Download or read book Safety Analysis Report for the Oregon State University TRIGA Research Reactor written by John Clayton Ringle and published by . This book was released on 1968 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis and Proposed Revision of the Radiation Protection and Waste Management Programs as Described in the Oregon State University TRIGA Research Reactor Safety Analysis Report written by Kittisak Chinudomsub and published by . This book was released on 1999 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Safety Analysis Report (SAR) of the Oregon State University TRIGA Research Reactor (OSTR) was prepared and used as a safety baseline for the reactor's operation since 1968. Although, in general, revision of the Safety Analysis Report of a research reactor is not a regulation requirement, it should be revised from time to time to include changes to the facility or procedures or update to current regulatory standards. The ANS 15.21 workgroup developed a draft standard format and content for safety analysis reports for research reactors. An area of this guidance, which was selected for this work's revision of OSTR-SAR, is the radiation protection program and waste management chapter. The Health Physics program of the facility was observed. The radiological data were obtained from the annual reports for more than 10 years of operation. The related data, such as meteorological data, were obtained and prepared for the analysis processes. The current federal regulation limits and recommendations were used as the references for dose assessments. The results show the OSTR has a sufficient radiation protection program not only for the facility's workers, but also for the general public, and the program is in full compliance with the federal regulations. The dose estimation shows that the workers and general public can not receive and have not received doses in excess of regulatory limits from the normal operation of the OSTR.
Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1982 with total page 704 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal Hydraulic Analysis of the Oregon State TRIGA Reactor Using RELAP5 3D written by Wade R. Marcum and published by . This book was released on 2008 with total page 302 pages. Available in PDF, EPUB and Kindle. Book excerpt: Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Pprogram. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both the Highly Enriched Uranium (HEU) and Low Enriched Uranium (LEU) cores; for steady state and pulsed operation, calculate peak values of fuel temperature, cladding temperature, surface heat flux as well as critical heat flux ratio (CHFR) and temperature profiles in hot channel for both the HEU and LEU cores; finally, perform accident analyses for the accident scenarios identified in the Oregon State TRIGA® Reactor (OSTR) Safety Analysis Report (SAR). RELAP5-3D Version 2.4.2 was used for all computational modeling during the thermal hydraulics analysis. This is a lumped parameter code forcing engineering assumptions to be made during the analysis. A single hot channel model's results are compared to that produced from more refined two and eight channel models in order to identify variations in thermal hydraulic characteristics as a function of spatial refinement.
Download or read book Molybdenum 99 Production in the Oregon State TRIGA Reactor written by Andrew J. Hummel and published by . This book was released on 2014 with total page 139 pages. Available in PDF, EPUB and Kindle. Book excerpt: The most widely used and versatile medical radioisotope today is technetium-99m. Roughly 30 million people depend on this radioisotope for diagnostic procedures each year, and this demand is expected to grow. Although there are numerous ways of procuring this isotope, the most common and most practical, for reasons to be stated later, comes from fission product molybdenum. Molybdenum is produced in all nuclear reactors as a fission fragment with a yield of around 6.1%. Molybdenum-99 has a half-life of just over 2.5 days, and it will decay to Tc-99m 87% of the time. In 1978, the Reduced Enrichment for Research Test Reactors (RERTR) program was established at Argonne National Laboratory to investigate technology that would aid in converting High Enriched Uranium (HEU) facilities to use Low Enriched Uranium (LEU) fuel. Since the majority of all Mo-99 produced currently comes from the irradiation of HEU fuel targets, there has been a growing effort to design LEU targets that can yield comparable quantities of high Specific Activity (SA) Mo-99. Approximately three years ago the Oregon State TRIGA Reactor (OSTR) switched from HEU to LEU fuel elements in compliance with the RERTR program, and recently, a novel LEU target design has been developed for use in TRIGA reactors for production of Mo-99. Preliminary analysis has already been carried out with targets replacing several fuel elements, and it does not appear to negatively affect the reactor behavior. The current supply capability of Tc-99m cannot keep pace with the growing demand. There are few, if any, new production facilities of Mo-99 slated for the future, and many of those presently operating will shutdown in the coming decades. Factoring in the time needed to license and construct new reactors, and the always pressing political and public wariness towards nuclear power, action must be taken immediately to ensure the future supply of this invaluable radioisotope. This research will analyze the viability of operating a low-power research reactor using the newly developed target design as the only source of fissile material. The normal TRIGA fuel will be offloaded and replaced with the new target elements for some optimal amount of time to produce molybdenum. After Mo-99 production reaches saturation, the normal fuel will be loaded back into the reactor, where normal operation can continue. MCNP5 will be the primary simulation tool used to analyze the behavior of the reactor and verify compliance with all safety limitations set forth in the OSTR Safety and Analysis Report as stated by the U.S. Nuclear Regulatory Commission.
