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Book Cold Source Moderator Vessel Development for the High Flux Isotope Reactor

Download or read book Cold Source Moderator Vessel Development for the High Flux Isotope Reactor written by and published by . This book was released on 1998 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: A project is underway at Oak Ridge National Laboratory (ORNL) to design, test, and install a cold neutron source facility in the High Flux Isotope Reactor (HFIR). This new cold source employs supercritical hydrogen at cryogenic temperatures both as the medium for neutron moderation and as the working fluid for removal of internally-generated nuclear heating. The competing design goals of minimizing moderator vessel mass and providing adequate structural integrity for the vessel motivated the requirement of detailed multidimensional thermal-hydraulic analyses of the moderator vessel as a critical design subtask. This paper provides a summary review of the HFIR cold source moderator vessel design and a description of the thermal-hydraulic studies that were carried out to support the vessel development.

Book The High Flux Isotope Reactor  HFIR  Cold Source Project at ORNL

Download or read book The High Flux Isotope Reactor HFIR Cold Source Project at ORNL written by and published by . This book was released on 1998 with total page 1 pages. Available in PDF, EPUB and Kindle. Book excerpt: The scope of this project includes the development, design, procurement/fabrication, testing, and installation of all of the components necessary to produce a working cold source within an existing HFIR beam tube hole in the pressure vessel. All aspects of the cold source design will be based on demonstrated technology adapted to the HFIR design and operating conditions.

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  • Release : 1991
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Download or read book written by and published by . This book was released on 1991 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Reactor Dosimetry State Of The Art 2008   Proceedings Of The 13th International Symposium

Download or read book Reactor Dosimetry State Of The Art 2008 Proceedings Of The 13th International Symposium written by Wim Voorbraak and published by World Scientific. This book was released on 2009-08-19 with total page 761 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book gives the state of the art in the field of reactor dosimetry as applied in nuclear power plants and research reactors. Surveillance programs are presented for nuclear power plants in Europe, including Russia and Ukraine, USA, Argentina and Korea. New cross-section measurements from most of the European, American and Japanese research reactors are reported. The latest developments in computer code development for radiation transport and shielding calculations, and radiation measurement techniques are also highlighted.

Book High Flux Isotope Reactor

Download or read book High Flux Isotope Reactor written by and published by . This book was released on 1964 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book 107 1 Hearings  Energy and Water Development Appropriations for 2002  Part 4  2001

Download or read book 107 1 Hearings Energy and Water Development Appropriations for 2002 Part 4 2001 written by and published by . This book was released on 2001 with total page 1476 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book HIGH FLUX ISOTOPE REACTOR TARGET DEVELOPMENT

Download or read book HIGH FLUX ISOTOPE REACTOR TARGET DEVELOPMENT written by and published by . This book was released on 1968 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book A Review of Proposed Upgrades to the High Flux Isotope Reactor and Potential Impacts to Reactor Vessel Integrity

Download or read book A Review of Proposed Upgrades to the High Flux Isotope Reactor and Potential Impacts to Reactor Vessel Integrity written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) was scheduled in October 2000 to implement design upgrades that include the enlargement of the HB-2 and HB-4 beam tubes. Higher dose rates and higher radiation embrittlement rates were predicted for the two beam-tube nozzles and surrounding vessel areas. ORNL had performed calculations for the upgraded design to show that vessel integrity would be maintained at acceptable levels. Pacific Northwest National Laboratory (PNNL) was requested by the U.S. Department of Energy Headquarters (DOE/HQ) to perform an independent peer review of the ORNL evaluations. PNNL concluded that the calculated probabilities of failure for the HFIR vessel during hydrostatic tests and for operational conditions as estimated by ORNL are an acceptable basis for selecting pressures and test intervals for hydrostatic tests and for justifying continued operation of the vessel. While there were some uncertainties in the embrittlement predictions, the ongoing efforts at ORNL to measure fluence levels at critical locations of the vessel wall and to test materials from surveillance capsules should be effective in dealing with embrittlement uncertainties. It was recommended that ORNL continue to update their fracture mechanics calculations to reflect methods and data from ongoing research for commercial nuclear power plants. Such programs should provide improved data for vessel fracture mechanics calculations.

Book Energy and Water Development Appropriations for 2003

Download or read book Energy and Water Development Appropriations for 2003 written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 2002 with total page 2974 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy and Water Development Appropriations for 2003  Department of Energy     National Nuclear Security Administration     Power Marketing Administrations

Download or read book Energy and Water Development Appropriations for 2003 Department of Energy National Nuclear Security Administration Power Marketing Administrations written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 2002 with total page 2986 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy and Water Development Appropriations for 2002  Department of Energy fiscal year 2002 budget justifications

Download or read book Energy and Water Development Appropriations for 2002 Department of Energy fiscal year 2002 budget justifications written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 2001 with total page 3046 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy and Water Development Appropriations for 2002

Download or read book Energy and Water Development Appropriations for 2002 written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 2001 with total page 1520 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Transactions of the American Nuclear Society

Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 2002 with total page 1096 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Development of a Scale Model for High Flux Isotope Reactor Cycle 400

Download or read book Development of a Scale Model for High Flux Isotope Reactor Cycle 400 written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of a comprehensive SCALE computational model for the High Flux Isotope Reactor (HFIR) is documented and discussed in this report. The SCALE model has equivalent features and functionality as the reference MCNP model for Cycle 400 that has been used extensively for HFIR safety analyses and for HFIR experiment design and analyses. Numerical comparisons of the SCALE and MCNP models for the multiplication constant, power density distribution in the fuel, and neutron fluxes at several locations in HFIR indicate excellent agreement between the results predicted with the two models. The SCALE HFIR model is presented in sufficient detail to provide the users of the model with a tool that can be easily customized for various safety analysis or experiment design requirements.

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 882 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Method of Life Extension for the High Flux Isotope Reactor Vessel

Download or read book The Method of Life Extension for the High Flux Isotope Reactor Vessel written by and published by . This book was released on 1995 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The state of the vessel steel embrittlement as a result of neutron irradiation can be measured by its increase in the nil ductility temperature (NDT). This temperature is sometimes referred to as the brittle-ductile transition temperature (DBT) for fracture. The life extension of the High Flux Isotope Reactor (HFIR) vessel is calculated by using the method of fracture mechanics. A hydrostatic pressure test (hydrotest) is performed in order to determine a safe vessel static pressure. It is then followed by using fracture mechanics to project the reactor life from the safe hydrostatic pressure. The life extension calculation provides the following information on the remaining life of the reactor as a function of the nil ductility temperature increase: the probability of vessel fracture due to hydrotest vs vessel life at several hydrotest pressures; the hydrotest time interval vs the uncertainty of the nil ductility temperature increase rate; and the hydrotest pressure vs the uncertainty of the nil ductility temperature increase rate. It is understood that the use of a complete range of uncertainties of the nil ductility temperature increase is equivalent to the entire range of radiation damage that can be experienced by the vessel steel. From the numerical values for the probabilities of the vessel fracture as a result of hydrotest, it is estimated that the reactor vessel life can be extended up to 50 EFPY (100 MW) with the minimum vessel operating temperature equal to 85°F.