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Fabrication Development For The Advanced Neutron Source Reactor
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Book Synopsis Fabrication Development for the Advanced Neutron Source Reactor by :
Download or read book Fabrication Development for the Advanced Neutron Source Reactor written by and published by . This book was released on 1995 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report presents the fuel fabrication development for the Advanced Neutron Source (ANS) reactor. The fuel element is similar to that successfully fabricated and used in the High Flux Isotope Reactor (HFIR) for many years, but there are two significant differences that require some development. The fuel compound is U3Si2 rather than U3O, and the fuel is graded in the axial as well as the radial direction. Both of these changes can be accomplished with a straightforward extension of the HFIR technology. The ANS also requires some improvements in inspection technology and somewhat more stringent acceptance criteria. Early indications were that the fuel fabrication and inspection technology would produce a reactor core meeting the requirements of the ANS for the low volume fraction loadings needed for the highly enriched uranium design (up to 1.7 Mg U/m3). Near the end of the development work, higher volume fractions were fabricated that would be required for a lower- enrichment uranium core. Again, results look encouraging for loadings up to (almost equal to)3.5 Mg U/m3; however, much less evaluation was done for the higher loadings.
Book Synopsis Fuel Qualification Plan for the Advanced Neutron Source Reactor by :
Download or read book Fuel Qualification Plan for the Advanced Neutron Source Reactor written by and published by . This book was released on 1995 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes the development and qualification plan for the fuel for the Advanced Neutron Source. The reference fuel is U3Si2, dispersed in aluminum and clad in 6061 aluminum. This report was prepared in May 1994, at which time the reference design was for a two-element core containing highly enriched uranium (93% 235U) . The reactor was in the process of being redesigned to accommodate lowered uranium enrichment and became a three-element core containing a higher volume fraction of uranium enriched to 50% 235U. Consequently, this report was not issued at that time and would have been revised to reflect the possibly different requirements of the lower-enrichment, higher-volume fraction fuel. Because the reactor is now being canceled, this unrevised report is being issued for archival purposes. The report describes the fabrication and inspection development plan, the irradiation tests and performance modeling to qualify performance, the transient testing that is part of the safety program, and the interactions and interfaces of the fuel development with other tasks.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1989 with total page 848 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation Publisher : ISBN 13 : Total Pages :844 pages Book Rating :4.:/5 (319 download)
Book Synopsis Reactor development by : United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation
Download or read book Reactor development written by United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation and published by . This book was released on 1964 with total page 844 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Advanced Neutron Source written by and published by . This book was released on 1990 with total page 504 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source will be a new world-class facility for research using hot, thermal, cold, and ultra-cold neutrons. The heart of the facility will be a 330-MW (fission), heavy-water cooled and heavy-water moderated reactor. The reactor will be housed in a central reactor building, with supporting equipment located in an adjoining reactor support building. An array of cold neutron guides will fan out into a large guide hall, housing about 30 neutron research stations. Appropriate office, laboratory, and shop facilities will be included to provide a complete facility for users. The ANS is scheduled to begin operation at the Oak Ridge National Laboratory early in the next decade. This PDR document defines the plant-level requirements for the design, construction, and operation of ANS. It also defines and provides input to the individual System Design Description (SDD) documents. Together, this PDR document and the set of SDD documents will define and control the baseline configuration of ANS.
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 1991 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Atomic energy commission by : United States. Congress. House. Committee on Appropriations
Download or read book Atomic energy commission written by United States. Congress. House. Committee on Appropriations and published by . This book was released on 1963 with total page 432 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Hearings by : United States. Congress. House. Committee on Appropriations
Download or read book Hearings written by United States. Congress. House. Committee on Appropriations and published by . This book was released on 1964 with total page 1370 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Congress. Senate. Committee on Energy and Natural Resources Publisher : ISBN 13 : Total Pages :128 pages Book Rating :4.3/5 (121 download)
Book Synopsis Proposed Fiscal Year 1995 Budget Request for Department of Energy by : United States. Congress. Senate. Committee on Energy and Natural Resources
Download or read book Proposed Fiscal Year 1995 Budget Request for Department of Energy written by United States. Congress. Senate. Committee on Energy and Natural Resources and published by . This book was released on 1994 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Hearings and Reports on Atomic Energy by : United States. Congress. Joint Committee on Atomic Energy
Download or read book Hearings and Reports on Atomic Energy written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1946 with total page 834 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis AEC Authorizing Legislation, Fiscal Year 1967 by : United States. Congress. Joint Committee on Atomic Energy
Download or read book AEC Authorizing Legislation, Fiscal Year 1967 written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1966 with total page 608 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reviews costs and benefits of nuclear programs involving Defense Dept and nuclear industries.
