Nuclear Engineering and Technology

  • 제44권8호
  • /
  • Pages.855-870
  • /
  • 2012
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

PERSPECTIVES IN SYSTEM THERMAL-HYDRAULICS

  • D'auria, F. (GRNSPG - University of Pisa)
  • 투고 : 2012.11.20
  • 발행 : 2012.12.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

The paper deals with three main topics: a) the definition of System Thermal-Hydraulics (SYS TH), b) a historical outline for SYS TH and, c) the description of elements for reflection when planning research projects or improvement activities, this last topic being the main reason for the paper. Distinctions between basic thermal-hydraulics and computational Fluid-Dynamics (CFD) on the one side and SYS TH on the other side are considered under the first topic; stakeholders in the technology are identified. The proposal of Interim Acceptance Criteria for Emergency Core Cooling Systems in 1971 by US NRC (AEC at the time) is recognized as the starting date or the triggering event for SYS TH (second topic). The complex codes and the main experimental programs (list provided in the paper) constitute the pillars for SYS TH. Caution or warning statements are introduced in advance when discussing the third topic: a single person (or a researcher) has little to no possibility, or capability, of streamlining the forthcoming investments or to propose a roadmap for future activities. Nevertheless, the ambitious attempt to foresee developments in this area has been pursued without constraints connected with the availability of funds and with industrial benefits or interests. Demonstrating the acceptability of current SYS TH limitations and training in the application of those codes are mentioned as the main challenges for forthcoming research activities.

