Published 1988
by Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in
Edition Notes
| Other titles | Thermal hydraulic research plan for Babcock and Wilcox plants |
| Statement | R.Y. Lee. |
| Contributions | U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor and Plant Systems |
| The Physical Object | |
|---|---|
| Pagination | xiii, 33 p. ; |
| Number of Pages | 33 |
| ID Numbers | |
| Open Library | OL17089956M |
The TMI-2 NPP is equipped with a Babcock and Wilcox (B & W) reactor. The key thermal-hydraulic design features which differentiate the B & W reactor from the Westinghouse reactor, widely spread solution in the world (i.e., adopted by other vendors) for the production of electricity, hereafter called standard PWR, are the following: (1)Cited by: 1. Alliance Research Center, and Babcock & Wilcox Company. Nuclear Power Division (page images at HathiTrust) Markviken I: general report on the physical tests carried out in the containment chamber of the reactor / (Washington, D.C.: U.S. Nuclear Regulatory Commission, ), by A. Sonnett, H. Tartu, U.S. Nuclear Regulatory Commission, France. The nuclear thermal-hydraulics discipline was developed following the needs for nuclear power plants (NPPs) and, to a more limited extent, research reactors (RR) design and safety. As in all other fields where analytical methods are involved, nuclear thermal Cited by: 1. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Year: Edition: 1st Edition. Publisher: Woodhead Publishing.
@article{osti_, title = {FLECHT SEASET program. Final report}, author = {Hochreiter, L E}, abstractNote = {This report presents the highlights and main findings of the USNRC, EPRI, and Westinghouse cooperative FLECHT SEASET program. The report indicates areas in which the results of the program can contribute to revising the current licensing requirements for Loss of Coolant (LOCA. Predictive Trip Detection for Nuclear Power Plants Article in IEEE Transactions on Nuclear Science 63(4) August with 3 Reads How we measure 'reads'. The study included review of documents, interviews, and depositions at Three Mile Island, Babcock and Wilcox, and the Nuclear Regulatory Commission (NRC) during June, July, and August Analysis of the information obtained was conducted almost exclusively by the writer. A methodology was developed to assess the operational performance of nuclear power plants through an integration of thermal-hydraulic and human factors analysis techniques together with inputs.
During 16 years at Babcock & Wilcox, he headed vibration analysis and design teams developing and testing innovative power plant equipment. Since , as a professor at the University of Dayton, he has led the way in integrating engineering education with engineering practice to improve the product realization process. 28 Nuclear Engineering Handbook × 8 × 10 Source × CPS % power Power 2×10–3 amps Intermediate Thermal neutron flux in neutrons/cm2/sec at detector location × 0% (%) power Detector sensitivity 3 × 10–13 AMP/N/cm2/sec 2×10–11 amperes Detector. You can write a book review and share your experiences. Other readers will always be interested in your opinion of the books you've read. Whether you've loved the book or not, if you give your honest and detailed thoughts then people will find new books that are right for them., Free ebooks since Registrant’s Telephone Number, Including Area Code: () Indicate by check mark whether the registrant (1) has filed all reports required to be filed by Section 13 or.
