Download or read book The RBU Reactor burnup Code written by J. R. Triplett and published by . This book was released on 1961 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book RHOBURN written by Gordon V. Pefley (Jr.) and published by . This book was released on 1963 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Plutonium Utilization Program Technical Activities Quarterly Report written by and published by . This book was released on 1969 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Physics Quarterly Report written by and published by . This book was released on 1969 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Performance of Power reactor Cores written by American Nuclear Society. Topical Meeting and published by . This book was released on 1964 with total page 480 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 1973 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Argonne Code Center written by and published by . This book was released on 1977 with total page 492 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book List written by and published by . This book was released on 1948 with total page 564 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Atomic Energy Research Reports for Sale by the U S Department of Commerce Office of Technical Services written by Business and Defense Services Administration and published by . This book was released on 1963 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ANS Topical Meeting written by American Nuclear Society. Topical Meeting and published by . This book was released on 1964 with total page 476 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Unclassified Research and Development Programs Executed for the Division of Reactor Development and Technology and the Division of Research June 1965 written by and published by . This book was released on 1965 with total page 102 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 1967 with total page 1004 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book TID written by and published by . This book was released on 1964 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book RBU written by E.J. Leshan and published by . This book was released on 1958 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book U S Government Research Reports written by and published by . This book was released on 1962 with total page 1166 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book BURNCAL written by and published by . This book was released on 2002 with total page 99 pages. Available in PDF, EPUB and Kindle. Book excerpt: BURNCAL is a Fortran computer code designed to aid in analysis, prediction, and optimization of fuel burnup performance in a nuclear reactor. The code uses output parameters generated by the Monte Carlo neutronics code MCNP to determine the isotopic inventory as a function of time and power density. The code allows for multiple fueled regions to be analyzed. The companion code, RELOAD, can be used to shuffle fueled regions or reload regions with fresh fuel. BURNCAL can be used to study the reactivity effects and isotopic inventory as a function of time for a nuclear reactor system. Neutron transmutation, fission, and radioactive decay are included in the modeling of the production and removal terms for each isotope of interest. For a fueled region, neutron transmutation, fuel depletion, fission-product poisoning, actinide generation, and burnable poison loading and depletion effects are included in the calculation. Fueled and un-fueled regions, such as cladding and moderator, can be analyzed simultaneously. The nuclides analyzed are limited only by the neutron cross section availability in the MCNP cross-section library. BURNCAL is unique in comparison to other burnup codes in that it does not use the calculated neutron flux as input to other computer codes to generate the nuclide mixture for the next time step. Instead, BURNCAL directly uses the neutron absorption tally/reaction information generated by MCNP for each nuclide of interest to determine the nuclide inventory for that region. This allows for the full capabilities of MCNP to be incorporated into the calculation and a more accurate and robust analysis to be performed.

Download or read book RBU written by E.J. Leshan and published by . This book was released on 1959 with total page 254 pages. Available in PDF, EPUB and Kindle. Book excerpt: RBU is a digital computer program for the detailed calculation of the neutron, reactivity, and isotopic history of a reactor in which relatively exact models of the geometry and physical processes are included to permit reliable pre dictions of fuel costs and reactor performance. The program uses the Monte Carlo method to obtain the fine structure of the neutron flux in three space dimensions and energy. Using this fine structure, cross sections are averaged over space and energy to obtain the neutronic properties for equivalent homogeneous one- dimensional regions of space and ranges of energy. These are used in diffusion calculations to obtain the macroscopic flux distribution throughout the reactor. The consumption and production of isotopes is computed for a time step by the solution of sets of partial differential equations involving both the macroscopic and microscopic fluxes. With the new concentrations, diffusion calculations are performed again to obtain macroscopic fluxes for the next time step. At variable intervals, Monte Carlo calculations are again performed to determine the changes in microscopic flux distributions. The cycle is repeated until conditions on the reactivity or other properties dictate the end of the calculation. Programmed control rod manipulation may be included in the calculation. The Monte Carlo, diffusion, or burnup portions of the program may be used separately. The unresolved resonance range is treated by random selection of resonance parameters from appropriate distributions using the Doppler broadened single level Breit- Wigner formula. Resolved resonances are treated similarly with the exception that specific values of the resonance parameters are used. The effects of molecular binding and thermal motion of the nuclei on near-thermal scattering are treated by a simple model capable of incorporating the pertinent physical theory and data. (auth).