References
- Hwang RN. A rigorous pole representation of multilevel cross sections and its practical applications. Nucl Sci Eng. 1987;96:192–209.
- Jammes C, Hwang RN. Generalized pole representation and interpolation of cross sections at any temperature. Lemont, IL: Argonne National Laboratory; 1999. (Report no. ANL-NT-101).
- Forget B, Xu S, Smith K. Direct Doppler broadening in Monte Carlo simulations using the multipole representation. Ann Nucl Energy. 2014;64:78–85.
- Josey C, Forget B, Smith K. Efficiency and accuracy evaluation of the windowed multipole direct Doppler broadening method. Paper presented at: PHYSOR; 2014 Sep 28–Oct 3; Kyoto.
- Henryson H II, Toppel BJ, Stenberg CG. MC22: a code to calculate fast neutron spectra and multigroup cross sections. Lemont, IL: Argonne National Laboratory; 1976. (Report no. Argonne-8144).
- Johnson SG. Faddeeva package – abinitio [Internet]. Cambridge (MA): Massachusetts Institute of Technology; c2012 [cited 2013 Nov 24]. Available from: http://ab-initio.mit.edu/wiki/index.php/Faddeeva_Package.
- Hwang RN. An extension of the rigorous pole representation of cross sections for reactor applications. Nucl Sci Eng. 1992;111:113–131.
- Chadwick MB, Herman M, Obložinskỳ P, Dunn ME, Danon Y, Kahler AC, Smith DL, Pritychenko B, Arbanas G, Arcilla R, Brewer R, Brown DA, Capote R, Carlson AD, Cho YS, Derrien H, Guber K, Hale GM, Hoblit S, Holloway S, Johnson TD, Kawano T, Kiedrowski BC, Kim H, Kunieda S, Larson NM, Leal L, Lestone JP, Little RC, McCutchan EA, MacFarlane RE, MacInnes M, Mattoon CM, McKnight RD, Mughabghab SF, Nobre GPA, Palmiotti G, Palumbo A, Pigni MT, Pronyaev VG, Sayer RO, Sonzogni AA, Summers NC, Talou P, Thompson IJ, Trkov A, Vogt RL, van der Mark SC, Wallner A, White MC. ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data. Nucl Data Sheets. 2011;112:2887–2996.
- Romano PK, Forget B. The OpenMC Monte Carlo particle transport code. Ann Nucl Energy. 2013;51:274–281.
- Horelik N, Herman B, Forget B, Smith K. MIT BEAVRS: benchmark for evaluation and validation of reactor simulations. Paper presented at: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering; 2013 May 5–9; Sun Valley, ID.