Design evaluation of emergency core cooling systems using Axiomatic Design

Nuclear Engineering and Design

Volumn 237, Issue 1, 2007, Pages 38-46

  Heo, Gyunyoung ^a   Lee, Song Kyu ^b  

^a Massachusetts Institute of Technology Cambridge   (United States)

^b Korea Advanced Institute of Science and Technology (KAIST)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

LAWS AND LEGISLATION; NUCLEAR POWER PLANTS; PLANT MANAGEMENT; SAFETY FACTOR; STRATEGIC PLANNING;

AXIOMATIC DESIGN (AD); DESIGN STRATEGIES; EMERGENCY CORE COOLING SYSTEMS (ECCS); VISUALIZATION TOOLS;

COOLING SYSTEMS;

EID: 33845391898     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2006.06.001     Document Type: Article

References (16)

1. Apostolakis G.E. How Useful Is Quantitative Risk Assessment ESD-WP-2003-05 (2003), Massachusetts Institute of Technology, Boston, USA
2. Axiomatic Design Solution Inc., 2005. Internet Homepage, http://www.axiomaticdesign.com.
3. Cho C.H., Park S.H., and Kim I.S. Advanced design characteristics of APR1400 nuclear steam supply system. International Congress on Advances in Nuclear Power Plants. Seoul, Korea, 15-19 May (2005)
4. Chung H.J., Chu I.C., Kim B.D., Park W.M., Song C.H., and Park J.K. Performance evaluation of passive safety injection flow controllers for the APR1400 reactor. Proceedings of 10th International Conference on Nuclear Engineering. Arlington, USA, 14-18 April (2002)
5. Herrmann J.L., and Wood P.J. The practical application of PRA: an evaluation of utility experience and USNRC perspectives. Reliability Eng. Syst. Saf. 24 2 (1989) 167-198
6. International Atomic Energy Agency (IAEA), 2003. Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors, Safety Reports Series No. 30. IAEA, Vienna, Austria.
7. Institute of Electrical and Electronics Engineers (IEEE). IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations, IEEE Std 603-1988 (1998), IEEE-SA Board, New York, USA
8. Kim D.S., and Kim I. Evolutionary Korean next generation reactor (KNGR)-APR1400. 10th International Conference on Nuclear Engineering. Arlington, USA, 14-18 April (2002)
9. Korea Power Engineering Co., Inc. (KOPEC), 2000. Probabilistic Safety Assessment Report for YGN5&6, Deajeon, Korea.
10. KOPEC, 2001. KNGR Level 1 Internal Event PSA Report. Deajeon, Korea.
11. Lee K.W., Huh J., Choi H.Y., and Ro T.S. Advanced Design Feature of SIS/SCS for APR1400, 17th KAIF/KNS Annual Conference. Seoul, Korea, 17-19 April (2002)
12. Pate-Cornell M.E., Dillon R.L., and Guikema S.D. On the limitations of redundancies in the improvement of system reliability. Risk Anal. 24 6 (2004) 1423-1436
13. Savransky S.D. Engineering of Creativity: Introduction to TRIZ Methodology of Inventive Problem Solving (2000), CRC Press, Boca Raton, USA
14. Song C.H., Kwon T.S., Chu I.C., Jun H.G., and Park C.K. Overview of Thermal-Hydraulic Test Program for evaluating or verifying the performance of new design features in APR1400 reactor. Proceedings of International Congress on Advanced Nuclear Power Plants. Hollywood, FL, USA, 9-13 June (2002)
15. Suh N.P. Axiomatic Design: Advances and Applications (2001), Oxford University Press, New York, NY, USA
16. Trewn J., and Yang K. The relationship between system functions, reliability and dependent failures. Proceedings of IEEE International Conference on System, Man, and Cybernetics. San Diego, USA (September 1998)