Sensitivity analysis of the Peach Bottom turbine trip 2 experiment

Kerntechnik

Volumn 69, Issue 1-2, 2004, Pages 7-14

  Bousbia Salah, Anis ^a   D'Auria, Francesco ^a   Bambara, Marco ^a  

^a UNIVERSITY OF PISA   (Italy)

Author keywords

[No Author keywords available]

Indexed keywords

CALCULATIONS; COMPUTER SIMULATION; HYDRAULIC TURBINES; MATHEMATICAL MODELS; NEUTRONS; REACTOR CORES; SENSITIVITY ANALYSIS; THERMODYNAMICS; THREE DIMENSIONAL;

DELAYED FEEDBACK MECHANISM; PEACH BOTTOM TURBINE; RAPID PRESSURE INDUCED POSITIVE REACTIVITY MECHANISM; THERMAL HYDRAULICS; THREE DIMENSIONAL NEUTRON MODELLING;

BOILING WATER REACTORS;

EID: 1842611120     PISSN: 09323902     EISSN: None     Source Type: Journal    
DOI: 10.3139/124.100182     Document Type: Article

References (12)

1. Solis, J.; Ivanov, K.; Sarikaya, B.; Olson, A.; Hunt, K. W.: Boiling Water Reactor Turbine Trip (TT) Benchmark. Volume 1: Final specifications. NEA/NSC/DOC, 2001
2. Ransom, V. H.; Wagner, R. J.; Trapp, J. A.; Johnsen, G. W.; Miller, C. S.; Kiser, D. M.; Riemke, R. A.: RELAP5/MOD3, Code Manual: User guide and Input Requirements. NUREG/CR-4312 EGG-2396, Idaho (US), 1990
3. Joo, H. G.; Barber, D.; Jiang, G.; Downar, T. J.: PARCS, A Multi-Dimensional Two Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal Method. PU/NE-98-26, Sept. 1998
4. Carmichael, L. A.; Niemi, R. O.: Transient and Stability Test at Peach Bottom Atomic Powr Station Unit2 at end of cycle 2. EPRI NP-564, June 1978
5. D'Auria F.; Galassi G. M.: Code Validation and Uncertainties in System Thermal-hydraulics. J. Progress in Nuclear Energy 33 (1998) 175
6. Bousbia Salah, A.; D'Auria, F.: Analysis of the Peach Bottom 2 BWR Turbine Trip Experiment by RELAP5/Mod3.2. Nuclear Technology & Radiation Protection 17 (2002) 44
7. Hornyik, K.; Naser, J. A.: RETRAN Analysis of the Turbine Trip Tests at Peach Bottom Atomic Power Station Unit 2 at the End of Cycle 2, EPRI-NP-1076-SR, 1979
8. 2 Core in SPERT-1. IDO-16751, 1962
9. Watson, J. K.; Ivanov, K. N.: Improved Cross-section Modeling Methodology for Coupled Three-dimensional Transient Simulations. Annals of Nuclear Energy 29 (2002) 937
10. Spadoni, A.; Bousbia Salah, A.; D'Auria, F.; Galassi, G.; Vedovi, J.: Peach Bottom Turbine Trip Benchmark Analysis With RELAP5-3D Coupled Code, 2003 Relap5 International Users Seminar West Yellowstone, Montana (US) August 27-29, 2003.
11. Lewis, E. E.: Nuclear Power Reactor Safety. John Wiley & Sons, 1977
12. Frisch, W.; Langenbuch, S.; Peternell, P.: The significance of Fast Moderator Feedback Effects in a Boiling Water Reactor during Severe Pressure Transients. Nuclear Science and Engineering. 64 (1977) 843