Open Access
Issue
EPJ Nuclear Sci. Technol.
Volume 2, 2016
Article Number 14
Number of page(s) 9
DOI https://doi.org/10.1051/epjn/2016012
Published online 25 March 2016
  1. F. Franceschini, E.J. Lahoda, Advanced fuel developments to improve fuel cycle cost in PWR, in GLOBAL 2011 , Makuhari, Japan, Dec. 11–16, 2011 (2011)
  2. K.E. Metzger, T.W. Knight, R.L. Williamson, Model of USi fuel system using bison fuel code, 3 2in ICAPP 2014 , Charlotte, NC, USA, Apr. 6–9, 2014 (2014)
  3. H. Kim, I. Kim, Y. Koo, J. Park, Application of coating technology on zirconium-based alloy to decrease high-temperature oxidation, in 17th International Symposium on Zirconium in the Nuclear Industry , Andhra Pradesh, India (2013)
  4. A. Abe, C. Giovedi, D.S. Gomes, A.T. Silva, Revisiting stainless steel as PWR fuel rod cladding after Fukushima Daiichi accident, J. Energy Power Eng. 8 , 973 (2014)
  5. E.J. Lahoda, F. Franceschini, Advanced fuel concepts RT-TR-11-12 (Westinghouse Electric Company LLC, 2011)
  6. Westinghouse Electric Company LLC, Enhancing safety: the pursuit of accident tolerant fuel, [Online], Available: http://www.westinghousenuclear.com/About/News/Features/View/ArticleId/481/Enhancing-Safety-The-Pursuit-of-Accident-tolerant-Fuel [Accessed 20.2.2015]
  7. T. Newton et al., Developments within WIMS10, in PHYSOR 2008 , Interlaken, Switzerland, Sept. 14–19, 2008 (2008)
  8. E.A. Morrison, PANTHER User Guide E/REP/BBDB/0015/GEN/03 ED/PANTHER/UG/5.5, British Energy, 2003
  9. B. Petrovic, Integral inherently safe light water reactors (IS-LWR) concept: extending SMR safety features to large power output, 2in ICAPP 2014 , Charlotte, NC, USA, Apr. 6–9, 2014 (2014)
  10. J. Leppänen, M. Pusa, T. Viitanen, V. Valtavirta, T. Kaltiaisenaho, The Serpent Monte Carlo code: status, development and applications in 2013, Ann. Nucl. Energy 82 , 142 (2015) [CrossRef]
  11. D. Salazar, F. Franceschini, IS-LWR equilibrium cycle core analysis, 2in PHYSOR 2014 , Kyoto, Japan, Sept. 29–Oct. 3, 2014 (2014)
  12. Department of Energy & Climate Change, Nuclear R&D - Accident Tolerant Fuel: Grant Notification, 2014
  13. Department of Energy and Climate Change, DECC Science Advisory Group: Horizon Scanning, October 2013
  14. Nuclear Innovation and Research Advisory Board, NIRAB Annual Report, 2014
  15. J.L. Hutton et al., Comparison of WIMS/PANTHER calculations with measurement on a range of operating PWR, in PHYSOR 2000 , Pittsburgh, USA, May 2000 (2000)
  16. S. Alam, B.A. Lindley, G.T. Parks, Feasibility study of the design of homogeneously mixed thorium-uranium, in ICAPP 2015 , Nice, France, May 3–6, 2015 (2015)
  17. C. Harrington, Reactor Physics Modelling of the Shippingport Light Water Reactor, MPhil Dissertation, University of Cambridge, 2012
  18. S.F. Ashley et al., Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems, Ann. Nucl. Energy 69 , 314 (2014) [CrossRef]
  19. T. Fei, E.A. Hoffman, T.K. Kim, T.A. Taiwo, Performance evaluation of two-stage fuel cycle from SFR to PWR, in GLOBAL 2013 , Salt Lake City, UT, USA (2013)
  20. F. Heidet, T.K. Kim, T.A. Taiwo, Two-stage fuel cycles with accelerator-driven systems, in PHYSOR 2014 , Kyoto, Japan, Sept. 28–Oct. 3, 2014 (2014)
  21. L.L. Snead et al., Handbook of SiC properties for fuel performance modelling, J. Nucl. Mater. 371 , 329 (2007) [CrossRef]
  22. Z. Xu, Design strategies for optimizing high burnup fuel in pressurized water reactors, PhD Thesis, Massachusetts Institute of Technology, 2003
  23. G.T. Parks, Pressurised water reactor fuel management using PANTHER, Nucl. Sci. Eng. 124 , 178 (1996)
  24. G.T. Parks, M.P. Knight, Loading pattern optimization in hexagonal geometry using PANTHER, in PHYSOR 96 , Mito, Japan, Sept. 16–20, 1996 (1996)
  25. N.Z. Zainuddin, B.A. Lindley, G.T. Parks, Towards optimal in-core fuel management of thorium-plutonium-fuelled PWR cores, in ICONE 21, 21st International Conference on Nuclear Energy , Chengdu, China, July 29–Aug. 3, 2013 (2013)
  26. B.A. Lindley, A. Ahmad, N.Z. Zainuddin, F. Franceschini, G.T. Parks, Steady-state and transient core feasibility analysis for a thorium-fuelled reduced-moderation PWR performing full transuranic recycle, Ann. Nucl. Energy 72 , 320 (2014) [CrossRef]
  27. M. Ouisloumen et al., PARAGON: The New Westinghouse Assembly Lattice Code, in ANS Int. Mtg. on Mathematical Methods for Nuclear Applications , Salt Lake City, UT, USA (2001)
  28. L. Mayhue et al., Qualification of NEXUS/ANC nuclear design system for PWR analyses, in PHYSOR 2008 , Interlaken, Switzerland, Sept. 16–19, 2008 (2008)

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.