Download or read book Monte Carlo Calculations with the MCNP Code for Investigationsof Neutron and Photon Transport at the ASDEX Upgrade Tokamak written by G. Fieg and published by . This book was released on 1991 with total page 43 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Monte Carlo Calculations with the MCNP Code for Investigations of Neutron and Photon Transport at the ASDEX Upgrade Tokamak written by Günter Fieg and published by . This book was released on 1991 with total page 43 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 1991 with total page 800 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MCNP written by Los Alamos Monte Carlo Group and published by . This book was released on 1981 with total page 512 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MCNP a General Monte Carlo Code for Neutron and Photon Transport written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The general-purpose Monte Carlo code MCNP can be used for neutron, photon, or coupled neutron-photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and some special fourth-degree surfaces (elliptical tori).

Download or read book Monte Carlo Particle Transport Methods written by I. Lux and published by CRC Press. This book was released on 2018-05-04 with total page 530 pages. Available in PDF, EPUB and Kindle. Book excerpt: With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.

Download or read book Development and Implementation of Photonuclear Cross section Data for Mutually Coupled Neutron photon Transport Calculations in the Monte Carlo N Particle MCNP Radiation Transport Code written by Morgan C. White and published by . This book was released on 2000 with total page 1078 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MCNP a General Monte Carlo Code for Neutron and Photon Transport written by and published by . This book was released on 1986 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Physics Briefs written by and published by . This book was released on 1991 with total page 826 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MCNP written by Los Alamos Scientific Laboratory. Group X-6 and published by . This book was released on 1979 with total page 411 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MCNP written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: MCNP is a very general Monte Carlo neutron photon transport code system with approximately 250 person years of Group X-6 code development invested. It is extremely portable, user-oriented, and a true production code as it is used about 60 Cray hours per month by about 150 Los Alamos users. It has as its data base the best cross-section evaluations available. MCNP contains state-of-the-art traditional and adaptive Monte Carlo techniques to be applied to the solution of an ever-increasing number of problems. Excellent user-oriented documentation is available for all facets of the MCNP code system. Many useful and important variants of MCNP exist for special applications. The Radiation Shielding Information Center (RSIC) in Oak Ridge, Tennessee is the contact point for worldwide MCNP code and documentation distribution. A much improved MCNP Version 3A will be available in the fall of 1985, along with new and improved documentation. Future directions in MCNP development will change the meaning of MCNP to Monte Carlo N Particle where N particle varieties will be transported.

Download or read book MCNP a General Monte Carlo Code for Neutron and Photon Transport Version 3A written by Judith F. Briesmeister and published by . This book was released on 1986 with total page 582 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MCNP written by W. L. Thompson and published by . This book was released on 1979 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MCNP A GENERAL MONTE CARLO CODE FOR NEUTRON AND PHOTON TRANSPORT written by W. L. Thompson and published by . This book was released on with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book KfK written by and published by . This book was released on 1991 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Systems Guide to MCNP Monte Carlo Neutron and Photon Transport Code written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The subject of this report is the implementation of the Los Alamos National Laboratory Monte Carlo Neutron and Photon Transport Code - Version 3 (MCNP) on the different types of computer systems, especially the IBM MVS system. The report supplements the documentation of the RSIC computer code package CCC-200/MCNP. Details of the procedure to follow in executing MCNP on the IBM computers, either in batch mode or interactive mode, are provided.

Download or read book High Altitude Neutral Particle Transport Using the Monte Carlo Simulation Code MCNP with Variable Density Atmosphere written by David L. Monti and published by . This book was released on 1991 with total page 138 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Monte Carlo transport code, MCNP was modified for purposes of two dimensional neutron-photon transport modelling in a variable density atmosphere. Calculations were performed using cylindrical (r, z) geometry and a point isotropic neutron-photon source at an elevation of 40 kilometers. Neutron and photon fluence results were computed using ring detectors for field points at constant range versus source elevation angle and for field points at constant altitude versus radius. Comparisons between the modified and unmodified versions of MCNP showed a decrease in run time by a factor of two was possible. Only a fraction of the spatial cells previously required were used. Results showed streaming of the neutron and photon radiation at very close ranges. Buildup from multiple scattering contributions proved to be the dominant effect at intermediate ranges. Attenuation from successive downscatter in energy was shown to be the dominant effect at ranges greater than about 60 kilometers. Results obtained with MCNP were compared to those obtained with the computer code SMAUG- II, which uses the mass-integral scaling approximation. The comparison showed SMAUG-II to be accurate at points close to the source, but serious errors were encountered at ranges exceeding 9 kilometers as the mass range increased.