Quantification of Uncertainties for Evaluated Neutron-Induced Reactions on Actinides in the Fast Energy Range

Nuclear Data Sheets

Volumn 112, Issue 12, 2011, Pages 3054-3074

  Talou, P ^a   Young, P G ^a   Kawano, T ^a   Rising, M ^b   Chadwick, M B ^c  

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

^b University of New Mexico   (United States)

^c LOS ALAMOS NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

COVARIANCE MATRIX;

COVARIANCE EVALUATIONS; COVARIANCE MATRICES; ENERGY RANGES; LOW FIDELITIES; MODEL CALCULATIONS; NEUTRON-INDUCED REACTIONS; UNCERTAINTY;

ACTINIDES;

EID: 84855922987     PISSN: 00903752     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nds.2011.11.005     Document Type: Article

References (51)

1. M. Herman, P. Obložinský, C.M. Mattoon, M. Pigni, S. Hoblit, S.F. Mughabghab, A. Sonzogni, P. Talou, M.B. Chadwick, G.M. Hale, A.C. Kahler, T. Kawano, R.C. Little, and P.G. Young, "COMMARA-2.0 Neutron Cross Section Covariance Library," BNL-94830-2011 Technical Report (2011).
2. Chadwick M.B., Obložinský 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., Möller 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. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology. Nuclear Data Sheets 2006, 107:2931.
3. Chadwick M.B., Herman M., Obložinský P., et al. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data. Nuclear Data Sheets 2011, 112:2887.
4. L. Leal, K. Guber, D. Wiarda, D. Arbanas, H. Derrien, R. Sayer, N.M. Larson, M.E. Dunn, "ORNL Resolved Resonance Covariance Generation for ENDF/B-VII.1," Nuclear Data Sheets, submitted.
5. "Covariance Data in the Fast Neutron Region," M. Herman, Coordinator, A. Koning, Monitor, OECD, NEA/WPEC-24 (2011).
6. An Essay towards Solving a Problem in the Doctrine of Chances. Phil. Trans. 1763, 53:370. Rev. Mr. Bayes.
7. 239Pu. Nucl. Sci. Eng. 2010, 166:254.
8. J. Raynal, "Notes on ECIS94," Centre d'Études Nucléaires, Saclay, report CEA-N-2772 (1994).
9. Young P.G., Arthur E.D., Chadwick M.B. Comprehensive Nuclear Model Calculations: Theory and Use of the GNASH Code. Proceedings of the Workshop on Nuclear Reaction Data and Nuclear Reactors 1998, 227-404. World Scientific Publ. Co., Singapore. A. Gandini, G. Reffo (Eds.).
10. Kawano T., Talou P., Chadwick M.B., Watanabe T. Monte Carlo Simulation for Particle and Gamma-Ray Emissions in Statistical Hauser-Feshbach Model. J. Nucl. Sci. Tech. 2010, 47(5):462.
11. P. Talou, "Prompt Fission Neutron Calculations in the Madland-Nix Model", P. Talou, LANL Technical Report, LA-UR-07-8168 (2007).
12. Madland D.G., Nix J.R. New calculation of prompt fission neutron spectra and average prompt neutron multiplicities. Nucl. Sci. Eng. 1982, 81:213.
13. T. Kawano and K. Shibata, "Covariance Evaluation System," JAERI-Data/Code 97-037 (in Japanese) Technical Report (1997).
14. R.E. MacFarlane, "The NJOY Nuclear Data Processing System, Version 91", Los Alamos National Laboratory Technical Report, LA-1274-M (1994).
15. Leeb H., Neudecker D., Srdinko Th. Consistent Procedure for Nuclear Data Evaluation Based on Modeling. Nuclear Data Sheets 2008, 109(12):2762.
