Neutronics and nuclear data: Achievements in computational simulations and experiments in support of fusion reactor design

Fusion Engineering and Design

Volumn 51-52, Issue , 2000, Pages 663-680

  Fischer, U ^a   Batistoni, P ^b   Ikeda, Y ^c   Youssef, M Z ^d  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b ENEA   (Italy)

^c JAPAN ATOMIC ENERGY AGENCY   (Japan)

^d UNIVERSITY OF CALIFORNIA   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; COMPUTER SIMULATION; DATABASE SYSTEMS; EXPERIMENTAL REACTORS; MONTE CARLO METHODS; SENSITIVITY ANALYSIS;

INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR (ITER); NEUTRONICS;

FUSION REACTORS;

EID: 0034314929     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(00)00236-2     Document Type: Article

References (44)

1. Greenspan H., Kelber C.N., Okrent D. Computational Methods in Reactor Physics. 1968;Gordon and Breach Science Publishers, New York.
2. W.W. Engle, A user's manual for ANISN, a one-dimensional discrete ordinates transport code with anisotropic scattering, Report K-1693, Union Carbide Corporation, 1967.
3. R.D. O'Dell, et al., User's manual for ONEDANT: a code package for one-dimensional diffusion-accelerated neutral particle transport, LA-9184-M, 1982.
4. R.E. Alcouffe, et al., DANTSYS 3.0 - a diffusion-accelerated, neutral-particle transport code system, Report LA-12969-M, Los Alamos National Laboratories, 1995.
5. Rhoades W.A., Childs R.L. DORT-TORT: two- and three-dimensional discrete ordinates transport. Nucl. Sci. Eng. 99:1989;88-89.
6. Lux I., Koblinger L. Monte Carlo Particle Transport Methods: Neutron and Photon Calculations. 1991;CRC Press, Boca Raton, FL.
7. F. Briesmeister (Ed.), MCNP - a general Monte Carlo N-particle transport code, version 4A, LA-12625-M, November 1993, Version 4B, March 1997.
8. D. Muir, S. Ganesan, A.B. Pashchenko, FENDL - a reference nuclear data library for fusion applications, International Conference on Nuclear Data for Science and Technology, Jülich, Germany, May 13-17, 1991.
9. FENDL/MC-1.0 - library of continuous energy cross-sections in ACE format for neutron-photon transport calculations with the Monte Carlo N-particle transport code system MCNP4A, generated by R.E. MacFarlane by processing FENDL/E-1.0, summary documentation by A.B. Pashchenko, H. Wienke, S. Ganesan, IAEA-NDS-169, Rev. 3, November 1995.
10. FENDL/MG-1.0 - Library of multigroup cross-sections in GENDF and MATXS format for neutron-photon transport calculations, generated by R.E. MacFarlane by processing FENDL/E-1.0, summary documentation by A.B. Pashchenko, H. Wienke, S. Ganesan, IAEA-NDS-129, Rev. 3, November 1995.
11. U. Fischer (Ed.), Integral data tests of the FENDL-1 nuclear data library for fusion applications, Summary Report of the International Working Group on Experimental and Calculational Benchmarks on Fusion Neutronics for FENDL Validation, FZKA-5785, INDC(GER)-41, August 1996.
12. Fischer U., et al. Benchmark validation of the FENDL-1 nuclear data library - a co-ordinated international effort. Fusion Technol. 30:1996;1093-1100.
13. M. Herman, A.B. Pashchenko (Eds.), Extension and improvement of the FENDL library for fusion applications (FENDL-2), Report on a Meeting Held in Vienna, Austria, March 3-7, 1997, Report INDC (NDS)-373, 1997.
14. Validation and improvement of the FENDL-2.0 transport sub-libraries, Summary Report on IAEA Consultant's Meeting, Vienna, Austria, October 12-14, 1998.
15. Sub working group of fusion reactor physics subcommittee (Ed.), Collection of experimental data for fusion neutronics benchmarks, Report JAERI-M 94-014, February 1994.
16. F. Maekawa, et al., Compilation of benchmark results for fusion related nuclear data, JAERI-Data/Code 98-024, 1998.
17. F. Maekawa, et al., Data collection of fusion neutronics benchmark experiment conducted at FNS/JAERI, JAERI-Data/Code 98-021, August 1998.
18. 252Cf neutron sources, Proceedings of the 17th Symposium on Fusion Technology, Rome, Italy, September 14-18, 1992, pp. 1489-1493.
19. U.v. Mollendrof, et al., A 14 MeV neutron transmission experiment on vanadium, Proceedings of the 19th Symposium in Fusion Technology, Lisbon, Portugal, September 16-20, 1996, pp. 1575-1578.
