Development of a computer code, ONCESG, for the thermal-hydraulic design of a once-through steam generator

Journal of Nuclear Science and Technology

Volumn 37, Issue 5, 2000, Pages 445-454

  Yoon, Juhyeon ^a   Kim, Joo Pyung ^a   Kim, Hwan Yeol ^a   Lee, Doo Jeong ^a   Chang, Moon Hee ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Empirical correlation; Friction factor; Heat transfer; MRX; Numerical solution; Once through steam generator; Sensitivity analysis; SMART; Thermal hydraulic design; Thermal sizing equation

Indexed keywords

CORRELATION METHODS; FRICTION; HEAT TRANSFER; HYDRAULICS; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; PRESSURE DISTRIBUTION; PUMPS; STEAM GENERATORS; TEMPERATURE DISTRIBUTION; TUBES (COMPONENTS);

INTEGRAL REACTORS; SOFTWARE PACKAGE ONCESG; THERMAL HYDRAULICS;

NUCLEAR REACTORS;

EID: 0033688242     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2000.9714917     Document Type: Article

References (21)

1. The RELAP5 Development Team: RELAP5/MOD3 code manual; Model and correlations, NUREG/CR-5535, /ATEL-95/0174, (1995).
2. Nariai, N., Kobayashi, M., Matsuoka, T.: Friction pressure drop and heat transfer coefficient of two-phase flow in helically coiled tube once-through steam generator for integrated type marine water reactor, J. Nucl. Sci. Technol, 19[11], 936-947 (1982).
3. Tzanos, C. P.: A movable boundary model for once-through steam generator analysis, Nucl. Technol. 82, 5-17 (1988).
4. Berry, G.: Model of a once-through steam generator with moving boundaries and a variable number of nodes, 83- WA/HT-19, (1983).
5. Lee, D. J.: Development of a computer code for the thermal hydraulic design and performance analysis for a once-through steam generator, KAERI internal report, May (1995), [in Korean].
6. Yoon, J., et al.: Development of a computer code, ON-CESG, for the thermal hydraulic design and performance analysis for a once-through steam generator, 95 Proc. of Fall KNS, (1995), [in Korean].
7. Yoon, J., et al.: Thermal optimum design of modular once-through steam generators, 96 Proc. of Spring KNS, (1996), [in Korean].
8. Whang, S. T.: Introduction to IBM PC compatible ASME steam table with air properties, 90 Proc. of Fall KNS, (1990).
9. Mori, Y., Nakayama, W.: Study on forced convective heat transfer in curved pipes, Int. J. Mass Transfer, 10, 37-59 (1967).
10. Zukauskas, A. A.: Heat transfer from tubes in cross flow in adv. heat transfer, Academic, Vol. 8, pp. 93-106, (1972).
11. Todreas, N. E., Kazimi, M. S.: “Nuclear Systems I; Thermal hydraulic fundamentals”, Hemisphere Publ., (1990).
12. Lahey, R. T.: The Thermal-hydraulics of a Boiling Water Nuclear Reactor, Am. Nucl. Soc. (1977)
13. SKBK: Steam generator with helically coiled heat transfer area, Analytical Method (IZH ER.500609.001), SKBK internal report, (1984).
14. Collier, J. G.: “Convective Boiling and Condensation”, (2nd ed.), McGraw-Hill Book, (1972).
15. Carey, Van P.: “Liquid-Vapor Phase-Change Phenomena; An Introduction to the Thermophysics of Vaporization and Condensation Processes in Heat Transfer Equipment”, Hemisphere Publ., (1992).
16. JAERI: Research and Development Status of Nuclear Ships, (1993).
17. IAEA: Design and development status of small and medium reactor systems, IAEA-TECDOC-final draft, (1995).
18. Kozeki, M., Nariai, H., Furukawa, T., Kurosu, K.: A study of helically-coiled tube once-through steam generator, Bull JSME, 13, 1485 (1970).
19. Kakarala, C. R., Boardman, C. E.: Advanced liquid metal helical coil steam generator, AS ME G00548, (1990).
20. Campolunghi, F., Cumo, M., Palazzi, G., Urbani, G. C.: Subcooled and bulk boiling correlations for thermal design of steam generators, CENT-RT/ING (77)10, (1977).
21. Kreith, F., Bohn, M. S.: “Principles of Heat Transfer”, (4th ed.), Harper & Row, Publ., (1986).