Author:
Brockman J.,Nigg D.W.,Hawthorne M.F.,McKibben C.
Reference9 articles.
1. Briesmeister, J.F., 1999. MCNP—a general Monte Carlo N-particle transport code, version 4C. LA-13709-M, Los Alamos National Laboratory, USA.
2. Integral reaction rate determinations–part I: tailored reactor spectrum preparation and measurement;Draper;Nucl. Sci. Eng.,1971
3. Cross sections of materials used as neutron monochromators and filters;Freund;Nucl. Instrum. Methods,1983
4. Järvinen, H., Voorbraak, W.P., 2003. Recommendations for the dosimetry of boron neutron capture therapy. Report 21425/03 55339/C, NRG Petten, The Netherlands.
5. Development and characteristics of the HANARO neutron irradiation facility for applications in the boron neutron capture therapy field;Kim;Phys. Med. Biol.,2007
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