Neutronics analysis of the international thermonuclear experimental reactor (ITER) MCNP "Benchmark CAD Model" with the ATTILA discrete ordinance code

Fusion Engineering and Design

Volumn 83, Issue 10-12, 2008, Pages 1661-1668

  Youssef, Mahmoud Z ^a   Feder, Russell ^b   Davis, Ian M ^c  

^a UNIVERSITY OF CALIFORNIA   (United States)

^b PRINCETON PLASMA PHYSICS LABORATORY   (United States)

^c Transpire Inc   (United States)

Author keywords

ATTILA discrete ordinates code; CAD based Neutronics Model; Codes verification; ITER neutronics benchmarking; Nuclear quality assurance

Indexed keywords

BENCHMARKING; CODES (SYMBOLS); DESIGN; EXPERIMENTAL REACTORS; FUSION REACTORS; MILITARY OPERATIONS; MODAL ANALYSIS; PROCESS ENGINEERING; QUALITY ASSURANCE; THREE DIMENSIONAL; TOTAL QUALITY MANAGEMENT; TURNAROUND TIME;

ATTILA DISCRETE ORDINATES CODE; CAD-BASED NEUTRONICS MODEL; CODES VERIFICATION; ITER NEUTRONICS BENCHMARKING; NUCLEAR QUALITY ASSURANCE;

COMPUTER AIDED DESIGN;

EID: 56949087325     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2008.05.040     Document Type: Article

References (11)

1. In: Breismeister J.F. (Ed). MCNP-A general Monte Carlo Code for Neutron and Photon Transport, LA-13709-M (2000), Los Alamos National Laboratory, Los Alamos, New Mexico
2. M. Herman, A.B. Pashchenko, Extension and improvement of the FENDL library for fusion applications (FENDL-2), Report INDC (NDS)-373, IAEA, Vienna, 1997.
3. ATTILA: comprehensive radiation transport solution environment, http://www.radiative.com/Attila-010505.pdf.
4. Youssef M.Z., Batistoni P., Patrizzi L., Wareing T., and Davis I.M. Comparing the prediction of "Attila" code to the experimental data of fusion integral experiments and to the results of MCNP code. Proceedings of the 17th Topical Meeting on the Technology of Fusion Energy. Albuquerque, NM, USA, November 13-15 (2006)
5. Youssef M.Z., Feder R., and Wareing T. Benchmarking the CAD-based ATTILA discrete ordinates code with experimental data of fusion experiments and to the results of MCNP code in simulating ITER. A Paper Submitted to the 13th International Conference on Emerging System (ICENES2007). Istanbul, Turkey, June 3-8 (2007)
6. Fischer U., Serikov A., and Tsige-Tamirat H. ITER benchnmark on CAD-MCNP interface. Progress Review Meeting on Procedures and Tools for ITER Neutronics. UW-Madison, USA, July 24-26 (2006)
7. P. Wilson, M. Sawan, B. Kiedrowski, T. Tautgas, D. Henderson, G. Sviatoslavsky, MCNPX-CGM & the ITER CAD-neutronics benchmark, 2006 (see above reference).
8. The Progress Review Meeting on Neutronics Analyses for ITER, Cadarache, France, March 26-27, 2007, http://www.iter.org/bl/WBS_Webs/Safety_Web/Meetings/Neutronics_March07/.
9. Morel J.E. A hybrid collocation-Galerkin-Sn method for solving the Boltzmann transport equation. Nucl. Sci. Eng. 101 (1989) 72-87
10. ITER Nuclear Analysis Report (NAR, 1998, ITER FEAT 2001 and ITER FEAT Rev., 2004).
11. P.P.H. Wilson, R. Feder, U. Fischer, M. Loughlin, L. Petrizzi, Y. Wu, M. Youssef, State-of-the-art 3-d neutronics analysis methods for fusion energy systems, this issue.