Evaluation of Stability and Transient Characteristics of ABWR-II Large Bundle Core and SSR Influence for Transient phenomena by TRACG Code
- Hitachi, Ltd., 7-2-1, Omika-cho, Hitachi, 319-1221 (Japan)
- Tokyo Electric Company, 1-1-3, Uchisaiwai-cho, Chiyoda-ku, Tokyo, 100-0011 (Japan)
- Toshiba Corporation, 8, Shinsugita-cho, isogo-ku Yokohama, 235-8523 (Japan)
- Global Nuclear Fuel Japan, 2-3-1, Uchikawa, Yokosuka (Japan)
- Global Nuclear Fuel - Americas, P.O. Box 780, MC B12, Wilmington, NC 28402-0780 (United States)
The next generation ABWR, the ABWR-II, has been under development for more than a decade in Japan. Among various features newly adopted for the ABWR-II, a 1.5 times lager fuel bundle is notable. This bundle design makes it possible to increase the total number of fuel rods in the core while minimizing the reactor pressure vessel size increase. As a result, the void coefficient is more negative due to the harder neutron spectrum since a smaller hydrogen-to uranium (H/U) ratio with fuel inventory increase makes the neutron spectrum harder. This more negative void coefficient affects the stability and transient characteristics of the ABWR-II plant. We have evaluated the stability and transient characteristics by using analysis codes and proven that these characteristics do not affect the realization of the ABWR-II large bundle core concept. Furthermore, we have evaluated the influences for the stability and transient phenomena by using spectral shift rods (SSRs) for the ABWR-II core. The analytical results show that the use of SSRs increases the design margin for the core stability. Regarding transient phenomena, the analyses by the TRACG code show that the influence of using SSRs is very small and do not affect the realization of the ABWR-II plant. In addition, the sensitivity analyses with the TRACG code show that design parameters of SSRs, inlet hole diameter of ascending path etc, are not very sensitive for the transient phenomena. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21160586
- Resource Relation:
- Conference: ICAPP'04: 2004 international congress on advances in nuclear power plants, Pittsburgh, PA (United States), 13-17 Jun 2004; Other Information: Country of input: France; 12 refs; Related Information: In: Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04, 2338 pages.
- Country of Publication:
- United States
- Language:
- English
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