Performance Evaluation of Core II and III Advanced Test Reactor Fuel Elements

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (862 download)

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Book Synopsis Performance Evaluation of Core II and III Advanced Test Reactor Fuel Elements by : M. J. Graber

Download or read book Performance Evaluation of Core II and III Advanced Test Reactor Fuel Elements written by M. J. Graber and published by . This book was released on 1971 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Performance Evaluation of Core II and III Advanced Test Reactor Fuel Elements

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ISBN 13 :
Total Pages : 63 pages
Book Rating : 4.:/5 (862 download)

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Book Synopsis Performance Evaluation of Core II and III Advanced Test Reactor Fuel Elements by : M. J. Graber

Download or read book Performance Evaluation of Core II and III Advanced Test Reactor Fuel Elements written by M. J. Graber and published by . This book was released on 1971 with total page 63 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 744 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Criticality Safety Evaluation for the Advanced Test Reactor Enhanced Low Enriched Uranium Fuel Elements

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ISBN 13 :
Total Pages : 119 pages
Book Rating : 4.:/5 (958 download)

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Book Synopsis Criticality Safety Evaluation for the Advanced Test Reactor Enhanced Low Enriched Uranium Fuel Elements by :

Download or read book Criticality Safety Evaluation for the Advanced Test Reactor Enhanced Low Enriched Uranium Fuel Elements written by and published by . This book was released on 2016 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Global Threat Reduction Initiative (GTRI) convert program is developing a high uranium density fuel based on a low enriched uranium (LEU) uranium-molybdenum alloy. Testing of prototypic GTRI fuel elements is necessary to demonstrate integrated fuel performance behavior and scale-up of fabrication techniques. GTRI Enhanced LEU Fuel (ELF) elements based on the ATR-Standard Size elements (all plates fueled) are to be fabricated for testing in the Advanced Test Reactor (ATR). While a specific ELF element design will eventually be provided for detailed analyses and in-core testing, this criticality safety evaluation (CSE) is intended to evaluate a hypothetical ELF element design for criticality safety purposes. Existing criticality analyses have analyzed Standard (HEU) ATR elements from which controls have been derived. This CSE documents analysis that determines the reactivity of the hypothetical ELF fuel elements relative to HEU ATR elements and whether the existing HEU ATR element controls bound the ELF element. The initial calculations presented in this CSE analyzed the original ELF design, now referred to as Mod 0.1. In addition as part of a fuel meat thickness optimization effort for reactor performance other designs have been evaluated. As of early 2014 the most current conceptual designs are Mk1A and Mk1B that were previously referred to as conceptual designs Mod 0.10 and Mod 0.11, respectively. Revision 1 evaluates the reactivity of the ATR HEU Mark IV elements for a comparison with the Mark VII elements.

Nuclear Power Reactor Instrumentation Systems Handbook

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ISBN 13 : 9780870790058
Total Pages : 1052 pages
Book Rating : 4.7/5 (9 download)

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Book Synopsis Nuclear Power Reactor Instrumentation Systems Handbook by : Joseph M. Harrer

Download or read book Nuclear Power Reactor Instrumentation Systems Handbook written by Joseph M. Harrer and published by . This book was released on 1973 with total page 1052 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Advanced Test Reactor (ATR)

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ISBN 13 :
Total Pages : 232 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis The Advanced Test Reactor (ATR) by :

Download or read book The Advanced Test Reactor (ATR) written by and published by . This book was released on 1960 with total page 232 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Fuel Element Design and Analysis for Advanced Test

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (967 download)

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Book Synopsis Fuel Element Design and Analysis for Advanced Test by :

Download or read book Fuel Element Design and Analysis for Advanced Test written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR), located at the Id.

Government-wide Index to Federal Research & Development Reports

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ISBN 13 :
Total Pages : 1028 pages
Book Rating : 4.E/5 ( download)

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Book Synopsis Government-wide Index to Federal Research & Development Reports by :

Download or read book Government-wide Index to Federal Research & Development Reports written by and published by . This book was released on 1966 with total page 1028 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Scientific and Technical Aerospace Reports

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ISBN 13 :
Total Pages : 280 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis Scientific and Technical Aerospace Reports by :

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1971 with total page 280 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Core Reload Analysis Techniques in the Advanced Test Reactor

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (139 download)

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Book Synopsis Core Reload Analysis Techniques in the Advanced Test Reactor by : Samuel E. Bays

Download or read book Core Reload Analysis Techniques in the Advanced Test Reactor written by Samuel E. Bays and published by . This book was released on 2019 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Since becoming a national user facility in 2007, the type of irradiation campaigns the Advanced Test Reactor (ATR) supports has become much more diverse and complex. In prior years, test complexity was limited by the computational ability to analyze the tests,Äô influence on the fuel. Large volume tests are irradiated in flux traps which are designed to receive excess neutrons from the surrounding fuel elements. Typically, fuel elements drive the test conditions, not vice versa. The computational tool, PDQ, was used for core physics analysis for decades. The PDQ code was adequate so long as the diffusion approximation between test and fuel element remained valid. This paradigm changed with the introduction of the Ki-Jang Research Reactor,ÄîFuel Assembly Irradiation (KJRR-FAI) in 2015. The KJRR-FAI was a prototypic fuel element for the KJRR research reactor project in the Republic of Korea. The KJRR-FAI irradiation presented multiple modeling and simulation challenges for which PDQ was ill suited. To demonstrate that the KJRR-FAI could be irradiated and meet safety requirements, the modern neutron transport codes, HELIOS and MCNP, were extensively verified and validated to replace PDQ. The hybrid 3D/2D methodology devised with these codes made analysis of the ATR with KJRR-FAI possible. The KJRR-FAI was irradiated in 2015-2016.

