ONIX: An open-source depletion code

被引：13

作者：

de Lanversin, J. de Troullioud ^{[1
]}

Kuett, M. ^{[2
]}

Glaser, A. ^{[3
]}

机构：

[1] Stanford Univ, Ctr Int Secur & Cooperat CISAC, 616 Jane Stanford Way, Stanford, CA 94305 USA

[2] Univ Hamburg IFSH, Inst Peace Res & Secur Policy, Beim Schlump 83, D-20144 Hamburg, Germany

[3] Princeton Univ, Program Sci & Global Secur, 221 Nassau St,2nd Floor, Princeton, NJ 08542 USA

来源：

ANNALS OF NUCLEAR ENERGY | 2021年 / 151卷

关键词：

Burnup; Depletion; Open source; ONIX; OpenMC; Validation;

D O I：

10.1016/j.anucene.2020.107903

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Open Source software enables innovative, community-based software development. ONIX brings this concept to the field of depletion calculations. It is an open-source depletion software to be used for nuclear reactor simulations, for fissile material production analysis as well as for nuclear arms control applications. ONIX provides a module to solve the depletion equation using a Chebyshev Rational Approximation Method. For the generation of one-group cross sections, it includes a coupling interface for the open-source neutron transport code, OpenMC, as well as a module to read pre-computed values in a stand-alone mode. ONIX has special features to optimize nuclear data libraries, to update isomeric branching ratio during burnup, and to support automation of simulations for nuclear archaeology. ONIX has been validated against results from numerical and experimental benchmarks, and its results agree with other methods within expected error ranges. (C) 2020 Elsevier Ltd. All rights reserved.

引用

页数：13

共 34 条

[1] GEANT4-a simulation toolkit [J].

Agostinelli, S ;

Allison, J ;

Amako, K ;

Apostolakis, J ;

Araujo, H ;

Arce, P ;

Asai, M ;

Axen, D ;

Banerjee, S ;

Barrand, G ;

Behner, F ;

Bellagamba, L ;

Boudreau, J ;

Broglia, L ;

Brunengo, A ;

Burkhardt, H ;

Chauvie, S ;

Chuma, J ;

Chytracek, R ;

Cooperman, G ;

Cosmo, G ;

Degtyarenko, P ;

Dell'Acqua, A ;

Depaola, G ;

Dietrich, D ;

Enami, R ;

Feliciello, A ;

Ferguson, C ;

Fesefeldt, H ;

Folger, G ;

Foppiano, F ;

Forti, A ;

Garelli, S ;

Giani, S ;

Giannitrapani, R ;

Gibin, D ;

Cadenas, JJG ;

González, I ;

Abril, GG ;

Greeniaus, G ;

Greiner, W ;

Grichine, V ;

Grossheim, A ;

Guatelli, S ;

Gumplinger, P ;

Hamatsu, R ;

Hashimoto, K ;

Hasui, H ;

Heikkinen, A ;

Howard, A .

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2003, 506 (03) :250-303

[2]

Anderson E., 1999, LAPACK USERSGUIDE

[3]

Bell M.J., 1973, ORNL4628 OAK RIDG NA

[4] ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data [J].

Brown, D. A. ;

Chadwick, M. B. ;

Capote, R. ;

Kahler, A. C. ;

Trkov, A. ;

Herman, M. W. ;

Sonzogni, A. A. ;

Danon, Y. ;

Carlson, A. D. ;

Dunn, M. ;

Smith, D. L. ;

Hale, G. M. ;

Arbanas, G. ;

Arcilla, R. ;

Bates, C. R. ;

Beck, B. ;

Becker, B. ;

Brown, F. ;

Casperson, R. J. ;

Conlin, J. ;

Cullen, D. E. ;

Descalle, M. -A. ;

Firestone, R. ;

Gaines, T. ;

Guber, K. H. ;

Hawari, A. I. ;

Holmes, J. ;

Johnson, T. D. ;

Kawano, T. ;

Kiedrowski, B. C. ;

Koning, A. J. ;

Kopecky, S. ;

Leal, L. ;

Lestone, J. P. ;

Lubitz, C. ;

Marquez Damian, J. I. ;

Mattoon, C. M. ;

McCutchan, E. A. ;

Mughabghab, S. ;

Navratil, P. ;

Neudecker, D. ;

Nobre, G. P. A. ;

Noguere, G. ;

Paris, M. ;

Pigni, M. T. ;

Plompen, A. J. ;

Pritychenko, B. ;

Pronyaev, V. G. ;

Roubtsov, D. ;

Rochman, D. .

NUCLEAR DATA SHEETS, 2018, 148 :1-142

[5] IAEA CIELO Evaluation of Neutron-induced Reactions on 235U and 238U Targets [J].

Capote, R. ;

Trkov, A. ;

Sin, M. ;

Pigni, M. T. ;

Pronyaev, V. G. ;

Balibrea, J. ;

Bernard, D. ;

Cano-Ott, D. ;

Danon, Y. ;

Daskalakis, A. ;

Goricanec, T. ;

Herman, M. W. ;

Kiedrowski, B. ;

Kopecky, S. ;

Mendoza, E. ;

Neudecker, D. ;

Leal, L. ;

Noguere, G. ;

Schillebeeckx, P. ;

Sirakov, I. ;

Soukhovitskii, E. S. ;

Stetcu, I. ;

Talou, P. .

NUCLEAR DATA SHEETS, 2018, 148 :254-292

[6]

Carter L., 1975, Tech. Rep. LA-5903-MS

[7] ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology [J].

Chadwick, M. B. ;

Oblozinsky, P. ;

Herman, M. ;

Greene, N. M. ;

McKnight, R. D. ;

Smith, D. L. ;

Young, P. G. ;

MacFarlane, R. E. ;

Hale, G. M. ;

Frankle, S. C. ;

Kahler, A. C. ;

Kawano, T. ;

Little, R. C. ;

Madland, D. G. ;

Moller, P. ;

Mosteller, R. D. ;

Page, P. R. ;

Talou, P. ;

Trellue, H. ;

White, M. C. ;

Wilson, W. B. ;

Arcilla, R. ;

Dunford, C. L. ;

Mughabghab, S. F. ;

Pritychenko, B. ;

Rochman, D. ;

Sonzogni, A. A. ;

Lubitz, C. R. ;

Trumbull, T. H. ;

Weinman, J. P. ;

Brown, D. A. ;

Cullen, D. E. ;

Heinrichs, D. P. ;

McNabb, D. P. ;

Derrien, H. ;

Dunn, M. E. ;

Larson, N. M. ;

Leal, L. C. ;

Carlson, A. D. ;

Block, R. C. ;

Briggs, J. B. ;

Cheng, E. T. ;

Huria, H. C. ;

Zerkle, M. L. ;

Kozier, K. S. ;

Courcelle, A. ;

Pronyaev, V. ;

van der Marck, S. C. .

NUCLEAR DATA SHEETS, 2006, 107 (12) :2931-3059

[8]

Chanteloup F., 2017, ORILL

[9]

Croff A.G., 1980, USERS MANUAL ORIGEN2

[10] ORIGEN2 - A VERSATILE COMPUTER CODE FOR CALCULATING THE NUCLIDE COMPOSITIONS AND CHARACTERISTICS OF NUCLEAR-MATERIALS [J].

CROFF, AG .

NUCLEAR TECHNOLOGY, 1983, 62 (03) :335-352

← 1 2 3 4 →