Advance Nuclear Physics, Chandni Chowk, Global Media, p.9380168926, 2009. ,
Revised Release on Viscosity and Thermal Conductivity of Heavy Water Substance, International Association for the Properties of Water and Steam, 2007. ,
Nuclear reactor engineering, 1994. ,
MOX and UOX PWR Fuel Performances EDF Operating Experience, Journal of Nuclear Science and Technology, vol.43, issue.9, pp.960-962, 2006. ,
DOI : 10.1080/18811248.2006.9711182
Investigative studies on effect of reflector thickness on the performance of low, Nuclear Engineering and Design, vol.241, pp.2902-2915, 2011. ,
Neutron energy spectrum flux profile of Ghana???s miniature neutron source reactor core, Annals of Nuclear Energy, vol.38, issue.8, 2011. ,
DOI : 10.1016/j.anucene.2011.04.017
Determination of Neutron Fluxes and Spectrum Shaping Factors in Irradiation Sites of Ghana???S Miniature Neutron Source Reactor (mnsr) by Activation Method After Compensation of Loss of Excess Reactivty, World Journal of Nuclear Science and Technology, vol.01, issue.02, pp.50-56, 2011. ,
DOI : 10.4236/wjnst.2011.12009
Determination of thermal neutron cross-section and resonance integral for the 75As (n, ??)76As reaction by activation method using 55Mn (n, ??)56Mn as a monitor, Nuclear Engineering and Design, vol.240, issue.5, pp.980-984, 2010. ,
DOI : 10.1016/j.nucengdes.2009.12.020
Levels of Arsenic and Antimony in Water and Sediment from Prestea, A Gold Mining Town in Ghana and its Environs, Water, Air, and Soil Pollution, vol.5, issue.0, pp.10-1007, 2006. ,
DOI : 10.1007/s11270-006-9127-9
Evaluation of trace elements contents in staple foodstuffs from the gold mining areas in southwestern part of Ghana using neutron activation analysis, Journal of Radioanalytical and Nuclear Chemistry, vol.114, issue.3, pp.653-661, 2011. ,
DOI : 10.1007/s10967-011-0979-0
Biomonitoring of Occupational Exposure to Total Arsenic and Total Mercury in Urine of Goldmine Workers in Southwestern Ghana, Environmental Research, Engineering and Management, vol.56, issue.2, pp.43-48, 2011. ,
DOI : 10.5755/j01.erem.56.2.273
Fuel Reprocessing and Recycling, Nuclear Reactor Physics, p.223, 2007. ,
Plutonium Isotopics -Non-Proliferation And Safeguards Issues Australian Safeguards Office ,
The radiochemistry of americium and curium, Subcommittee on Radiochemistry, National Academy of Sciences-National Research Council : available from the Office of Technical Services, Dept. of Commerce, 1960. ,
DOI : 10.2172/4187189
The coordination chemistry of 1,2,4-triazinyl bipyridines with lanthanide(iii) elements ??? implications for the partitioning of americium(iii), Dalton Transactions, issue.9, pp.1675-1685, 2003. ,
DOI : 10.1039/b301178j
Sanex-Btp Process Development Studies, Scientific Research on the Back-end of the Fuel Cycle for the 21st Century. Commissariat à l'énergie atomique., Atalante, pp.24-26, 2000. ,
DOI : 10.1080/00223131.2002.10875470
URL : http://citeseerx.ist.psu.edu/viewdoc/summary?doi=10.1.1.216.4019
???BTBP Molecule on a Genuine Fuel Solution, Solvent Extraction and Ion Exchange, vol.13, issue.2, pp.10-97, 1080. ,
DOI : 10.1080/07366290600761936
Preparation and some properties of americium metal, Journal of Inorganic and Nuclear Chemistry, vol.29, issue.10, p.2577, 1967. ,
DOI : 10.1016/0022-1902(67)80183-0
Why Faster is Better -On Minor Actinide Transmutation in Hard Neutron Spectra, KTH School of Engineering Sciences, p.37, 2007. ,
Fast iterative methods for discrete-ordinates particle transport calculations, Progress in Nuclear Energy, vol.40, issue.1, p.3, 2002. ,
DOI : 10.1016/S0149-1970(01)00023-3
Handbook of Nuclear Engineering, LLC 233 Spring Street ,
Particle transport simulation with the Monte Carlo method, TID-26607, National Technical Information Service, 1975. ,
MCNP ? a general Monte Carlo N-particle transport code, Version 5, LA-UR-03-1987, 2003. ,
A Review of Neutron Transport Approximations, Nuclear Science and Engineering, vol.80, issue.4, p.481, 1982. ,
DOI : 10.13182/NSE80-04-481
Monte Carlo variance reduction with deterministic importance functions, Progress in Nuclear Energy, vol.42, issue.1, p.25, 2003. ,
DOI : 10.1016/S0149-1970(02)00002-1
A case study in manual and automated Monte Carlo variance reduction with a deep penetration reactor shielding problem, Nucl Sci Eng, vol.149, p.23, 2005. ,
A hybrid Monte Carlo-S2 method for preserving neutron transport effects, Proceedings of the 2009 international conference on advances in mathematics, computational methods, and reactor physics, pp.3-7, 2009. ,
Application of the " functional Monte Carlo " method to estimate continuous energy k-eigenvalues and eigenfunctions, Proceedings of the 2009 international conference on advances in mathematics, computational methods, and reactor physics, pp.3-7, 2009. ,
MCNP ? A General Monte Carlo N-Particle Transport Code, Version 5, LA-UR-03-1987, 2008. ,
ACTI An MCNP Data Library for Prompt Gamma-ray Spectroscopy, 12th Biennial Radiation Protection and Shielding Topical Meeting, 2002. ,
The LLL Evaluated Nuclear Data Library (ENDL): Evaluation Techniques, Reaction Index, and Descriptions of Individual Reactions, 1975. ,
Tables and Graphs of Photon Interaction Cross Sections from 10 eV to 100 GeV Derived from the LLNL Evaluated Photon Data Library (EPDL), Part A: Z = 1 to 50 and Part B: Z = 51 to 100, 1989. ,
ACTL: Evaluated Neutron Activation Cross?Section Library- Evaluation Techniques and Reaction Index, 1978. ,
DOI : 10.2172/6227738
New Tungsten Isotope Evaluations for Neutron Energies Between 0.1 and 20 MeV, Trans. Am. Nucl. Soc, vol.39, issue.793, 1981. ,
The NJOY Nuclear Data Processing System Version 91, Los Alamos National Laboratory, 1994. ,
DOI : 10.2172/10115999
Cycles uranium et thorium en réacteurs à neutrons rapides refroidis au sodium. Aspects neutroniques et déchets associés, Thèse de doctorat, 2010. ,
MCNP Utility for Reactor Evolution. MURE User Guide ? Version, 1.0, 2009. ,
Contributions à l'étude de la production d'233U en combustible MOX-ThPu en réacteur à eau sous pression.Scénarios de transition vers des concepts isogénérateurs Th/233U en spectre thermique, Thèse de doctorat, 2006. ,
MURE,MCNP Utility for Reactor Evolution, User Guide -Version 1.0, pp.73-74, 2009. ,
User's Manual, version 2.0 for MONTEBURNS, version 5B, Los Alamos National Laboratory report LA-UR-99-4999, 1999. ,
The MOCUP Interface: A Coupled Monte Carlo/Depletion System, Topical Meeting on Advances in Reactor Physics, 1994. ,
MCB: A continuous energy Monte Carlo Burnup simulation code, Actinides and Fission Product Partitioning and Transmutation, EUR 18898 EN, OECD/NEA, p.523, 1999. ,
An optimum Approach to Monte Carlo Burn-Up, Nucl. Sci. Eng, vol.156, pp.180-196, 2007. ,
Couplage 3D neutronique thermohydraulique. Développement d'outils pour les études de sûreté des réacteurs innovants, Thèse de doctorat en science, 2009. ,
URL : https://hal.archives-ouvertes.fr/tel-00474353
Coupled Monte Carlo transport with fuel burnup calculation," in MCNP Utility for Reactor Evolution, p.1845, 2009. ,
Nuclear Fuel Management, IEEE Transactions on Nuclear Science, vol.29, issue.3, p.269143, 1979. ,
DOI : 10.1109/TNS.1982.4336348
A piecewise linear reactivity fuel-cycle model, Annals of Nuclear Energy, vol.16, issue.8, pp.417-422, 1989. ,
DOI : 10.1016/0306-4549(89)90104-7
Quadratic reactivity fuel-cycle model stability, Annals of Nuclear Energy, vol.14, issue.3, pp.145-151, 1987. ,
DOI : 10.1016/0306-4549(87)90088-0
Nuclear Principles in Engineering, pp.47907-1290, 2009. ,
DOI : 10.1007/978-0-387-85608-7
Nuclear Fuel Cycle and Materials Section, Division of Nuclear Fuel Cycle and Waste Technology, 2005. ,
Fuel burnup calculation for HEU and LEU cores of Ghana MNSR, Annals of Nuclear Energy, vol.44, pp.65-70, 2012. ,
DOI : 10.1016/j.anucene.2011.12.027
Nuclear Reactor Materials and Fuels, p.785, 1992. ,
Nuclear wallet cards, National Nuclear Data Center, 2005. ,
Isotopic Composition and Decay Heat Calculations of Spent Nuclear Fuel from Kr?ko NPP, Nuclear Energy for New Europe, 2008. ,
Reactor Theory (Nuclear Parameters), pp.1019-1021, 1993. ,
Calculation and Experiment of Adding Top Beryllium Shims for Iran MNSR, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 2006. ,
DOI : 10.1115/ICONE14-89030
Monte Carlo Cross Section TestinP for Thermal and Intermediate 235U, 1997. ,
Reactor Physics, pp.120-173 ,