Publications, Reports, and Papers for 1968 from Oak Ridge National Laboratory

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ISBN 13 :
Total Pages : 340 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Publications, Reports, and Papers for 1968 from Oak Ridge National Laboratory by : F. M. O'Hara

Download or read book Publications, Reports, and Papers for 1968 from Oak Ridge National Laboratory written by F. M. O'Hara and published by . This book was released on 1969 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt:

TID.

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ISBN 13 :
Total Pages : 720 pages
Book Rating : 4.E/5 ( download)

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Book Synopsis TID. by :

Download or read book TID. written by and published by . This book was released on 19?? with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Advanced Test Reactor LEU Fuel Conversion Feasibility Study (2006 Annual Report).

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Advanced Test Reactor LEU Fuel Conversion Feasibility Study (2006 Annual Report). by :

Download or read book Advanced Test Reactor LEU Fuel Conversion Feasibility Study (2006 Annual Report). written by and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) is a high power density and high neutron flux research reactor operating in the United States. Powered with highly enriched uranium (HEU), the ATR has a maximum thermal power rating of 250 MWth with a maximum unperturbed thermal neutron flux rating of 1.0 x 1015 n/cm2-s. Because of these operating parameters, and the large test volumes located in high flux areas, the ATR is an ideal candidate for assessing the feasibility of converting an HEU driven reactor to a low-enriched core. The present work investigates the necessary modifications and evaluates the subsequent operating effects of this conversion. A detailed plate-by-plate MCNP ATR 1/8th core model was developed and validated for a fuel cycle burnup comparison analysis. Using the current HEU U 235 enrichment of 93.0 % as a baseline, an analysis can be performed to determine the low-enriched uranium (LEU) density and U-235 enrichment required in the fuel meat to yield an equivalent K-eff between the HEU core and the LEU core versus effective full power days (EFPD). The MCNP ATR 1/8th core model will be used to optimize the U-235 loading in the LEU core, such that the differences in K-eff and heat profile between the HEU and LEU core can be minimized for operation at 125 EFPD with a total core power of 115 MW. The depletion methodology, Monte-Carlo coupled with ORIGEN2 (MCWO), was used to calculate K-eff versus EFPDs. The MCWO-calculated results for the LEU case demonstrated adequate excess reactivity such that the K-eff versus EFPDs plot is similar in shape to the reference ATR HEU case. The LEU core conversion feasibility study can also be used to optimize the U-235 content of each fuel plate, so that the relative radial fission heat flux profile is bounded by the reference ATR HEU case. The detailed radial, axial, and azimuthal heat flux profiles of the HEU and optimized LEU cases have been investigated. However, to demonstrate that the LEU core fuel cycle performance can meet the UFSAR safety requirements, additional studies will be necessary to evaluate and compare safety parameters such as void reactivity and Doppler coefficients, control components worth (outer shim control cylinders (OSCCs), safety rods and regulating rod), and shutdown margins between the HEU and LEU cores.

Energy Research Abstracts

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ISBN 13 :
Total Pages : 1332 pages
Book Rating : 4.U/5 (183 download)

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Download or read book Energy Research Abstracts written by and published by . This book was released on 1989 with total page 1332 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Comprehensive Nuclear Materials

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Publisher : Elsevier
ISBN 13 : 0080560334
Total Pages : 3552 pages
Book Rating : 4.0/5 (85 download)

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Book Synopsis Comprehensive Nuclear Materials by : Todd R Allen

Download or read book Comprehensive Nuclear Materials written by Todd R Allen and published by Elsevier. This book was released on 2011-05-12 with total page 3552 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants

Benchmark Experiments, Development and Needs in Support of Advanced Reactor Design

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Publisher : Frontiers Media SA
ISBN 13 : 283253094X
Total Pages : 146 pages
Book Rating : 4.8/5 (325 download)

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Book Synopsis Benchmark Experiments, Development and Needs in Support of Advanced Reactor Design by : Mark David DeHart

Download or read book Benchmark Experiments, Development and Needs in Support of Advanced Reactor Design written by Mark David DeHart and published by Frontiers Media SA. This book was released on 2023-08-01 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Report on Civilian Reactor Fuel Elements by the Civilian Reactor Fuel Element Review Group

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ISBN 13 :
Total Pages : 204 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Report on Civilian Reactor Fuel Elements by the Civilian Reactor Fuel Element Review Group by : M. J. Whitman

Download or read book Report on Civilian Reactor Fuel Elements by the Civilian Reactor Fuel Element Review Group written by M. J. Whitman and published by . This book was released on 1959 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt: