MCNPX-PoliMi for nuclear nonproliferation applications

被引：106

作者：

Pozzi, S. A. ^{[1
]}

Clarke, S. D. ^{[1
]}

Walsh, W. J. ^{[1
]}

Miller, E. C. ^{[1
]}

Dolan, J. L. ^{[1
]}

Flaska, M. ^{[1
]}

Wieger, B. M. ^{[1
]}

Enqvist, A. ^{[1
]}

Padovani, E. ^{[2
]}

Mattingly, J. K. ^{[3
]}

Chichester, D. L. ^{[4
]}

Peerani, P. ^{[5
]}

机构：

[1] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA

[2] Politecn Milan, Dept Energy, Milan, Italy

[3] N Carolina State Univ, Dept Nucl Engn, Raleigh, NC 27695 USA

[4] Idaho Natl Lab, Idaho Falls, ID 83415 USA

[5] Commiss European Communities, Joint Res Ctr, ITU, I-21020 Ispra, VA, Italy

来源：

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | 2012年 / 694卷

基金：

美国国家科学基金会;

关键词：

MCNP; MCNPX-PoliMi; Liquid scintillator; Nonproliferation; Mixed-oxide fuel; Plutonium oxide; NEUTRON;

D O I：

10.1016/j.nima.2012.07.040

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

This paper describes the use of the Monte Carlo code MCNPX-PoliMi for nuclear-nonproliferation applications, with particular emphasis on the simulation of spontaneous and neutron-induced nuclear fission. New models for the outgoing neutrons and gamma rays emitted in spontaneous and induced fission are described. For spontaneous fission, the models include prompt neutron energy distributions that depend on the number of neutrons emitted in the individual fission events. For neutron-induced fission, due to lack of data, the prompt neutron energy distributions are independent of the number of neutrons emitted in the individual fission events. Gamma rays are sampled independently of the neutrons. Code validation is performed on well-characterized mixed-oxide fuel and plutonium-oxide samples. (C) 2012 Elsevier B.V. All rights reserved.

引用

页码：119 / 125

页数：7

共 18 条

[1]

Briesmeister J.F., 2000, MCNP-A general Monte Carlo N -particle transport code, version 4A, V2

[2]

Dolan J., 2009, J. Nucl. Mat. Manag, V38, P40

[3] Measurement and simulation of neutron/gamma-ray cross-correlation functions from spontaneous fission [J].

Enqvist, Andreas ;

Flaska, Marek ;

Pozzi, Sara .

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2008, 595 (02) :426-430

[4]

Klann R.T., 2001, ANLNT176 NUCL TECHN

[5] Monte Carlo approach to sequential neutron emission from fission fragments [J].

Lemaire, S ;

Talou, P ;

Kawano, T ;

Chadwick, MB ;

Madland, DG .

PHYSICAL REVIEW C, 2005, 72 (02)

[6]

Marseguerra M., 2001, P 3 IMACS SEM MONT C

[7]

MATTINGLY J. K., 1998, THESIS U TENNESSEE

[8]

Miller E.C., 2011, T I NUCL MAT MAN 52

[9]

Padovani E., 2002, VALIDATION MONTE C 2

[10]

PADOVANI E., 2012, MCNPX-PoliMi User's Manual, C00791 MNYCP

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