16. 239Pu evaluated files in the fast energy range. Proceedings of the International Conference on Nuclear Data for Science and Technology 2008, 293. EDP Sciences. O. Bersillon, F. Gunsing, E. Bauge, R. Jacqmin, S. Leray (Eds.).
17. 239Pu for ENDF/B-VI. Proc. Int. Conf. on Nuclear Data for Science and Technology 1992, 894. Springer-Verlag. S.M. Qaim (Ed.).
18. Capote R., Herman M., Obložinský P., Young P.G., Goriely S., Belgya T., Ignatyuk A.V., Koning A.J., Hilaire S., Plujko V.A., Avrigeanu M., Bersillon O., Chadwick M.B., Fukahori T., Ge Zhigang, Han Yinlu, Kailas S., Kopecky J., Maslov V.M., Reffo G., Sin M., Soukhovitskii E.Sh., Talou P. RIPL - Reference Input Parameter Library for Calculations of Nuclear Reactions and Nuclear Data Evaluations. Nuclear Data Sheets 2009, 110:3107.
19. Carlson A.D., Pronyaev V.G., Smith D.L., Larson N.M., Zhenpeng Chen, Hale G.M., Hambsch F.-J., Gai E.V., Oh Soo-Youl, Badikov S.A., Kawano T., Hofmann H.M., Vonach H., Tagesen S. International Evaluation of Neutron Cross Section Standards. Nuclear Data Sheets 2009, 110:3215.
20. 235U (n,2n) Cross Section between Threshold and 13 MeV. Nucl. Sci. Eng. 1980, 74:29.
21. D.S. Mather, P.F. Bampton, R.E. Coles, G. James, and N.J. Nind, "Measurement of (n,2n) Cross Sections for Incident Energies between 6 and 14 MeV," Aldermaston Report AWRE-O-72/72 (1972).
22. Fröhner F.H. Nucl. Sci. Eng. 1988, 103.
23. F.H. Fröhner, Proc. Int. Conf. on Reactor Phys., Jackson Hole, Wyoming (1988) Vol. III, p. 171.
24. Poenitz W.P., Fawcett L.R., Smith D.L. Nucl. Sci. Eng. 1981, 78:239.
25. Y. Kanda and M. Baba, "WPEC-SG4 Report: 238U Capture and Related Cross Sections," Tech. Rep. WPEC/SG4, NEA, Paris (1999).
26. Drake D., Bergqvist I., McDaniels D.K. Dependence of 14 MeV Radiative Neutron Capture on Mass Number. Phys. Lett. B 1971, 36:557.
27. 238U. Nucl. Phys. A 1982, 384:88.
28. L.R. Veeser and E.D. Arthur, "Measurement of (n,3n) Cross Sections for U-235 and U-238," Proc. Int. Conf. on Neutron Physics and Nuclear Data for Reactors and Other Applied Purposes, AERE Harwell, U.K., 25-29 Sep. 1978, p. 1054.
29. J. Frehaut, Nuclear Energy Agency Nuclear Data Committee Report NEANDC(E) 238/L (1986).
30. J. Taieb, T. Granier, T. Ethvignot, M. Devlin, R.C. Haight, R.O. Nelson, J.M. O'Donnell, and D. Rochman, "Measurement of the Average Energy and Multiplicity of Prompt Fission Neutrons from 238U (n,f) and 237Np (n,f) from 1 to 200 MeV," Proc. Int. Conf. on Nuclear Data for Science and Technology, Nice, France, April 2007, Vol. 1, p. 429 (2007).
31. 238U by Neutron with Energies 2.9 and 14.7 MeV. Yad. Fiz. 1991, 53(3):628.
32. Silbert M.G., Berreth J.R. Neutron Capture Cross Section of Plutonium-238: Determination of Resonance Parameters. Nucl. Sci. Eng. 1973, 52:187.
33. Tudora A. Systematic Behaviour of the Average Parameters Required for the Los Alamos Model of Prompt Neutron Emission. Annals of Nuclear Energy 2009, 36:72.
34. Jaffey A.H., Lerner J.L. Measurement of Prompt Neutron Fission Yield in Thermal Neutron Fission of U-232, Pu-238, Pu-241, Am-241, Am-242m, Cm-243, Cm-245 and in Spontaneous Fission of Cm-244. Nucl. Phys. A 1970, 145:1.
