International standard problems and small break loss-of-coolant accident (SBLOCA)

Science and Technology of Nuclear Installations

Volumn 2008, Issue , 2008, Pages

  Aksan, N ^a  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT CONDITIONS; HYDROGEN DISTRIBUTION; INTERNATIONAL STANDARDS; NUCLEAR INSTALLATIONS; SMALL BREAK LOCA; STEAM GENERATOR TUBE RUPTURES; THERMAL HYDRAULIC SYSTEM CODE; THERMAL HYDRAULICS;

ACCIDENTS; COOLANTS; FISSION PRODUCTS; HYDRAULIC EQUIPMENT; LOSS OF COOLANT ACCIDENTS; NUCLEAR POWER PLANTS; NUCLEAR REACTORS; TEST FACILITIES;

PRESSURIZED WATER REACTORS;

EID: 84859731641     PISSN: 16876075     EISSN: 16876083     Source Type: Journal    
DOI: 10.1155/2008/814572     Document Type: Review

References (23)

1. OECD, CSNI international standard problems (ISP): brief description (1975-1997). 1997 NEA/CSNI/R(97)3 Paris, France OECD/NEA
2. Reocreux M., Aksan N., Contribution from twenty-two years of CSNI international standard problems. 1998. OECD/NEA report, NEA/CSNI/R(97)29, Paris, France
3. OECD/NEA, CSNI standard problem procedures. November 1989 17 Paris, France OECD/NEA. CSNI Report, OECD/NEA/GD (94)/82, 1994
4. Lessons learned from OECD/CSNI ISP on small break LOCA. 1996. OECD/NEA report written by group of experts, NEA/CSNI/R (96) 20, OCDE/GD (97) 10
5. Staedtke H., ISP 18: LOBI-MOD2 small break LOCA experiment final comparison report. 1986. CSNI Report no. 133, Paris, France
6. De Feu M., Firnhaber M., Pochard R., Stubbe E., ISP 20: doel-2 steam generator tube rupture event: final report. 1988. CSNI Report no. 154
7. De Toma G., Ederli S., Negrenti E., Marsili P., Pignatelli N., OECD/CSNI ISP 22: draft comparison report. 1990. NEAG 1 TP413 90009
8. Ambrosini W., Breghi M., D'Auria P. F., Galassi G. M., ISP 22: SPES loss of feedwater transient in Italian PWR: final comparison report and evaluation of post test analysis. 1992. CSNI Report no. 174- NEA/CSNI/R (92) 7, Paris, France
9. Kukita Y., Nakamura H., Watanabe T., ISP 26: ROSA-IV LSTF cold leg small break LOCA experiment: comparison report. 1992 NEA/CSNI/R (91) 13 Paris, France OECD/NEA
10. Clement P., Chataing T., Deruaz R., ISP 27: BETHSY small break LOCA with loss of HP injection. 1992. NEA/CSNI R(92) 20, Paris, France
11. Aksan S. N., D'Auria F., Staedtke H., User effects on the transient system code calculations. 1995. NEA/CSNI/R (94) 35
12. 10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light water cooled nuclear power reactors. 1974. Appendix K to 10 CFR part 50-ECCS Evaluation Models, US Cod of Federal Register
13. Lewis M. J., Pochard R., D'Auria F., Thermohydraulics of emergency core cooling in light water reactors-a state of the art report. October 1989 161 Paris, France OECD/NEA
14. D'Auria F., Karwat H., OECD/CSNI state of the art report on thermalhydraulics of emergency core cooling systems-review of the operation of experimental facilities. 1989. University of Pisa Report, DCMN NT 138(89), Pisa, Italy, OECD-CSNI Report SINDOC (89)101, Paris, France
15. Billa C., D'Auria F., Debrecin N., Galassi G. M., Application of relap5/Mod2 to PWR international standard problems. Winter Meeting of the American Nuclear Society (ANS '91) November 1991 San Francisco, Calif, USA
16. D'Auria F., Leonardi M., Pochard R., Methodology for the evaluation of thermalhydraulic code accuracy. Proceedings of International Conference on New Trends in Nuclear System Thermalhydraulics May-June 1994 Pisa, Italy
17. Bovalini R., D'Auria F., Galassi G. M., Scaling of complex phenomena in system thermalhydraulics. Journal of Nuclear Science and Engineering 1993 115 2 89 111
18. De Pasquale F., Sencar M., Aksan S. N., Bethsy 2″ cold leg break with accident management procedures (ISP 27): blind and post-test analysis calculations using the RELAP5/Mod2.5 code. Proceedings of the 1st Code Application and Maintenance Program Meeting (CAMP '92) May 1992 Villigen, Switzerland PSI
19. Annunziato A., Addabbo C., Briday G., Small break counterpart tests in the LSTF, BETHSY, LOBI and SPES test facilities. Proceedings of the 5th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-5) September 1992 Salt Lake City, Utah, USA
20. D'Auria F., Galassi G. M., Ingegneri M., Evaluation of the data base from the small break LOCA high power and low power tests performed in PWR experimental simulators LOBI and SPES. Proceedings of the 1st International Symposium on Two-Phase Flow Modelling and Experimentation October 1995 Rome, Italy
21. Ambrosini W., Bovalini R., D'Auria F., Evaluation of accuracy of thermalhydraulic code calculations. Journal Energia Nucleare 1990 7 2 5 16
22. Aksan N., D'Auria F., Glaeser H., Pochard R., Richards C., Sjoberg A., Separate effects test matrix for thermal-hydraulic code validation Vol. I: phenomena characterisation and selection of facilities and tests. July 1994. OECD/GD(94)82, Paris, France
23. Aksan N., D'Auria F., Glaeser H., Pochard R., Richards C., Sjoberg A., Separate effects test matrix for thermal-hydraulic code validation Vol. II: facilities and experiment characteristics. July 1994. OECD/GD(94)83, Paris, France