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MCNP5_manual_VOL_II
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MCNP5是一种蒙特卡洛模拟软件,主要用于模拟电子、光子、中子与物质相互作用,本文档是MCNP5的说明书~~
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4/24/03 i
Title:
MCNP — A General Monte Carlo
N-Particle Transport Code, Version 5
Volume II: User’s Guide
Authors:
X-5 Monte Carlo Team
LA-CP-03-0245
Los Alamos Controlled Publication;
distribution is limited
Los Alamos National Laboratory, an affirmative action/equal opportunity employer, is operated by the University of California for the U.S.
Department of Energy under contract W-7405-ENG-36. By acceptance of this article, the publisher recognizes that the U.S. Government
retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or to allow others to do so, for U.S.
Government purposes. Los Alamos National Laboratory requests that the publisher identify this article as work performed under the
auspices of the U.S. Department of Energy. Los Alamos National Laboratory strongly supports academic freedom and a researcher’s right to
publish; as an institution, however, the Laboratory does not endorse the viewpoint of a publication or guarantee its technical correctness.
Form 1756d (10/98)
DISTRIBUTION LIMITATION STATEMENT
Further dissemination authorized to U.S. Government agencies and their
contractors; other requests shall be approved by the X-5 Monte Carlo Team,
ORNL/RSICC, or by higher DOE programmatic authority.
April 24, 2003
ii 4/24/03
MCNP, MCNP5, and “MCNP Version 5” are trademarks of the Regents of the University of
California, Los Alamos National Laboratory.
COPYRIGHT NOTICE & DISCLAIMER
This material was prepared by the University of California (University) under Contract W-7405-
ENG-36 with the U.S. Department of Energy (DOE). All rights in the material are reserved by
DOE on behalf of the Government and the University pursuant to the contract. You are authorized
to use the material for Government purposes but it is not to be released or distributed to the public.
NEITHER THE UNITED STATES NOR THE UNITED STATES DEPARTMENT OF ENERGY,
NOR THE UNIVERSITY OF CALIFORNIA, NOR ANY OF THEIR EMPLOYEES, MAKES
ANY WARRANTY, EXPRESS OR IMPLIED, OR ASSUMES ANY LEGAL LIABILITY OR
RESPONSIBILITY FOR THE ACCURACY, COMPLETENESS, OR USEFULNESS OF ANY
INFORMATION, APPARATUS, PRODUCT, OR PROCESS DISCLOSED, OR REPRESENTS
THAT ITS USE WOULD NOT INFRINGE PRIVATELY OWNED RIGHTS.
4/24/03 iii
FOREWORD
This manual is a practical guide for the use of the general-purpose Monte Carlo code MCNP. The previous version of
the manual (LA-13709-M, March 2000) has been corrected and updated to include the new features found in MCNP
Version 5 (MCNP5). The manual has also been split into 3 volumes:
Volume I: MCNP Overview and Theory Chapters 1, 2 and Appendices G, H
Volume II: MCNP User’s Guide Chapters 1, 3, 4, 5 and Appendices A, B, I, J, K
Volume III: MCNP Developer’s Guide Appendices C, D, E, F
Volume I (LA-UR-03-1987) provides an overview of the capabilities of MCNP5 and a detailed discussion of the
theoretical basis for the code. The first chapter provides introductory information about MCNP5. The second chapter
describes the mathematics, data, physics, and Monte Carlo simulation techniques which form the basis for MCNP5.
This discussion is not meant to be exhaustive — details of some techniques and of the Monte Carlo method itself are
covered by references to the literature.
Volume II (LA-CP-03-0245) provides detailed specifications for MCNP5 input and options, numerous example
problems, and a discussion of the output generated by MCNP5. The first chapter is a primer on basic MCNP5 use.
The third chapter shows the user how to prepare input for the code. The fourth chapter contains several examples, and
the fifth chapter explains the output. The appendices provide information on the available data libraries for MCNP,
the format for several input/output files, and plotting the geometry, tallies, and cross-sections.
Volume III (LA-CP-03-0284) provides details on how to install MCNP on various computer systems, how to modify
the code, the meaning of some of the code variables, and data layouts for certain arrays.
The Monte Carlo method for solving transport problems emerged from work done at Los Alamos during World
War II. The method is generally attributed to Fermi, von Neumann, Ulam, Metropolis, and Richtmyer. MCNP, first
released in 1977, is the successor to their work and has been under continuous development for the past 25 years.
Neither the code nor the manual is static. The code is changed as needs arise, and the manual is changed to reflect the
latest version of the code. This particular manual refers to Version 5.
MCNP5 and this manual are the product of the combined effort of many people in the Diagnostics Applications Group
(X-5) in the Applied Physics Division (X Division) at the Los Alamos National Laboratory:
X-5 Monte Carlo Team
Thomas E. Booth John T. Goorley Avneet Sood
Forrest B. Brown H. Grady Hughes Jeremy E. Sweezy
Jeffrey S. Bull Russell D. Mosteller Richard F. Barrett (X-3)
Lawrence J. Cox Richard E. Prael Susan E. Post (CCN-8)
R. Arthur Forster Elizabeth C. Selcow Teresa L. Roberts (IM-8)
X-5 Data Team
Joann M. Campbell Robert C. Little Morgan C. White
Stephanie C. Frankle
Technical Editors
Sheila M. Girard Judith B. Shinn
The code and manual can be obtained from the Radiation Safety Information Computational Center (RSICC),
P. O. Box 2008, Oak Ridge, TN, 37831-6362.
Forrest B. Brown
MCNP Team Leader
<fbrown@lanl.gov>
iv 4/24/03
4/24/03 v
MCNP – A General Monte Carlo N-Particle Transport Code
Version 5
X-5 Monte Carlo Team
Diagnostics Applications Group
Los Alamos National Laboratory
ABSTRACT
MCNP is a general-purpose Monte Carlo N–Particle code that can be used for neutron, photon,
electron, or coupled neutron/photon/electron 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 fourth-degree
elliptical tori.
Pointwise cross-section data are used. For neutrons, all reactions given in a particular cross-section
evaluation (such as ENDF/B-VI) are accounted for. Thermal neutrons are described by both the
free gas and S(α,β) models. For photons, the code accounts for incoherent and coherent scattering,
the possibility of fluorescent emission after photoelectric absorption, absorption in pair production
with local emission of annihilation radiation, and bremsstrahlung. A continuous-slowing-down
model is used for electron transport that includes positrons, k x-rays, and bremsstrahlung, but does
not include external or self-induced fields.
Important standard features that make MCNP very versatile and easy to use include a powerful
general source, criticality source, and surface source; both geometry and output tally plotters; a rich
collection of variance reduction techniques; a flexible tally structure; and an extensive collection
of cross-section data.
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