Tungsten Carbide compact primary shielding for Small Medium Reactor

Autoridad Regulatoria Argentina, 2002, Norma AR 3.1.1: Exposición ocupacional en reactores nucleares de potencia. Revisión 2. Betzler, B.R., 2016. ORIGEN Reactor Libraries: Chapter vver440. Oak Ridge National Laboratory, April 8. Bragg-Sitton, S., 2015. Handbook of Small Modular Nuclear Reactors; Chapter 13: Hybrid energy systems (HESs) using small modular reactors (SMRs). Idaho Natonal Laboratory, Idaho Falls, ID, USA. Brookhaven National Laboratory, 2017, National Nuclear Data Center: https://www.nndc.bnl.gov/nudat2/. Bunemann, D., Enginol, T.B., 1970. Engineering Compendium on Radiation Shielding; Volume III Shield Design and Engineering; Chapter 10.11 Shielding of ship propulsion reactors. International Atomic Energy Agency. Springer-Verlag, Berlin, Heidlberg, New York. Chilton, 1984 CIRSOC, 2005. Tablas y perfiles laminados y tubos estructurales para aplicación de los reglamentos CIRSOC 301/2005 y CIRSOC 302/2005. Instituto Nacional de Tecnología Industrial, September. Czapek, 1956 Giménez, J.B.E., Chocrón, M., Conti, M.C., Labollita, S., 2016. Annual Meeting of the Argentine Association of Nuclear Technology: coupling of a seawater desalination plant with a small power nuclear reactor. December. Hamer, E.E., McArthy, A.E., 1970. Engineering Compendium on Radiation Shielding; Volume II Shielding Materials: Chapter 9.1.4 TUNGSTEN. International Atomic Energy Agency. Springer-Verlag, Berlin, Heidelberg, New York. Hungerford, H.E., Hunig, A., Devson, A.E., DuBois, F., Davis, H.S., 1970. Engineering Compendium on Radiation Shielding; Volume II Shielding Materials: Chapter 9.1.12 Concretes, Cements, Mortars and Grouts. International Atomic Energy Agency. Springer-Verlag, Berlin, Heidlberg, New York. McConn, Jr., R.J., Gesh, C.J., Pagh, R.T., Rucker, R.A., Williams, III, R.G., 2011. Radiation Portal Monitor Project, Compendium of Material Composition Data for Radiation Transport Modeling. Pacific Northwest National Laboratory, March 4, 2011. PIET-43741-TM-963 PNNL-15870 Rev.1. NIST-XCOM, 2017. https://physics.nist.gov/PhysRefData/Xcom/html/xcom1.html. Nunes R., Adams J.H., Ammons M., Avery H.S., Barnhurst R.J., Bean J.C., Beaudry B.J., Berry D.F., Black W.T., Bess M., Biermann R.J., Blackmon C.M., Blaugher R.D., Bounds C.O., Bray J.W., Brodsky M.B., Brog T.K., Capellen J., Cascone P.J., 1990. ASM Handbook Volume 2, Properties and Selection: Nonferrous Alloys and Special-Purpose Materials. ASM International, The Materials Information Company. TA459.M43. Scilab, 2017: Open source software for numerical computation; https://www.scilab.org/scilab/about. Wieselquist, W., Hart, S., Isotalo, A., Havlúj, F., Skutnik, S., Lefebvre, R., Gauld, I., Wiarda, D., Lefebvre, J., Hu, G., Sly, N., Lago, D., 2016. SCALE Code System: Chapter 5.1 Origen: Neutron Activation, Actinide Transmutation, Fission Product Generation and Radiation Source Term Calculation. ORNL/TM-2005/36 Version 6.2, April. X-5 Monte Carlo Team, MCNP-A General Monte Carlo N-Particle Transport Code, Version 5, Volume II: User’s Guide: Chapter 3 – Description of MCNP INPUT .April 24, 2003 (Revised 10/3/05). X-5 Monte Carlo Team, 2003. MCNP-A General Monte Carlo N-Particle Transport Code, Version 5, Volume I: User’s Guide: Appendix H – Fission Spectra Constants and Flux-to-Dose Factors .April 24, 2003 (Revised 10/3/05). Yamaji, A., Sako, K., 1994. J. Nucl. Sci. Technol.: Shielding Des. Obtain Compact Marine Reactor. pp. 510–520 (June).