Download or read book ORTAP a Nuclear Steam Supply System Simulation for the Dynamic Analysis of High Temperature Gas Cooled Reactor Transients written by J. C. Cleveland and published by . This book was released on 1977 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ORTAP written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: ORTAP was developed to predict the dynamic behavior of the high temperature gas cooled reactor (HTGR) Nuclear Steam Supply System for normal operational transients and postulated accident conditions. It was developed for the Nuclear Regulatory Commission (NRC) as an independent means of obtaining conservative predictions of the transient response of HTGRs over a wide range of conditions. The approach has been to build sufficient detail into the component models so that the coupling between the primary and secondary systems can be accurately represented and so that transients which cover a wide range of conditions can be simulated. System components which are modeled in ORTAP include the reactor core, a typical reheater and steam generator module, a typical helium circulator and circulator turbine and the turbine generator plant. The major plant control systems are also modeled. Normal operational transients which can be analyzed with ORTAP include reactor start-up and shutdown, normal and rapid load changes. Upset transients which can be analyzed with ORTAP include reactor trip, turbine trip and sudden reduction in feedwater flow. ORTAP has also been used to predict plant response to emergency or faulted conditions such as primary system depressurization, loss of primary coolant flow and uncontrolled removal of control poison from the reactor core.
Download or read book ORTAP written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: ORTAP was developed to predict the dynamic behavior of the high temperature gas-cooled reactor (HTGR) Nuclear Steam Supply System for normal operational transients and postulated accidents. Normal operational transients which can be analyzed with ORTAP include both reactor startup and shutdown, and normal and rapid load charges. Upset transients that can be analyzed with ORTAP include reactor trip, turbine trip and sudden reduction in feedwater flow. ORTAP has been used to predict plant response to postulated emergency or faulted conditions such as primary system depressurization, loss of primary coolant flow and uncontrolled removal of control poison from the reactor core. A brief description of the HTGR system and the models used for each of the major components is presented, together with certain modeling and solution techniques used in ORTAP that are of general interest.
Download or read book High temperature Gas cooled Reactor Safety Studies for the Division of Reactor Safety Research written by and published by . This book was released on 1980 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1978-02 with total page 764 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book High temperature Gas cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report written by and published by . This book was released on 1979 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book CORTAP written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: CORTAP (Core Transient Analysis Program) was developed to predict the dynamic behavior of the High Temperature Gas Cooled Reactor (HTGR) core under normal operational transients and postulated accident conditions. CORTAP is used both as a stand-alone component simulation and as part of the HTGR nuclear steam supply (NSS) system simulation code ORTAP. The core thermal neutronic response is determined by solving the heat transfer equations for the fuel, moderator and coolant in an average powered region of the reactor core. The space independent neutron kinetics equations are coupled to the heat transfer equations through a rapidly converging iterative technique. The code has the capability to determine conservative fuel, moderator, and coolant temperatures in the ''hot'' fuel region. For transients involving a reactor trip, the core heat generation rate is determined from an expression for decay heat following a scram. Nonlinear effects introduced by temperature dependent fuel, moderator, and coolant properties are included in the model. CORTAP predictions will be compared with dynamic test results obtained from the Fort St. Vrain reactor owned by Public Service of Colorado, and, based on these comparisons, appropriate improvements will be made in CORTAP.
Download or read book Proceedings of the Topical Meeting on Thermal Reactor Safety written by and published by . This book was released on 1978 with total page 796 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the Third Japan U S Seminar on HTGR Safety Technology written by and published by . This book was released on 1983 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the Second U S Japan Seminar on HTGR Safety Technology written by and published by . This book was released on 1979 with total page 322 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration. Technical Information Center and published by . This book was released on 1977 with total page 1682 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindex written by and published by . This book was released on 1983 with total page 722 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1977 with total page 646 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the Power Plant Dynamics Control and Testing Symposium written by and published by . This book was released on 1980 with total page 448 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Modular High temperature Gas cooled Reactor Short term Thermal Response to Flow and Reactivity Transients written by and published by . This book was released on 1993 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The research reported here has been conducted at the Oak Ridge National Laboratory for the Nuclear Regulatory Commission's Division of Regulatory Applications of the Office of Nuclear Regulatory Research. The short-term thermal response of the Modular High-Temperature Gas-Cooled Reactor (MHTGR) is analyzed for a range of flow and reactivity transients. These transients include loss of forced circulation without scram, spurious withdrawal of a control rod group, moisture ingress, control rod and control rod group ejections, and a rapid core cooling event. For each event analyzed, an event description, a discussion of the analysis approach and assumptions, and results are presented. When possible, results of these analyses are compared with those presented by the designers in the MHTGR Preliminary Safety Information Document and in the MHTGR Probabilistic Risk Assessment. The importance of inherent safety features is illustrated, and conclusions are presented regarding the safety performance of the MHTGR. Recommendations are made for a more in-depth examination of MHTGR response for some of the analyzed transients. The coupled heat transfer-neutron kinetics model is described in detail in Appendix A.
Download or read book Government reports annual index written by and published by . This book was released on 199? with total page 1602 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Index to Scientific Technical Proceedings written by and published by . This book was released on 1978 with total page 754 pages. Available in PDF, EPUB and Kindle. Book excerpt: Monthly, with annual cumulation. Published conference literature useful both as current awareness and retrospective tools that allow searching by authors of individual papers as well as by editors. Includes proceedings in all formats, i.e., books, reports, journal issues, etc. Complete bibliographical information for each conference proceedings appears in section titled Contents of proceedings, with accompanying category, permuterm subject, sponsor, author/editor, meeting location, and corporate indexes. Contains abbreviations used in organizational and geographical names.