35. Kroshkin N.I., Zamjatnin J.S. The Measurement of Energy Spectra and Average Number of Prompt Fission Neutrons. Atomic Energy 1970, 29:95.
36. J.J. Ressler, J.T. Burke, J.E. Escher, C.T. Angell, M.S. Basunia, C.W. Bausang, L.A. Bernstein, D.L. Bleuel, B.L. Goldblum, J. Gostic, R. Hatarik, R.A. Henderson, J. Munson, E.B. Norman, L.W. Phair, T. Ross, N.D. Scielzo, M. Wiedeking, "Surrogate Measurement of the 238Pu (n,f) Cross Section", LLNL Technical Report LLNL-TR-457798 (2010).
37. 238Pu (n,f) Cross-Section. CP 2009, vol. 1175:227. AIP. A. Chatillon, H. Faust, G. Fioni, D. Goutte, H. Goutte (Eds.).
38. Shcherbakov O.A., Donets A.Yu., Evdokimov A.V., Fomichev A.V., Fukahori T., Hasegawa A., Laptev A.B., Maslov V.M., Petrov G.A., Tuboltsev Yu.V., Vorobiev A.S. Neutron-Induced Fission of U-233, U-238, Th-232, Pu-239, Np-237, nat-Pb and Bi-209 Relative to U-235 in the Energy Range 1-200 MeV. J. Nucl. Science and Technology, Tokyo, Supplement 2002, 2(1):230.
39. n=0.01eV to 200 MeV. Nucl. Sci. Eng. 2010, 165:224.
40. R. Batchelor and K. Wyld, "Neutron Scattering by 235U and 239Pu for Incident Neutrons of 2, 3 and 4 MeV," Report AWRE-O-55/69 (1969).
41. Andreev V.N. Inelastic Scattering of Neutrons of the Fission Spectrum and Neutrons with an Energy of 0.9 MeV in U2 and Pu239. Nejtronfiz 1961, 287.
42. 238Pu Cross Section Deduced Using a Combination of Experiment and Theory. Phys. Rev. C 2002, 65:021601.
43. 241Am (n,2n) Cross-Section Measurements Near En = 14 MeV. Radiochim. Acta 2002, 90:833.
44. J. Frehaut, A. Bertin, R. Blois, E. Gryntakis, and C.A. Philis, "(n,2n) Cross Sections of 2-H and 239-Pu," Proc. Int. Conf. on Basic and Applied Science, Santa Fe, NM, 1985, p. IB06 (1985).
45. 252Cf. Nucl. Sci. Eng. 1986, 94:365.
46. 238Pu. Nucl. Sci. Eng. 1967, 30:355.
47. 242Pu from 1 eV to 200 MeV. Phys. Rev. C 2009, 79:014613.
48. A.V. Laptev, A.Yu. Donets, V.N. Dushin, A.V. Fomichev, A.A. Fomichev, R.C. Haight, O.A. Shcherbakov, S.M. Soloviev, Yu.V. Tuboltsev, and A.S. Vorobyev, "Neutron-Induced Fission Cross Sections of 240Pu, 243Am, and natW in the Energy Range 1-200 MeV", Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2004, Sep. 26-Oct. 1, 2004, Santa Fe, USA, AIP CP769, Eds. R.C. Haight, M.B. Chadwick, T. Kawano, and P. Talou, p. 865 (2004).
49. Soukhovitskii E., Chiba S., Lee J.-Y., Iwamoto O., Fukahori T. Global coupled-channel optical potential for nucleon-actinide interaction from 1 keV to 200 MeV. Journal Phys. G: Nucl. Part. Phys. 2004, 30:905.
50. Palmiotti G., Salvatores M., Aliberti G., Hiruta H., McKnight R., Obložinský P., Yang W.S. A Global Approach to the Physics Validation of Simulation Codes for Future Nuclear Systems. Annals of Nuclear Energy 2009, 36:355.
51. Aliberti G., Palmiotti G., Salvatores M., Kim T.K., Taiwo T.A., Anitescu M., Kodeli I., Sartori E., Bosq J.C., Tommasi J. Nuclear Data Sensitivity, Uncertainty and Target Accuracy Assessment for Future Nuclear Systems. Annals of Nuclear Energy 2006, 33:700.