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Book Review of Cross Section Data Important to the Uranium  plutonium Fuel Cycle in Thermal Reactors

Download or read book Review of Cross Section Data Important to the Uranium plutonium Fuel Cycle in Thermal Reactors written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The present state of knowledge concerning the cross sections, etc., of the isotopes 235U, 238U, 239Pu, 24°Pu, and 241Pu is discussed. Most cross sections important to the design of U--Pu-fueled light-water reactors with current fuel--water ratios are known with reasonable accuracy. The three most serious discrepancies remaining are the following: the difference between integral measurements and differential calculations of 238U resonance capture, the discrepancy between irradiation experiments and other measurements of the ratio of capture to fission in 235U, and the uncertainty in the parameters of the 1 eV resonance of 24°Pu. 2 figures, 2 tables. (RWR).

Book Nuclear Cross Sections for Technology

Download or read book Nuclear Cross Sections for Technology written by Joseph L. Fowler and published by . This book was released on 1980 with total page 1056 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1982 with total page 1744 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Thorium Fuel Cycle

Download or read book Thorium Fuel Cycle written by International Atomic Energy Agency and published by . This book was released on 2005 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.

Book An Analysis of Plutonium Recycle Fuel Elements in San Onofre 1

Download or read book An Analysis of Plutonium Recycle Fuel Elements in San Onofre 1 written by Bruce William Foster Momsen and published by . This book was released on 1974 with total page 450 pages. Available in PDF, EPUB and Kindle. Book excerpt: A method has been developed to allow independent assessment of the use of plutonium recycle assemblies in operating reactors. This method utilizes Generalized Mixed Number Density (GMND) cross sections (based on Breen's Mixed Number Density cross sections) and the spectrum code LASER. LASER is modified to form LASER-M by adding ENDF/B-II thermal cross sections for the plutonium isotopes; adding edits to output G-aND cross sections, approximate microscopic removal and transport cross sections; and increasing LASERs compatibility with commonly used diffusion theory codes such as PDQ. Plutonium critical experiments for a number of lattices of 1.5 w/o and 6.6 w/o plutonium are analysed with LASER-M which is found to give better criticality agreement than LASER (without the ENDF/B-II plutonium cross sections) and other published data. Unit assembly power distributions are calculated for a uranium assembly and a constant and graded enrichment plutonium assembly both surrounded by uranium assemblies. The use of LASER-M with GMND cross sections is found to give excellent agreement with the published calculations of power distributions for the uranium assembly and good agreement for the plutonium assemblies. A quarter core depletion calculation of the San Onofre reactor containing four plutonium recycle demonstration assemblies is performed using the diffusion theory computer code PDQ-7. Use of PDQ-7 with GMND cross sections from LASER-M is shown to give excellent agreement with quasi experimental power distributions at cycle burnups of 0 MWD/MTM, 3342 MWD/MTM, and 6045 MWD/'MTM. Also, the calculated value of k-eff versus cycle burnup is determined to be in excellent agreement with the actual operating condition of k-eff = 1 .000.

Book Nuclear Cross Sections for Technology

Download or read book Nuclear Cross Sections for Technology written by Joseph L. Fowler and published by . This book was released on 1980 with total page 1064 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 764 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book NBS Special Publication

Download or read book NBS Special Publication written by and published by . This book was released on 1968 with total page 1064 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974-03 with total page 1100 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.

Book Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1971 with total page 1330 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book INIS Atomindex

Download or read book INIS Atomindex written by and published by . This book was released on 1982 with total page 1214 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Publications

Download or read book Publications written by United States. National Bureau of Standards and published by . This book was released on 1981 with total page 684 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Publications of the National Bureau of Standards     Catalog

Download or read book Publications of the National Bureau of Standards Catalog written by United States. National Bureau of Standards and published by . This book was released on 1980 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Publications of the National Institute of Standards and Technology     Catalog

Download or read book Publications of the National Institute of Standards and Technology Catalog written by National Institute of Standards and Technology (U.S.) and published by . This book was released on 1981 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book TID

Download or read book TID written by and published by . This book was released on 19?? with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt: