Techniques In Fast Reactor Critical Experiments

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Techniques In Fast Reactor Critical Experiments

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Author : W. G. Davey
language : en
Publisher: Gordon & Breach Publishing Group
Release Date : 1970

Techniques In Fast Reactor Critical Experiments written by W. G. Davey and has been published by Gordon & Breach Publishing Group this book supported file pdf, txt, epub, kindle and other format this book has been release on 1970 with Breeder reactors categories.

Exponential And Critical Experiments

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Author : International Atomic Energy Agency
language : en
Publisher:
Release Date : 1964

Exponential And Critical Experiments written by International Atomic Energy Agency and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1964 with Nuclear engineering categories.

Lessons Learned From Applying Vim To Fast Reactor Critical Experiments

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Author :
language : en
Publisher:
Release Date : 1995

Lessons Learned From Applying Vim To Fast Reactor Critical Experiments written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1995 with categories.

VIM is a continuous energy Monte Carlo code first developed around 1970 for the analysis of plate-type, fast-neutron, zero-power critical assemblies. In most respects, VIM is functionally equivalent to the MCNP code but it has two features that make uniquely suited to the analysis of fast reactor critical experiments: (1) the plate lattice geometry option, which allows efficient description of and neutron tracking in the assembly geometry, and (2) a statistical treatment of neutron cross section data in the unresolved resonance range. Since its inception, VIM's capabilities have expanded to include numerous features, such as thermal neutron cross sections, photon cross sections, and combinatorial and other geometry options, that have allowed its use in a wide range of neutral-particle transport problems. The earliest validation work at Argonne National Laboratory (ANL) focused on the validation of VIM itself. This work showed that, in order for VIM to be a ''rigorous'' tool, extreme detail in the pointwise Monte Carlo libraries was needed, and the required detail was added. The emphasis soon shifted to validating models, methods, data and codes against VIM. Most of this work was done in the context of analyzing critical experiments in zero power reactor (ZPR) assemblies. The purpose of this paper is to present some of the lessons learned from using VIM in ZPR analysis work. This involves such areas as uncovering problems in deterministic methods and models, pitfalls in using Monte Carlo codes, and improving predictions. The numerical illustrations included here were taken from the extensive documentation cited as references.

Lessons Learned From Applying Vim To Fast Reactor Critical Experiments Summary

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Author :
language : en
Publisher:
Release Date : 1995

Lessons Learned From Applying Vim To Fast Reactor Critical Experiments Summary written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1995 with categories.

VIM is a continuous energy Monte Carlo code first developed around 1970 for the analysis of plate-type, fast-neutron, zero-power critical assemblies. In most respects, VIM is functionally equivalent to the MCNP code but it has two features that make uniquely suited to the analysis of fast reactor critical experiments: (1) the place lattice geometry option, which allows efficient description of and neutron tracking in the assembly geometry, and (2) a statistical treatment of neutron cross section data in the unresolved resonance range. Since its inception, VIM's capabilities have expanded to include numerous features, such as thermal neutron cross sections, photon cross sections, and combinatorial and other geometry options, that have allowed its use in a wide range of neutral-particle transport problems. The earliest validation work at Argonne National Laboratory (ANL) focused on the validation of VIM itself. This work showed that, in order for VIM to be a ''rigomus'' tool, extreme detail in the pointwise Monte Carlo libraries was needed, and the required detail was added. The emphasis soon shifted to validating models, methods, data and codes against VIM. Most of this work was done in the context of analyzing critical experiments in zero power reactor (ZPR) assemblies. The purpose of this paper is to present some of the lessons learned from using VIM in ZPR analysis work.

The Physics Of Fast Reactor Operation And Design

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Author :
language : en
Publisher:
Release Date : 1969

The Physics Of Fast Reactor Operation And Design written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1969 with Fast reactors categories.

Three Dimensional Nodal Diffusion And Transport Methods For The Analysis Of Fast Reactor Critical Experiments

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Author :
language : en
Publisher:
Release Date : 1984

Three Dimensional Nodal Diffusion And Transport Methods For The Analysis Of Fast Reactor Critical Experiments written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1984 with categories.

This paper describes two new nodal methods for solving the multigroup neutron diffusion and transport equations in three-dimensional Cartesian geometry. These methods have been developed for the global analysis of fast-reactor critical experiments once cell-averaged multigroup cross sections for each matrix position or drawer have been computed using appropriate cell-homogenization procedures. Brief descriptions of the nodal diffusion and transport schemes are presented, along with results of two- and three-dimensional calculations for a current Zero Power Plutonium Reactor (ZPPR) configuration.

Progress In Reactor Physics

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Author : Virgil W. Lower
language : en
Publisher:
Release Date : 1969

Progress In Reactor Physics written by Virgil W. Lower and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1969 with Nuclear reactors categories.

Reactor Physics Quarterly Report

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Author :
language : en
Publisher:
Release Date : 1968

Reactor Physics Quarterly Report written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1968 with Nuclear physics categories.

The objective of the Reactor Physics Quarterly Report is to inform the scientific community in a timely manner of the technical progress made on the many phases of reactor physics work within the laboratory. The report contains brief technical discussions of accomplishments in all areas where significant progress has been made during the quarter. The results presented herein should be considered preliminary, and do not constitute final publication of the work. A list of publications and papers issued during the last quarter is included in the report. Anyone desiring additional information concerning the work reported herein is encouraged to contact the author directly.

Lmfbr

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Author : Argonne National Laboratory
language : en
Publisher:
Release Date : 1968

Lmfbr written by Argonne National Laboratory and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1968 with Breeder reactors categories.

Analysis And Evaluation Of Zppr Zero Power Physics Reactor Critical Experiments For A 100 Kilowatt Electric Space Reactor

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Author :
language : en
Publisher:
Release Date : 1990

Analysis And Evaluation Of Zppr Zero Power Physics Reactor Critical Experiments For A 100 Kilowatt Electric Space Reactor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1990 with categories.

ZPPR critical experiments were used for physics testing the reactor design of the SP-100, a 100-kW thermoelectric LMR that is being developed to provide electrical power for space applications. These tests validated all key physics characteristics of the design, including the ultimate safety in the event of a launch or re-entry accident. Both the experiments and the analysis required the use of techniques not previously applied to fast reactor designs. A few significant discrepancies between the experimental and calculated results leave opportunities for further optimization. An initial investigation has been made into application of the ZPPR-20 results, along with those of other relevant integral data, to the SP-100 design. 13 refs., 5 figs., 7 tabs.