20. Elfruth T., et al. The neutron multiplication of lead at 14 MeV neutron incidence energy. Atomkernenergie Kerntechnik. 49:1987;121-125.
21. H. Freiesleben, W. Hansen, H. Klein, T. Novotny, D. Richter, R. Schwierz, K. Seidel, M. Tichy, S. Unholzer, Experimental results of an iron slab benchmark, Report TUD-PHY-94/2, TU Dresden, 1995.
22. Chen Y., et al. Experiments of neutron multiplication in beryllium. Fusion Technol. 19:1991;1919.
23. Chen Y., et al. Neutronics integral experiments. Hewuli Dongtai (Trends Nucl. Phys.). 12:(4):1995;54-57. in Chinese.
24. Smith J.R., et al. Multiplication of 14-MeV neutrons in bulk beryllium. Fusion Technol. 23:1993;51.
25. U. von Möllendorff, U. Fischer, H. Fries, H. Giese, F. Kappler, R. Tayama, T. Tsukiyama, E. Wiegner, Measurement and analysis of neutron leakage spectra from beryllium spherical shells, Proceedings of the 17th Symposium on Fusion Technology, Rome, Italy, September 14-18, 1992, pp. 1537-1541.
26. von Möllendorff U., Alevra A.V., Giese H., Kappler F., Klein H., Tayama R. Measurements of 14 MeV neutron multiplication in spherical beryllium shells. Fusion Eng. Des. 28:1995;737-744.
27. P. Batistoni, et al., Neutronics Shield Experiment for ITER at the Frascati neutron generator (FNG), Proceedings of the 19th Symposium on Fusion Technology, Lisboa, Portugal, September 16-20, 1996, pp. 233-238.
28. C. Konno, et al., Summary of bulk shield experiments for ITER at JAERI/FNS, Proceedings of the 20th Symposium on Fusion Technology, Marseille, France, September 7-11, 1998, pp. 1263-1266.
29. Fusion neutronics integral experiments, Parts I and II, Fusion Technol. 28 (1/2) (1995).
30. U. Fischer, R.L. Perel, H. Tsige-Tamirat, Monte Carlo uncertainty analyses for integral beryllium experiments, this conference.
31. 9Be reactions, Report LA-7932-MS, July 1979.
32. Drake M., et al. Double-differential beryllium neutron cross-sections at incident neutron energies of 5.9, 10.1 and 14.2 MeV. Nucl. Sci. Eng. 63:1977;401.
33. P. Song, M.Z. Youssef, M. Abdou, A new approach and computational algorithm for sensitivity/uncertainty analysis for SED and SAD with application to beryllium integral experiments, UCLA Report, University of California, Los Angeles, UCLA-FT-54, October 1991.
34. M. Angelone, P. Batistoni, L. Pettrizzi, M. Billon, Neutron streaming experiment at FNG: results and analysis, Fusion Eng. Des. 49-52 (2000).
35. I. Kideli, I. Kodeli, Sensitivity and Uncertainty Analysis of FNG 14 MeV Neutron Bulk Shield Experiment, 5th International Conference Radiation Shielding, October 18-21, 2000.
36. M.Z. Youssef, et al., Benchmarking FENDL libraries through analysis of bulk shielding experiments on large SS316 assemblies for verification of ITER shielding characteristics, 12th Topical Meeting on the Technology of Fusion Energy, Reno, Nevada, June 16-20, 1996.
37. C. Konno, et al., Some comments for cross section data of iron around 15 MeV, 13th Topical Meeting on the Technology of Fusion Energy, Nashville, Tennessee, June 7-11, 1998.
38. Y. Ikeda, et al., Experimental validation of nuclear heating for ITER structural materials, Proceedings of the 20th Symposium on Fusion Technology, Marseille, France, September 7-11, 1998, pp. 1469-1472.
39. Taylor N.P., Ikeda Y., et al. Experimental validation of calculations of decay heat induced by 14 MeV neutron activation of ITER materials. Fusion Eng. Des. 45:1999;75-88.
40. F. Maekawa, et al., Decay heat experiment featuring low-energy neutron induced tungsten-187 production in ITER baffle plates and its analysis, Fusion Eng. Des. 49-52 (2000).
41. Y. Wu, et al., Integral data tests of FENDL-2 fusion nuclear data library with neutronic integral experiments, Ninth International Conference on Radiation Shielding, Tsukuba, Japan, October 17-22, 1999.
42. FORSS: A Sensitivity and Uncertainty Analysis Code System, CCC-334, Radiation Shielding Information Centre, Oak Ridge National Laboratory, 1983.
43. N transport (BISTRO), International Topical Meeting on Reactor Physics, Paris, France, April 27-30, 1987.
44. K. Furuta, Y. Oka, S. Kondo, SUSD: a computer code for cross section sensitivity and uncertainty analysis including secondary neutron energy and angular distributions, UTNL-R-0185, 1986.