키워드

참고문헌

  1. USNRC, Code of Federal Regulation, Washington (US) [continuously updated - see the website of US NRC].
  2. IAEA, Accident Analysis for Nuclear Power Plants, IAEA Safety Reports Series No 23, ISSN 1020-6450; ISBN 92-0-115602-2, Vienna (A), 2002.
  3. D'Auria F., Galassi G.M., Scaling in nuclear reactor system thermal-hydraulics, J. Nucl. Eng. Des. 240 (10), 3267-3293, 2010. https://doi.org/10.1016/j.nucengdes.2010.06.010
  4. OECD/NEA/CSNI, CSNI Code Validation Matrix of Thermo-Hydraulic Codes for LWR LOCA and Transients, CSNI, 132, Paris, France, 1987
  5. OECD/NEA/CSNI, CSNI Code Validation Matrix of Thermo-Hydraulic Codes for LWR LOCA and Transients. CSNI Report, 132-rev.1, Paris, France, 1996
  6. OECD/NEA/CSNI, Separate Effects Test Matrix for Thermal-Hydraulic Code Validation: Phenomena Characterization and Selection of Facilities and Tests, OCDE/GD (94)82, Paris, France, 1993.
  7. US AEC, Interim Acceptance Criteria (IAC) for ECCS, USAEC, Washington (DC), USA, 1971.
  8. USNRC, WASH-1400, NUREG-75/014, Washington (DC), USA, 1975.
  9. D'Auria F., Galassi G.M., Code validation and uncertainties in system thermal-hydraulics, J. Progress in Nuclear Energy, 33(1/2), 175-216, 1998. https://doi.org/10.1016/S0149-1970(97)00097-8
  10. Aksan S.N., D'Auria F., Staedtke H., User effects on the thermal-hydraulic transient system codes calculations, J. Nuclear Engineering and Design 145 (1 and 2), 1993.
  11. Ashley R., El-Shanawany M., Eltawila F., D'Auria F, Good Practices for User Effect Reduction, OECD/CSNI Report NEA/CSNI/R(98)22,Paris(F) 1998.
  12. D'Auria F., Proposal for training of thermal-hydraulic system codes users, IAEA Spec. Meet. On User Qualification and User Effects on Accident Analysis for Nuclear Power Plants, Vienna (A), 1998.
  13. Bonuccelli M., D'Auria F., Debrecin N., Galassi G.M., A methodology for the qualification of thermal-hydraulic codes nodalizations, International Top. Meet. On Nuclear Reactor Thermal-Hydraulics (NURETH-6), Grenoble, France, 1993.
  14. Damerell P.S., Simons J.W., 2D/3D Program Work Summary Report, GRS Report No 100, ISBN 3-923875-50-9, Koln (G), 1992.
  15. USNRC, Quantifying Reactor Safety Margins: Application of CSAU to a LBLOCA NUREG/CR-5249, USNRC, Washington, DC, USA, 1989.
  16. Hofer E., The GRS programme package for uncertainty and sensitivity analysis. In: Seminar on Methods and Codes for Assessing the Off-site Consequences of Nuclear Accidents, EUR 13013, CEC, Bruxelles (Belgium), 1990.
  17. D'Auria F., Debrecin N., Galassi G.M., Outline of the uncertainty methodology based on accuracy extrapolation (UMAE), J. Nucl. Technol. 109 (1), 21-38, 1995. https://doi.org/10.13182/NT109-21
  18. OECD/NEA CSNI [Authors: Wickett, T. (Ed.), D'Auria, F., Glaeser, H., Chojnacki, E., Lage, C. (Lead Authors), Sweet, D., Neil, A., Galassi, G.M., Belsito, S., Ingegneri, M., Gatta, P., Skorek, T., Hofer, E., Kloos, M., Ounsy, M., Sanchez, J.I.]. Report of the Uncertainty Methods Study for advanced best estimate thermal-hydraulic code applications - Vols. I & II. OECD/CSNI Report NEA/CSNI/R(97)35, Paris (F), June 1998.
  19. USNRC, Best-Estimate Calculations of Emergency Core Cooling System Performance, USNRC Regulatory Guide 1.157, 1989.
  20. D'Auria F., Giannotti W., Development of code with capability of internal assessment of uncertainty. Nuclear Technology 131(1), 159-196, 2000. https://doi.org/10.13182/NT00-5
  21. Yadigaroglu G., Andreani M., Dreier J., Coddington P., Trends and needs in experimentation and numerical simulation for LWR safety, J. Nucl. Eng. Des. 221, 205-223, 2003 https://doi.org/10.1016/S0029-5493(02)00339-4
  22. OECD/NEA, Neutronics/Thermal-hydraulics Coupling in LWR Technology - Three vols. OECD/NEA Report No 4452, ISBN 92-64-02083-7, Paris (F), 2004, (Vol. I, 103 pages)
  23. Petruzzi A., D'Auria F., Bajs T., Reventos F., International Training Program: 3D S.UN.COP-Scaling. Uncertainty and 3D thermal-hydraulics/neutron-kinetics CouPled Codes Seminar. ENC, Versailles, France, 2005.
  24. KWU-Siemens, FSAR: Final Safety Analysis Report Central Nuclear Almirante Alvaro Alberto, Unit 2 - Rev. 0 , Sept. 1997
  25. US NRC, Transient and Accident Analysis Methods. RG 1.203, USNRC, Washington, USA, 2005.
  26. IAEA, Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation, IAEA Safety Report Series, No 52, Vienna (A), 2008
  27. IAEA, Deterministic Safety Analysis for Nuclear Power Plants, IAEA SSG-2, Vienna, Austria, 2010.
  28. ANS, Int. Meet. on Best-Estimate Methods in Nuclear Installation Safety Analysis (BE-2000), Washington, DC (US), 10-13 Nov. 2000.
  29. ANS, Int. Meet. on Best-Estimate Methods in Nuclear Installation Safety Analysis (BE-2004) Washington, DC (US), 14-18 Nov. 2004.
  30. Abdul-Razzak A., Guidelines for application of the Best Estimate Analysis and Uncertainty (BEAU) methodology to licensing analysis in the Canadian CANDU Nuclear Power Industry, IAEA TM, "Application of Deterministic Safety Analysis, Pisa (I), 21-29 Sept. 2009.
  31. Glaeser H., GRS method for uncertainty and sensitivity evaluation of code results and applications .Journal of Science and Technology of Nuclear Installations, 2008
  32. UNIPI-GRNSPG, A Proposal for Performing the Atucha II Accident Analyses for Licensing Purposes - The BEPU Report - Rev. 3 , Pisa (I) 2008 [endorsed by Regulatory Authority in Argentina].
  33. Zuber N., Scaling: from Quanta to Nuclear Reactors, J. Nucl. Eng. Des. 240, 1986-1996, 2010. https://doi.org/10.1016/j.nucengdes.2010.01.021
  34. Jafari J., D'Auria F., Kazeminejad H., Davilu H., Reliability evaluation of a natural circulation system. J. Nuclear Engineering and Design 224,79-104, 2003. https://doi.org/10.1016/S0029-5493(03)00105-5
  35. Petruzzi A., Fiori F., Kovtonyuk A., D'Auria F., Supporting qualified database for uncertainty evaluation, Proceeding of ICAPP 2012, Chicago, June 24-28, 2012, paper No 12085.
  36. D'Auria F., Chojnacki E., Glaeser H., Lage C., Wickett T., Overview of Uncertainty Issues and Methodologies, Invited at OECD/CSNI Seminar on Best Estimate Methods in Thermal-Hydraulic Analyses - Ankara (Tr) June 29 -July 1, 1998.
  37. D'Auria F., Camargo C., Muellner N., Lanfredini M., Mazzantini O., The simulation of I & C in accident analyses of nuclear power plants, J. Nuclear Engineering and Design 250, 656-663, 2012. https://doi.org/10.1016/j.nucengdes.2012.04.022