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2014 | 59 | 2 | 67-72
Tytuł artykułu

Estimation of Control Rod Worth in a VVER-1000 Reactor using DRAGON4 and DONJON4

Treść / Zawartość
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors. In this paper, we developed a justifiable approach called D4D4 to estimate the control rod worth of a VVER-1000 reactor that enables to perform the best estimate analysis and reduce the conservatism that utilize DRAGON4 and DONJON4. The results are compared with WIMS-D4/CITATION to show the effectiveness and superiority of the developed package in predicting reactivity worth of the rod and also other reactor physics parameters of the VVER-1000 reactor. The results of this study are in good agreement with the plant's FSAR.
Słowa kluczowe
Wydawca

Czasopismo
Rocznik
Tom
59
Numer
2
Strony
67-72
Opis fizyczny
Daty
otrzymano
2013-10-30
zaakceptowano
2014-04-17
online
2014-07-08
Twórcy
  • Engineering Department, Shahid Beheshti University, P. O. Box: 1983963113, Tehran, Iran, Tel.: +98 21 2243 1596, Fax: +98 21 2990 2546
  • Engineering Department, Shahid Beheshti University, P. O. Box: 1983963113, Tehran, Iran, Tel.: +98 21 2243 1596, Fax: +98 21 2990 2546, o_safarzadeh@sbu.ac.ir
  • Engineering Department, Shahid Beheshti University, P. O. Box: 1983963113, Tehran, Iran, Tel.: +98 21 2243 1596, Fax: +98 21 2990 2546
Bibliografia
  • 1. Lee, E. K., Shin, H. C., Bae, S. M., & Lee, Y. K. (2005). New dynamic method to measure rod worths in zero power physics test at PWR startup. Ann. Nucl. Energy, 32, 1457-1475.
  • 2. Shimazu, Y., Okazaki, K., & Tsuji, M. (2006). Feasibility study for evaluation of control rod worth in pressurized water reactors using neutron count rate during a control rod drop testing. Nucl. Sci. Technol., 43, 919-923.
  • 3. Kalcheva, S., & Koonen, E. (2009). Improved Monte Carlo-Perturbation method for estimation of control rod worths in a research reactor. Ann. Nucl. Energy, 36, 344-349.[WoS]
  • 4. Varvayanni, M., Savva, P., & Catsaros, N. (2009). Control rod worth calculations using deterministic and stochastic methods. Ann. Nucl. Energy, 36, 1718-1725.[WoS]
  • 5. Petit, O., Hugot, F. -X., Lee, Y. -K., Jouanne, C., & Maz-zolo, A. (2008). TRIPOLI-4 Version 4 User Guide. (CEA–R-6169). Code Available from OECD/NEA Data Bank.
  • 6. Greene, N. M., Petrie, L. M., & Westfall, R. M. (2000). NITAWL-II: scale system module for performing resonance shielding and working library production. (NUREG/CR-0200). Revision 6, V. 2, Section F2. (ORNL/NUREG/ CSD-2/V2/R6).
  • 7. Greene, N. M., & Petrie, L. M. (2000). XSDRNPM: a one-dimensional discrete-ordinates code for transport analysis. Oak Ridge National Laboratory. (NUREG/ CR-0200). Revision 6, V. 2, Section F3. (ORNL/NUREG/ CSD-2/V2/R6).
  • 8. Fowler, T. B., Vondy, D. R., & Guningham, G. W. (1971). Nuclear reactor core analysis code: CITATION. Oak Ridge National Laboratory. (ORNL-TM-2496). Rev. 2.
  • 9. Savva, P., Varvayanni, M., & Catsaros, N. (2011). Dependence of control rod worth on fuel burnup. Nucl. Eng. Des., 241, 492-497.[WoS]
  • 10. Fadaei, A. H., & Setayeshi, S. (2009). Control rod worth calculation for VVER-1000 nuclear reactor using WIMS and CITATION codes. Prog. Nucl. Energy, 51, 184-191.
  • 11. Winfrith. (1982). LWR-WIMS, a computer code for light water reactor calculations. AEE, UK. AEEW-R 1498.
  • 12. D'Auria, F., Fischer, K., Mavko, B., & Sartmandjiev, A. (2001). Validation of accident and safety analysis methodology. Vienna: IAEA. (CRP/J.020.03).
  • 13. Internationa Atomic Energy Agency. (2008). Best estimate safety analysis for nuclear power plants: uncertainty evaluation. Vienna: IAEA. (Safety Series Report No. 52).
  • 14. Marleau, G., Hébert, A., & Roy, R. (2011). A user guide for DRAGON Version 4. Institut de génie nucléaire, Dé-partement de génie mécanique, École Polytechnique de Montréal. (Report IGE-294).
  • 15. Popov, A. V., & Olekhnovitch, A. (2012). Adapting the feed-back model to dynamic core heterogeneity. Ann. Nucl. Energy, 48, 134-137.[WoS]
  • 16. Popov, A. V., Olekhnovitch, A., & Fassi Fehri, M. (2012). LBLOCA in CANDU-NG cooled by light water. Ann. Nucl. Energy, 45, 161-165.[WoS]
  • 17. Sekki, D., Hébert, A., & Chambon, R. (2011). A user guide for DONJON Version 4. Institut de génie nucléaire, Département de génie mécanique, École Polytechnique de Montréal. (Report IGE-300).
  • 18. AEOI. (2006). Album of neutron and physical characteristics of the initial fuel inventory. Refers to Organization of operation on BNPP-1.
  • 19. AEOI. (2007). Final safety analysis report, Chapter 4, REACTOR. Atomic Energy Organization of Iran.
Typ dokumentu
Bibliografia
Identyfikatory
Identyfikator YADDA
bwmeta1.element.-psjd-doi-10_2478_nuka-2014-0006
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