Flow pattern and pressure fluctuation characteristics on the 1/3 scale hot-leg piping experiments of a primary circuit hot-leg piping in a sodium-cooled fast reactor

Sago, Hiromi*; Shiraishi, Tadashi*; Watakabe, Hisato*; Xu, Y.*; Aizawa, Kosuke; Yamano, Hidemasa

Nihon Kikai Gakkai Rombunshu, B, 78(792), p.1378 - 1382, 2012/08

https://doi.org/10.1299/kikaib.78.1378

A conceptual design study of the Japan Sodium-cooled Fast Reactor (JSFR) is in progress in "the Fast Reactor Cycle Technology Development (FaCT) project", and a two-loop primary system is adopted in order to economize the plant construction cost. In the JSFR the pipe thickness is designed to be considerably thinner and the mean sodium velocity increases. To understand the behavior of flow-induced vibration that is derived from the hydraulic characteristics under high Reynolds number conditions experiments were performed to evaluate and confirm the integrity.

Experimental demonstration on flow diodes applicable to a passive decay heat removal system for sodium-cooled reactors

Chikazawa, Yoshitaka; Aizawa, Kosuke; Shiraishi, Tadashi*; Sakata, Hideyuki*

Journal of Nuclear Science and Technology, 46(4), p.321 - 330, 2009/04

https://doi.org/10.3327/jnst.46.321

Pressure fluctuation characteristics of the short-radius elbow pipe for FBR in the postcritical Reynolds regime

Shiraishi, Tadashi*; Watakabe, Hisato*; Sago, Hiromi*; Kotake, Shoji; Yamano, Hidemasa

Proceedings of 2nd International Conference on Jets, Wakes and Separated Flows (ICJWSF 2008) (CD-ROM), 11 Pages, 2008/09

For the JAEA sodium-cooled fast reactor, an experimental study on the fluctuating pressure of the hot legs was carried out with tests using a 1/3-scale model. The total resistance coefficient is consistent with the published data, and our research has given some additional data up to the Reynolds number of 8.010. The flow pattern in the postcritical regime is independent of a Reynolds number. The statistical examination revealed that fluctuating pressures on the pipe wall depend on the mean velocity but not on the viscosity of the fluid. Negative spikes of pressure appeared for high velocity. Based on these experimental data it is revealed that, there are similarity laws for the scale of a model and the property of fluid, but not for the velocity in the pipe. We also discussed how to extrapolate the fluctuating pressure to the actual hot-leg conditions.

Comprehensive cost estimation method for decommissioning

Kudo, Kenji; Kawatsuma, Shinji; Rindo, Hiroshi; Watabe, Kozo; Tomii, Hiroyuki; Shiraishi, Kunio; Yagi, Naoto; Fukushima, Tadashi; Zaitsu, Tomohisa

Proceedings of 14th International Conference on Nuclear Engineering (ICONE-14) (CD-ROM), 8 Pages, 2006/07

Japan Atomic Energy Research Institute (JAERI) played a leading role in basic research in the field of atomic energy research and development, while Japan Nuclear Cycle Development Institute (JNC) did a major role in FBR cycle development and high level waste disposal. Following the Government's decision in December 2001, JAERI and JNC was merged as of October 1st, 2005. The new organization, Japan Atomic Energy Agency (JAEA), is an institute for comprehensive R&D for atomic energy, and is the largest research and development institute among Governmental R&D organizations. Its missions are basic research on atomic energy, R&D for nuclear fuel cycle, decommissioning of own facilities and disposal of waste, contribution to safety and non-proliferation, etc. The JAEA owns a number of nuclear facilities: research reactors such as JRR-2 and Joyo, prototype reactors such as ATR "Fugen" and FBR "Monju", fuel cycle plants such as Uranium Enrichment Demonstration Plant at Ningyo-Toge, MOX fuel plants at Tokai, Reprocessing Plant at Tokai, and Hot Laboratories such as JRTF and FMF. As a part of preparation of the mergence, JNC and JAERI have jointly developed a comprehensive cost estimation method for decommissioning, based on decommissioning and refurbishing experiences of JAERI and JNC. This method involves more estimation parameters from typical decommissioning activities than before, so as to make it more reliable. JAERI and JNC have estimated the total cost for decommissioning by using this method, and concluded that the cost would be 600 billion yen (approx. 5 billion USD).

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor, 17; Effect of inlet swirl flow on pressure fluctuation in 1/3-scale hot-leg experiment

Shiraishi, Tadashi*; Sago, Hiromi*; Watakabe, Hisato*; Xu, Y.*; Aizawa, Kosuke; Yamano, Hidemasa

no journal, , 

Flow characteristics in an elbow with swirl flow were experimentally obtained under a high Reynolds number regime. In the range of 015% of swirl flow fraction, no significant effect of the swirl flow on the magnitude of pressure fluctuation was not seen although the flow separation region at the elbow was twisted by the swirl flow.

Evaluation for flow-induced vibration of a primary circuit hot-leg piping in a sodium-cooled fast reactor, 2; Flow pattern and pressure fluctuation characteristics on the 1/3 scale hot-leg piping experiments

Sago, Hiromi*; Shiraishi, Tadashi*; Watakabe, Hisato*; Xu, Y.*; Aizawa, Kosuke; Yamano, Hidemasa

no journal, , 

no abstracts in English

Experimental study for the proposal of design measures against cover gas entrainment and vortex cavitation with 1/11 scale reactor upper sodium plenum model of Japan Sodium-cooled Fast Reactor

Yoshida, Kazuhiro*; Sakata, Hideyuki*; Sago, Hiromi*; Shiraishi, Tadashi*; Oyama, Kazuhiro*; Hagiwara, Hiroyuki*; Yamano, Hidemasa; Yamamoto, Tomohiko

no journal, , 

no abstracts in English

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium cooled fast reactor, 28; Pressure fluctuation and flow pattern on the 1/3-scale hot-leg experiments under defected inflow conditions

Sago, Hiromi*; Shiraishi, Tadashi*; Watakabe, Hisato*; Xu, Y.*; Aizawa, Kosuke; Yamano, Hidemasa

no journal, , 

no abstracts in English