ZAP - a Computer Program to Predict Fission Product Concentrations as a Function of Neutron Flux, Irradiation and Cooling Times PDF Download
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Author: Bruce Earl Koopmann
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 254
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Book Description
"The development of a computer code was undertaken to calculate the fission product nuclide concentration for spent fuel discharged from a nuclear reactor, as a function of irradiation time, cooling time, neutron flux, and element cross section. The necessary input data was prepared from the basic nuclear data for fission of uranium-235 and plutonium-239. Calculations are also made for total or selective element beta heating and total gamma flux according to user selected input groups. These calculations would be useful in fuel element shielding, cooling, shipping and processing studies"--Abstract, leaf ii.
Author: Bruce Earl Koopmann
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 254
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Book Description
"The development of a computer code was undertaken to calculate the fission product nuclide concentration for spent fuel discharged from a nuclear reactor, as a function of irradiation time, cooling time, neutron flux, and element cross section. The necessary input data was prepared from the basic nuclear data for fission of uranium-235 and plutonium-239. Calculations are also made for total or selective element beta heating and total gamma flux according to user selected input groups. These calculations would be useful in fuel element shielding, cooling, shipping and processing studies"--Abstract, leaf ii.
Author: G. M. Benson
Publisher:
ISBN:
Category : Burnup
Languages : en
Pages : 56
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
A computer program is described which calculates nuclide concentration histories, power or neutron flux histories, burnups, and fission-product birthrates for fueled experimental capsules subjected to neutron irradiations. Seventeen heavy nuclides in the chain from 232Th to 242Pu and a user- specified number of fission products are treated. A fourth-order Runge-Kutta calculational method solves the differential equations for nuclide concentrations as a function of time. For a particular problem, a user-specified number of fuel regions may be treated. A fuel region is described by volume, length, and specific irradiation history. A number of initial fuel compositions may be specified for each fuel region. The irradiation history for each fuel region can be divided into time intervals, and a constant power density or a time-dependent neutron flux is specified for each time interval. Also, an independent cross- section set may be selected for each time interval in each irradiation history. The fission-product birthrates for the first composition of each fuel region are summed to give the total fission-product birthrates for the problem.
Author:
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ISBN:
Category :
Languages : en
Pages :
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The behavior of some of the prominent fission products along their convection pathways is dominated by the interaction of other species with them. This gave rise to the development of a plateout code capable of analyzing coupled species effects. The single species plateout computer program PADLOC is described in Part I of this report. The present Part II is concerned with the extension of PADLOC to MULTI*PADLOK, a multiple species version of PADLOC. MULTI*PADLOC is designed to analyze the time and one-dimensional spatial dependence of the concentrations of interacting (fission product) species in the carrier gas and on the surrounding wall surfaces on an arbitrary network of flow channels. The problem solved is one of mass transport of several impurity spceis in a gas, including the effects of sources in the gas and on the surface, convection along the flow paths, decay interaction, sorption interaction on the wall surfaces, and chemical reaction interactions in the gas and on the surfaces. These phenomena are governed by a system of coupled, nonlinear partial differential equations. The solution is achieved by: (a) linearizing the equations about an approximate solution and employing a Newton-Raphson iteration technique, (b) employing a finite difference solution method with an implicit time integration, and (c) employing a substructuring technique to logically organize the systems of equations for an abitrary flow network.
Author: Thomas P. Gerrity (III.)
