References
- Reactor USNRC, Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, Bulletin 2002-01, OMB Control No.: 3150-0012, U.S. Nuclear Regulatory Commission, Washington, DC, 2002.
- H. Nakamura, T. Watanabe, T. Takeda, Y. Maruyama, M. Suzuki, Overview of recent efforts through ROSA/LSTF experiments, Nucl. Eng. Technol. 41 (2009) 753-764. https://doi.org/10.5516/NET.2009.41.6.753
- The ROSA-V Group, -V. ROSA, Large Scale Test Facility (LSTF) System Description for the Third and Fourth Simulated Fuel Assemblies, JAERI-tech 2003-037, Japan Atomic Energy Research Institute, Ibaraki, Japan, 2003.
- Y. Kukita, K. Tasaka, H. Asaka, T. Yonomoto, H. Nakamura, The effects of break locaion on PWR small break LOCA: experimental study at the ROSA-IV LSTF, Nucl. Eng. Des. 122 (1990) 255-262. https://doi.org/10.1016/0029-5493(90)90210-O
- J. Freixa, A. Manera, Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE, Nucl. Eng. Des. 240 (2010) 1779-1788. https://doi.org/10.1016/j.nucengdes.2010.02.007
- C. Queral, J. Gonzalez-cadelo, G. Jimenez, E. Villalba, Accident management actions in an upper-head small-break loss-of-coolant accident with highpressure safety injection failed, Nucl. Technol. 175 (2011) 572-593. https://doi.org/10.13182/NT11-A12507
- USNRC Nuclear Safety Analysis Division, RELAP5/MOD3.3 Code Manual, NUREG/CR-5535/Rev 1, Information Systems Laboratories, Inc., 2001.
- G.E. Wilson, B.E. Boyack, The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis, Nucl. Eng. Des. 186 (1998) 23-37. https://doi.org/10.1016/S0029-5493(98)00216-7
- N. Zuber, Problems in Modeling Small Break LOCA, USNRC Report NUREG-0724, U.S. Nuclear Regulatory Commission, Washington, DC, 1980.
- H. Kumamaru, K. Tasaka, in: Recalculation of Simulated Post-scram Core Power Decay Curve for Use in ROSA-IV/LSTF Experiments on PWR Small-break LOCAs and Transients, JAERI-M 90-142, Japan Atomic Energy Research Institute, Ibaraki, Japan, 1990.
- V.H. Ransom, J.A. Trapp, The RELAP5 choked flow model and application to a large scale flow test, in: Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Saratoga Springs, New York, USA, 1980.
- H. Asaka, Y. Kukita, T. Yonomoto, Y. Koizumi, K. Tasaka, Results of 0.5% coldleg small-break LOCA experiments at ROSA-IV/LSTF: effect of break orientation, Exp. Therm. Fluid Sci. 3 (1990) 588-596. https://doi.org/10.1016/0894-1777(90)90075-I
- H.K. Fauske, The discharge of saturated water through tubes, AlChE Symp. Ser. 61 (1965) 210-216.
- K.H. Ardron, R.A. Furness, A study of the critical flow models used in reactor blowdown analysis, Nucl. Eng. Des. 39 (1976) 257-266. https://doi.org/10.1016/0029-5493(76)90074-1
- D.W. Sallet, Thermal hydraulics of valves for nuclear applications, Nucl. Sci. Eng. 88 (1984) 220-244. https://doi.org/10.13182/NSE84-A18579
- B.E. Boyack, L.W. Ward, Validation test matrix for the consolidated TRAC (TRAC-M) code, in: Proceedings of International Meeting on Best Estimate Methods in Nuclear Installation Safety Analysis (BE '00), Los Alamos National Laboratory, NM, USA, Washington, DC, 2000.
- M.J. Griffiths, J.P. Schlegel, T. Hibiki, M. Ishii, I. Kinoshita, Y. Yoshida, Phenomena identification and ranking table for thermal-hydraulic phenomena during a small-break LOCA with loss of high pressure injection, Prog. Nucl. Energy 73 (2014) 51-63. https://doi.org/10.1016/j.pnucene.2014.01.008
- M. Ishii, K. Mishima, Study of Two-fluid Model and Interfacial Area, NUREG/CR-1873, Argonne National Laboratory, Lemont, IL, 1980.
- H. Kumamaru, Y. Kukita, H. Asaka, M. Wang, E. Ohtani, RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following SBLOCAs with totally failed HPI, Nucl. Technol. 126 (1999) 331-339. https://doi.org/10.13182/NT99-A2978
- L.A. Bromley, Heat transfer in stable film boiling, Chem. Eng. Prog. 46 (1950) 221-227.
- K.H. Sun, J.M. Gonzalez-santalo, C.L. Tien, Calculations of combined radiation and convection heat transfer in rod bundles under emergency cooling conditions, J. Heat Tran. 98 (1976) 414-420. https://doi.org/10.1115/1.3450569
- F.W. Dittus, L.M.K. Boelter, Heat transfer in automobile radiators of the tubular type, Int. Commun. Heat Mass Tran. 12 (1985) 3-22. https://doi.org/10.1016/0735-1933(85)90003-X
- J.R. Sellars, M. Tribus, J.S. Klein, Heat transfer to laminar flows in a round tube or flat conduit: the Graetz problem extended, Transactions of the ASME 78 (1956) 441-448.
- S.W. Churchill, H.H.S. Chu, Correlating equations for laminar and turbulent free convection from a vertical plate, Int. J. Heat Mass Tran. 18 (1975) 1323-1329. https://doi.org/10.1016/0017-9310(75)90243-4
- A. Guba, M. Makai, L. Pal, Statistical aspects of best estimate methodeI, Reliab. Eng. Syst. Saf. 80 (2003) 217-232. https://doi.org/10.1016/S0951-8320(03)00022-X
- A. de Crecy, P. Bazin, H. Glaeser, et al., Uncertainty and sensitivity analysis of the LOFT L2-5 test: results of the BEMUSE programme, Nucl. Eng. Des. 238 (2008) 3561-3578. https://doi.org/10.1016/j.nucengdes.2008.06.004
- W.W. Daniel, Spearman rank correlation coefficient, in: Applied Nonparametric Statistics, second ed., PWS-Kent Publishing, Boston, MA, 1990.
- J. Freixa, T.W. Kim, A. Manera, Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation, Nucl. Eng. Des. 264 (2013) 153-160. https://doi.org/10.1016/j.nucengdes.2013.02.023