR

Description: One approach to address the United States Nuclear Power (NP) 2010 program for the advanced light water reactor (LWR) (Gen-III+) intermediate-term spent fuel disposal need is to reduce spent fuel storage volume while enhancing proliferation resistance. One proposed solution includes increasing burnup of the discharged spent fuel and mixing minor actinide (MA) transuranic nuclides (237Np and 241Am) in the high burnup fuel. Thus, we can reduce the spent fuel volume while increasing the proliferati… more
Date: September 1, 2009
Creator: Chang, G. S. & Zhang, Hongbin
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Transmutation Dynamics: Impacts of Multi-Recycling on Fuel Cycle Performances

Description: From a physics standpoint, it is feasible to sustain continuous multi-recycle in either thermal or fast reactors. In Fiscal Year 2009, transmutaton work at INL provided important new insight, caveats, and tools on multi-recycle. Multi-recycle of MOX, even with all the transuranics, is possible provided continuous enrichment of the uranium phase to ~6.5% and also limitting the transuranic enrichment to slightly less than 8%. Multi-recycle of heterogeneous-IMF assemblies is possible with continuo… more
Date: September 1, 2009
Creator: Bays, S.; Piet, S.; Pope, M.; Youinou, G.; Dumontier, A. & Hawn, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement and Characterization of Nuclear Material at Idaho National Laboratory

Description: A measurement plan and preliminary Monte Carlo simulations are presented for the investigation of well-defined mixed-oxide fuel pins. Measurement analysis including pulse-height distributions and time-dependent cross-correlation functions will be performed separately for neutrons and gamma rays. The utilization of Monte Carlo particle transport codes, specifically MCNP-PoliMi, is discussed in conjunction with the anticipated measurements. Four EJ-309 liquid scintillation detectors with an accur… more
Date: July 1, 2009
Creator: Dolan, J. L.; Flaska, M.; Pozzi, S. A. & Chichester, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nondestructive Spent Fuel Assay Using Nuclear Resonance Fluorescence

Description: Quantifying the isotopic composition of spent fuel is an important challenge and essential for many nuclear safeguards applications, such as independent verification of the Pu content declared by a regulated facility, shipper/receiver measurements, and quantifying isotopic input masses at a reprocessing facility. As part of the Next Generation Safeguards Initiative, NA-241 has recently funded a multilab/university collaboration to investigate a variety of nondestructive methods for determining … more
Date: July 1, 2009
Creator: Quiter, Brian; Ludewigt, Bernhard; Mozin, Vladimir & Tobin, Steven
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Assessment of Failure Mechanisms for GFR Vented Fuel Pins Using Hexoloy Cladding

Description: A near-term vented fuel pin concept as a back-up option for the gas-cooled fast reactor (GFR) system was evaluated. This work explored the feasibility of using mixed carbide fuel (U0.85P0.15)C with off-the-shelf monolithic SiC clad in order to meet requirements for GFR fuel with an average burnup of 10%. The stress loading on the SiC cladding due to fuel swelling and thermal stress due to temperature gradient were estimated based on the data from the development of carbide fuels in the 1970’s-1… more
Date: September 1, 2008
Creator: Gan, Jian
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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