Publisher:
ISBN:
Category :
Languages : en
Pages : 72
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Book Description
In order to operate a reactor safely and efficiently, computer simulations must be used to predict certain nuclear characteristics of the reactor. To determine how materials change in a fission power environment, a time-dependent depletion isotopic code must be used. Over the past several decades, the MIT Reactor (MITR) has taken many steps to prepare for its conversion from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) in its fuel. Throughout this process, detailed neutronics simulations must be run to predict the characteristics of the reactor with its current HEU fuel, with potential forms of LEU fuel, and with combinations of the two. MCODE Version 3 is a linkage code that performs time-dependent burnup calculations by combining the Monte Carlo N-Particle transport code, MCNP, with the Oak Ridge Isotope Generation point depletion code, ORIGEN-S. MCNP provides reaction rates and neutron flux in user-specified irradiation material regions. COUPLE, a data-editing code included in the SCALE- 6.1 software package, uses these data from MCNP to update the cross section libraries, which ORIGEN then uses to perform nuclide depletion calculations in each irradiation zone. The MCNP model is then updated with the depleted material compositions, and the exchange is repeated. The MCNP/ORIGEN coupling utilizes an optional predictor-corrector capability. As a newer version of MCODE Version 2.2, MCODE-3 offers three major changes from its predecessor. The first is the incorporation of ORIGEN-S. MCODE-2 used a previous version of ORIGEN, which is no longer supported by ORNL. ORIGEN-S provides newer nuclear data as well as additional functionality and usability. Secondly, MCODE-3 uses COUPLE to create an entirely unique cross section library from the regionally averaged 238-group flux, which means every cross section value that MCODE-3 uses in its depletion is specific to the input model. MCODE-2 only updates a fraction of nuclides' cross sections, the rest default to a pre-compiled library. Finally, while MCODE-2.2 was written in ANSI C, MCODE-3's main function has been rewritten in the Python scripting language. MCODE's preproc, mcodeout, and mcnpxs programs have not been edited, and are thus still written in ANSI C. Benchmarking has indicated that while the evolution of most nuclides is similar to an MCODE-2 calculation, over many depletion steps some nuclides can diverge due to COUPLE's use of the 238-group flux.
Author: National Academies of Sciences Engineering and Medicine
Publisher:
ISBN: 9780309685382
Category :
Languages : en
Pages :
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Book Description
Fusion energy offers the prospect of addressing the nation's energy needs and contributing to the transition to a low-carbon emission electrical generation infrastructure. Technology and research results from U.S. investments in the major fusion burning plasma experiment known as ITER, coupled with a strong foundation of research funded by the Department of Energy (DOE), position the United States to begin planning for its first fusion pilot plant. Strong interest from the private sector is an additional motivating factor, as the process of decarbonizing and modernizing the nation's electric infrastructure accelerates and companies seek to lead the way. At the request of DOE, Bringing Fusion to the U.S. Grid builds upon the work of the 2019 report Final Report of the Committee on a Strategic Plan for U.S. Burning Plasma Research to identify the key goals and innovations - independent of confinement concept - that are needed to support the development of a U.S. fusion pilot plant that can serve as a model for producing electricity at the lowest possible capital cost.
Author: Grant Heiken
Publisher: CUP Archive
ISBN: 9780521334440
Category : Science
Languages : en
Pages : 796
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Book Description
The only work to date to collect data gathered during the American and Soviet missions in an accessible and complete reference of current scientific and technical information about the Moon.
Author: Stuart Ross Taylor
Publisher: Elsevier
ISBN: 1483136906
Category : Science
Languages : en
Pages : 393
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Book Description
Lunar Science: A Post-Apollo View: Scientific Results and Insights from the Lunar Samples explains the scientific results and discoveries of the manned Apollo lunar missions as they are understood. The emphasis is less on sample description and data and more on the interpretative aspects of the study, with the aim of providing a coherent story of the evolution of the moon and its origin as revealed by the lunar samples and the Apollo missions. This text has seven chapters; the first of which provides a historical background of efforts to study the moon prior to the Apollo missions, including lunar photogeologic mapping and direct exploration by spacecraft. Attention then turns to the Apollo missions and the lunar samples collected, beginning with Apollo 11 that landed on the moon on July 20, 1969 and followed by more missions. The next chapter describes the geology of the moon, with emphasis on craters, central peaks and peak rings, the large ringed basins, rilles, and maria lava flows. The reader is also introduced to the nature of the lunar surface material, the maria basalts, the highlands, and the moon’s interior. This book concludes with a discussion on the evidence that has been gathered by the Apollo missions that offers insights into the origin and evolution of the moon. An epilogue reflects on the usefulness of manned space flight. This book will appeal to lunar scientists as well as to those with an interest in astronomy and space exploration.
Author: David G. Lovering
Publisher: Springer
ISBN: 1475717245
Category : Education
Languages : en
Pages : 536
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Author:
Publisher:
ISBN:
Category : Lasers
Languages : en
Pages : 492
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