Reactivity control system of the high temperature engineering test reactor

Nuclear Engineering and Design

Volumn 233, Issue 1-3, 2004, Pages 89-101

  Tachibana, Yukio ^a   Sawahata, Hiroaki ^a   Iyoku, Tatsuo ^a   Nakazawa, Toshio ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

AC MOTORS; CONTROL SYSTEMS; COOLING; GRAVITATION; STRESS ANALYSIS; THERMAL STRESS;

CONTROL ROD SYSTEMS; REACTIVITY CONTROL SYSTEM; REACTOR SCRAMS;

HIGH TEMPERATURE REACTORS;

EID: 10644235545     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.07.014     Document Type: Conference Paper

References (17)

1. ASME Boiler and Pressure Vessel Code Case N-47-21, 1981. Class 1 Components in Elevated Temperature Service Section III, Division I. The American Society of Mechanical Engineers (ASME), New York.
2. Edwards, A.L., 1972. TRUMP: A Computer Program for Transient and Steady State Temperature Distribution in Multidimensional Systems. Lawrence Livermore Laboratory (rept. UCRL-14754, rev. 3).
3. Fukakura, J., Matsumoto, F., Araki, T., 1991. Effect of strain hold time on fatigue life of Alloy 800H at high temperatures. Trans. Jpn. Soc. Mech. Eng. 57 (540), 1700-1705.
4. Hino, R., et al., 1991. J. At. Energy Soc. Jpn. 33, 685.
5. Hirano, M., Hada, K., 1990. Development of THYDE-HTGR: Computer Code for Transient Thermal-Hydraulics of High-Temperature Gas-Cooled Reactor, JAERI-M 90-071.
6. Japan Atomic Energy Research Institute (JAERI). Present Status of HTGR Research & Development, February 1996.
7. Japan Atomic Energy Research Institute (JAERI). Present Status of HTGR Research & Development, August 1992.
8. Maruyama, S., et al., 1990. Temperature Analysis of Control Rod for HTTR, JAERI-M 90-104.
9. Monma, Y., et al., 1984. Assessment of elevated-temperature property data for Alloy 800H. Trans. Natl. Res. Inst. Met. 26 (3), 33-47.
10. Nishiguchi, I., et al., 1989. In: Proceedings of the Specialists Meeting Organized by the IAEA, GIFSUR-YVETTE, France, p. 105.
11. Nishiguchi, I., Tachibana, Y., Motoki, Y., Shiozawa, S., 1990. General Criteria for the Structural Design of the HTTR Control Rods. Report of the Japan Atomic Energy Research Institute, JAERI-M 90-152.
12. National Research Institute for Metals (NRIM) Creep Data Sheet No. 26A, 1983a. Data sheets on the elevated-temperature properties of iron base 21Cr-32Ni-Ti-Al alloy plates for corrosion and heat resistant applications (NCF 800H-P). National Research Institute for Metals, Tokyo.
13. National Research Institute for Metals (NRIM) Creep Data Sheet No. 27A, 1983b. Data sheets on the elevated-temperature properties of iron base 21Cr-32Ni-Ti-Al alloy tubes for heat exchanger seamless tubes (NCF 800H-TB). National Research Institute for Metals, Tokyo.
14. Saito, S., et al., 1994. Design of high temperature engineering test reactor (HTTR). Report of the Japan Atomic Energy Research Institute, JAERI 1332.
15. Tachibana, Y., et al., 1997. Integrity assessment of the high temperature engineering test reactor (HTTR) control rod at very high temperatures. Nucl. Eng. Des. 172, 93-102.
16. -2, Materials for Nuclear Reactor Core Application. BNES, London, pp. 23-28.
17. Watanabe, K., Kondo, T., Ogawa, Y., 1984. Postirradiation tensile and creep properties of heat-resistant alloys. Nucl. Technol. 66, 630-638.