Open Access
Issue
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
Article Number 02010
Number of page(s) 9
Section Reactor Surveillance and Plant Life
DOI https://doi.org/10.1051/epjconf/201610602010
Published online 03 February 2016
  1. G. Hordósy, Gy Hegyi, A. Keresztúri, Cs. Maráczy, E. Temesvári, P. Vértes, É. Zsolnay: Pressure vessel calculations for VVER-440 reactors. Radiation Protection Dosimetry, 115, Page 100–103, 2005 [CrossRef]
  2. A. Keresztúri, Gy. Hegyi, L. Korpás, Cs. Maráczy, M. Makai, M. Telbisz: General features and validation of the recent KARATE-440 code system. Int. J. of Nuclear Energy Science and Technology, Vol.5, No. 3, pp. 207–238. 2010 [CrossRef]
  3. E. M. Zsolnay, Sz. Czifrus, S. Fehér and F. Oszvald: Method for decreasing the uncertainty in reactor dosimetry results due to the undefined positioning of the surveillance capsules at the VVER-440 NPP reactors. Paper presented at the 12th ISRD, Gatlinburg, USA, 2005 (Paper not published)
  4. E. M. Zsolnay, S. Feher, Sz. Czifrus, G. Hordosy: Retrospective dosimetry on the Paks RPVs. Report in Hungarian. BME-NTI-261/2002. Budapest, January 2002
  5. E. M. Zsolnay, S. Feher, Sz. Czifrus: The uncertainty of the service life assessment of the reactor pressure vessel. Report in Hungarian. BME-NTI-273/2003-2004, Budapest, May 2004
  6. E. M. Zsolnay, S. Feher, Sz. Czifrus: Improving the accuracy of the results of the reactor dosimetry investigations on the exposure of the RPVs of the Paks NPP (I.). Report in Hungarian. BME-NTI-264/2002. Budapest, December 2002
  7. E. M. Zsolnay, Sz. Czifrus, S. Feher: Improving the accuracy of the results of the reactor dosimetry investigations on the exposure of the RPVs of the Paks NPP (II.). Report in Hungarian. BME-NTI-287/2004–2005. Budapest, February 2005
  8. E. M. Zsolnay, E. J. Szondi: Recommendation on the reactor dosimetry investigations to be performed in frame of the new RPV surveillance programme. Report in Hungarian. BME-NTI-201/1991. Budapest, November 1991
  9. G. Hordósy, A. Keresztúri, Cs. Maráczi, E. Temesvári, Gy. Hegyi, É. M. Zsolnay: Pressutre vessel fluence calculations for the power uprate and the lifetime extension. Paper to be presented at the 15Th ISRD, Aix en Provance, 18–23 May 2014
  10. E. M. Zsolnay, Sz. Czifrus: Evaluation of the responses of the neutron monitors irradiated during the cycles 12–16 (1994–1999) of the unit 1 of the Paks nuclear power plant, and determination of the fast neutron exposure of the specimens to the service life extension of the NPP. Report in Hungarian. BME-NTI-311/2005. Budapest, December 2005
  11. E. M. Zsolnay, Sz. Czifrus, D. Bódizs: Evaluation of the responses of neutron monitors (Paks NPP reactor unit 2, cycles 12–16, 1995–2000) to the service life extension of the nuclear power plant, and solution of other kinds of problems for the NPP. Report in Hungarian: BME-NTI-365/2006. Budapest, November 2006
  12. E. M. Zsolnay, Sz. Czifrus: Development of the investigation method and evaluation of the response of the RPV surveillance neutron monitors for the service life extension of the NPP (Paks NPP, reactor unit 3, cycles 11.-15., 1966–2001). Report in Hungarian BME-NTI-409/2007. Budapest, December 2007
  13. MCNP - A General Monte Carlo N-Particle Transport Code, Version 5, Volume I: Overview and Theory, LA-UR-03-1987, Volume II: User's Guide, LA-CP-03-0245, Volume III. Developer's Guide, LA-CP-03-0284
  14. B. Boehmer, Ballesteros, J. Konheiser, B. Ošmera, J. Kyncl, G. Hordósy, A., Keresztúri, S. Belousov, K. Ilieva, D. Kirilova, M. Mitev, V. Smutný, E. Polke, S. Zaritsky, C. Töre, P. Ortego: Deep Penetration Benchmarking Conclusions And Recommendations. Redos/R(07)/ 2004 /issue 1
  15. Gábor Hordósy, György Hegyi: Reactor Physical Calculations for the Study of the Pressure Vessel Radiation Damage of the Paks Nuclear Power Plant. Report in Hungarian. AEKI-RAL-2004/752/02/M2, Budapest 2008 (in Hungarian)
  16. G. Hordósy, Gy. Hegyi, Cs. Maráczy: Repetition of the KARATE-MCNP neutron fluence calculation for the fuel with Gadolinium. Report in Hungarian. AEKI-RAL-2009/ 745/04/M1
  17. E. M. Zsolnay, Sz. Czifrus, S. Fehér: Development of the method for evaluation of the responses of neutron monitors irradiated for 16 years in the reactor unit 1, and irradiated in the cavity of the reactor unit 3, during the reactor cycle between 2007–2008 (cycle 23). Report in Hungarian. BME-NTI-505/2009. Budapest, March 2010
  18. E. M. Zsolnay, Sz. Czifrus, D. Kis: Development of method for evaluation of the responses of neutron monitors irradiated in the cavity of the reactor unit 3 of the Paks NPP, at 104% and 108% reactor powers, and based on it, determination of the exposition data. Report in Hngarian. BME-NTI-534/2011. Budapest, June 2011
  19. E. M. Zsolnay, Sz. Czifrus, D. Kis: Evaluation of the responses of neutron monitors irradiated in the cavity of the reactor unit 2 of the Paks NPP, during the reactor cycle 28. Report in Hungarian. BME-NTI-643/2014. Budapest, April 2014
  20. P. Trampus, G. Bóna, J. Elter, T. Fekete, A. Keresztúri, S. Rátkai: Pressurized Thermal Shock Analysis, Paks NPP Units 1-4. Summary Report. EJR No: 000000A00212 OKA, Paks, 2010

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