Book Synopsis AEC Authorizing Legislation by : United States. Congress. Joint Committee on Atomic Energy
Download or read book AEC Authorizing Legislation written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1969 with total page 866 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Hearings, Reports and Prints of the Joint Committee on Atomic Energy by : United States. Congress. Joint Committee on Atomic Energy
Download or read book Hearings, Reports and Prints of the Joint Committee on Atomic Energy written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1966 with total page 1822 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Optimizing a Three-element Core Design for the Advanced Neutron Source Reactor by :
Download or read book Optimizing a Three-element Core Design for the Advanced Neutron Source Reactor written by and published by . This book was released on 1995 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Source of neutrons in the proposed Advanced Neutron Source facility is a multipurpose research reactor providing 5-10 times the flux, for neutron beams, of the best existing facilities. Baseline design for the reactor core, based on the ''no new inventions'' rule, was an assembly of two annular fuel elements similar to those used in the Oak Ridge and Grenoble high flux reactors, containing highly enriched U silicide particles. DOE commissioned a study of the use of medium- or low-enriched U; a three-element core design was studied as a means to provide extra volume to accommodate the additional U compound required when the fissionable 235U has to be diluted with 238U to reduce the enrichment. This paper describes the design and optimization of that three-element core.
Book Synopsis Advances in Neutron Capture Therapy by : R.F. Barth
Download or read book Advances in Neutron Capture Therapy written by R.F. Barth and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 776 pages. Available in PDF, EPUB and Kindle. Book excerpt: Binary systems for the treatment of cancer potentially are among the most attractive of the new therapeutic modalities that currently are under investigation. The basicconcept is to selectivelydestroy malignantcells whileconcomitantlysparing normal tissue. Neutron capture therapy (NCT) is the binary system that has been the subject of the Fifth International Symposium on Neutron Capture Therapy, which was held September13-17, 1992, in Columbus, Ohio, undertheauspicesoftheInternational Society for Neutron Capture Therapy. Its objective was to bring together researchers from throughout the world and to provide a forum at which they could present the latest advances in the development of Neutron capture therapy. Neutron capture therapy has largely, but not exclusively, focused on the use of boron-10 as the target nuclide. Boron neutron capture therapy (BNCT) is based on the nuclear reaction that occurs when the stable isotope, boron-10, absorbs low-energy non ionizing thermal neutrons to yield alphaparticles and recoiling lithium-7 nuclei. The size and energy of these high linear energy transfer (LET) particles result in their being confined largely to the cells in which the capture reaction occurs. For BNCT to be successful, a sufficient numberof I~atoms mustbe localized within neoplastic cells, and enough thermal neutrons must be delivered and absorbed by the I~ to produce a lethal 1~(n,QVLi reaction. Two major problems must be surmounted.
Book Synopsis Postirradiation Evaluations of Capsules HANS-1 and HANS-2 Irradiated in the HFIR Target Region in Support of Fuel Development for the Advanced Neutron Source by :
Download or read book Postirradiation Evaluations of Capsules HANS-1 and HANS-2 Irradiated in the HFIR Target Region in Support of Fuel Development for the Advanced Neutron Source written by and published by . This book was released on 1995 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes the design, fabrication, irradiation, and evaluation of two capsule tests containing U3Si2 fuel particles in contact with aluminum. The tests were in support of fuel qualification for the Advanced Neutron Source (ANS) reactor, a high-powered research reactor that was planned for the Oak Ridge National Laboratory. At the time of these tests, the fuel consisted of U3Si2, containing highly enriched uranium dispersed in aluminum at a volume fraction of (approximately)0.15. The extremely high thermal flux in the target region of the High Flux Isotope Reactor provided up to 90% burnup in one 23-d cycle. Temperatures up to 450°C were maintained by gamma heating. Passive SiC temperature monitors were employed. The very small specimen size allowed only microstructural examination of the fuel particles but also allowed many specimens to be tested at a range of temperatures. The determination of fission gas bubble morphology by microstructural examination has been beneficial in developing a fuel performance model that allows prediction of fuel performance under these extreme conditions. The results indicate that performance of the reference fuel would be satisfactory under the ANS conditions. In addition to U3Si2, particles of U3Si, UAl2, UAl(subscript x), and U3O were tested.
