Using Monte Carlo transport to accurately predict isotope production and activation analysis rates at the University of Missouri research reactor-Reference-Cited by-同舟云学术

Using Monte Carlo transport to accurately predict isotope production and activation analysis rates at the University of Missouri research reactor

Published:2009-07-16 Issue:1 Volume:282 Page:255-259
ISSN:0236-5731
Container-title:Journal of Radioanalytical and Nuclear Chemistry
language:en
Short-container-title:J Radioanal Nucl Chem

Author:

Peters N. J.,Brockman J. D.,Robertson J. D.

Publisher

Springer Science and Business Media LLC

Subject

Health, Toxicology and Mutagenesis,Public Health, Environmental and Occupational Health,Spectroscopy,Pollution,Radiology, Nuclear Medicine and imaging,Nuclear Energy and Engineering,Analytical Chemistry

Link

http://link.springer.com/content/pdf/10.1007/s10967-009-0163-y.pdf

Reference10 articles.

1. Committee on Medical Isotope Production without Highly Enriched Uranium, N.R.C., (ed) (2009) Medical isotope production without highly enriched uranium. The National Academies Press, Washington DC

2. Monte Carlo X Team (2005) MCNP—A general Monte Carlo N-particle transport code, Version 5. Department of Energy, Los Alamos National Laboratory, Los Alamos

3. Koning AF, Kellet M, Mills R, Henriksson H, Rugama Y (eds) (2006) The JEFF-3.1 nuclear data library. OECD NEA, France

4. Chadwick MB, Oblozinsky P, Herman M et al (2006) ENDF/B-VII0: next generation evaluated nuclear data library for nuclear science and technology. Nucl Data Sheets 107:2931

5. Laboratory O.R.N (2002) ORIGEN 2.2 Isotope generation and depletion code matrix exponential method. Department of Energy, RSICC, Oak Ridge

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