Download or read book Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report written by International Atomic Energy Agency and published by . This book was released on 1994 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents guidelines, approved by international consensus, for the preparation, review and assessment of the safety documentation (Safety Series No. 35-S1) and for the preparation of the Safety Analysis Report (SAR) (Safety Series No. 35-S2).
Download or read book Reactor Safety Study Rasmussen Report written by United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment and published by . This book was released on 1976 with total page 620 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book American National Standard Format and Content for Safety Analysis Reports for Research Reactors written by and published by . This book was released on 1997 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Standard Safety Analysis Report written by Faye H. Horn and published by . This book was released on 1974 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Safety Evaluation Report Related to the Renewal of the Operating License for the Washington State University TRIGA Reactor written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1982 with total page 69 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report IAEA Safety Standards Series No Ssg 20 Rev 1 written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2022-10-31 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide provides recommendations on the safety assessment for research reactors in the authorization process, and on performance of safety analysis and preparation of the safety analysis report. It also incorporates the relevant lessons learned from the accident at the Fukushima Daiichi nuclear power plant and elaborates guidance on interfaces between nuclear safety and nuclear security. The recommendations in this Safety Guide are intended for operating organizations of research reactors; it can also be used by designers performing a safety assessment for a research reactor. Furthermore, this guide provides useful guidance for regulatory bodies performing a review and assessment of submitted safety analysis reports as an important document within authorization process. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-20, which it supersedes.
Download or read book History Development and Future of TRIGA Research Reactors written by and published by . This book was released on 2016 with total page 131 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal Hydraulic and Safety Analysis of the University of Wisconsin Nuclear Reactor written by Brian J. Vitiello and published by . This book was released on 2008 with total page 392 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1969-11 with total page 788 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Supplement No 3 to the Safety Evaluation Report by the Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission in the Matter of Public Service Electric and Gas Company Et Al Salem Nuclear Generating Station Unit 2 Docket No 50 311 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1978 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Safety Research Programs written by S. K. Edler and published by . This book was released on 1983 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Issues in Water and Power Engineering 2013 Edition written by and published by ScholarlyEditions. This book was released on 2013-05-01 with total page 743 pages. Available in PDF, EPUB and Kindle. Book excerpt: Issues in Water and Power Engineering / 2013 Edition is a ScholarlyEditions™ book that delivers timely, authoritative, and comprehensive information about Fusion Engineering. The editors have built Issues in Water and Power Engineering: 2013 Edition on the vast information databases of ScholarlyNews.™ You can expect the information about Fusion Engineering in this book to be deeper than what you can access anywhere else, as well as consistently reliable, authoritative, informed, and relevant. The content of Issues in Water and Power Engineering: 2013 Edition has been produced by the world’s leading scientists, engineers, analysts, research institutions, and companies. All of the content is from peer-reviewed sources, and all of it is written, assembled, and edited by the editors at ScholarlyEditions™ and available exclusively from us. You now have a source you can cite with authority, confidence, and credibility. More information is available at http://www.ScholarlyEditions.com/.
