Some Facts About Neutron and Reactor Physics - The Risks of Nuclear Energy Technology - page 29

References
1. Lamarsh JR (1983) Introduction to nuclear reactor theory, 2nd edn. Addison-Wesley, Reading,
MA
2. Glasstone S, Edlund MC (1952) Nuclear reactor theory. D. Van Nostrand, Princeton, NJ
3. Ott K et al (1983) Introductory nuclear reactor statics. American Nuclear Society, LaGrange
Park, IL
4. Weinberg AM, Wigner EP (1958) The physical theory of neutron chain reactors. University of
Chicago Press, Chicago, IL
5. Bell GI, Glasstone S (1970) Nuclear reactor theory. Van Nostrand Reinhold, New York, NY
6. Ash M (1965) Nuclear reactor kinetics. McGraw-Hill, New York, NY
7. Keepin GR (1965) Physics of nuclear kinetics. Addison-Wesley, Reading, MA
8. Ott KO et al (1985) Nuclear reactor dynamics. American Nuclear Society, LaGrange Park, IL
9. Broeders CHM (2010) Personal communication. KIT Karlsruhe
10. Michaudon A (1981) Nuclear fission and neutron induced fission cross sections. Pergamon,
Oxford
11. Kessler G (2012) Sustainable and safe nuclear fission energy. Springer, Heidelberg
12. Dresner L (1960) Resonance absorption in nuclear reactors. Pergamon, New York, NY
13. Nuclear Data Files and Their References, Nuclear Data Center, Japan Atomic Energy Agency.
http://wwwndc.jaea.go.jp/nucldata/evlrefs.html
14. Oblozinsky P et al (2010) Evaluated nuclear data. In: Cacuci DG (ed) Nuclear engineering
fundamentals, vol 1, Handbook of nuclear engineering. Springer, New York, NY
15. Koning A et al (2006) The JEFF-3.1 nuclear data library. JEFF Report 21, NEA No. 6190.
OECD/NEA, Paris
16. Roussin RW et al (1994) Current status of ENDF/B-VI. In: Proceedings of international
conference nuclear data for science and technology, Gatlinburg, TN, vol 2, p 692
17. Kikuchi Y (1994) JENDL-3, revision 2: JENDL 3-2. In: Proceedings of international confer-
ence nuclear data for science and technology, Gatlinburg, TN, vol 2, p 685
18. Stacey W (2007) Nuclear reactor physics. Wiley, New York, NY
19. MacFarlane RE et al (1994) The NJOY nuclear data processing system version 91. LA-12740-
M, Los Alamos National Laboratory
20. Yang WS et al (2010) Neutronics modeling and simulation of SHARP for fast reactor analysis.
Nucl Eng Technol 42:520
21. Lee CH et al (2011) MC 2 -3: multigroup cross section generation code for fast reactor analysis.
ANL-NE-11-41, Argonne National Laboratory
22. Askew J et al (1966) A general description of the lattice code WIMS. J Br Nucl Energy Soc
5:564
23. Knott D et al (2010) Lattice physics computations. In: Cacuci DG (ed) Nuclear engineering
fundamentals, vol 1, Handbook of nuclear engineering. Springer, New York, NY
24. Yang WS (2012) Fast reactor physics and computational methods. Nucl Eng Technol
44(2):177-198
25. Lawrence RD (1983) The DIF3D nodal neutronics option for two- and three-dimensional
diffusion theory calculations in hexagonal geometry. ANL-83-1, Argonne National Laboratory
26. Bahadir T et al (2005) SIMULATE-4 multigroup nodal code with microscopic depletion
model. In: Mathematics and computation, supercomputing, reactor physics and nuclear and
biological applications, Avignon, France, 12-15 September
27. Alcouffe RE et al (1995) DANTSYS: a diffusion accelerated neutral particle transport code
system. LA-12969-M
28. Alcouffe RE et al (2000) PARTISN abstract. In: PHYSOR 2000 ANS international topical
meeting on advances in reactor physics and mathematics and computation into the next
millennium, Pittsburgh, PA, 7-11 May
29. Brown FB et al (2009) MCNP5-1.51 release notes. LA- UR-09-00384, Los Alamos National
Laboratory