The Startup of the Dodewaard Natural Circulation Boiling Water Reactor—Experiences

1994 ◽  
Vol 107 (1) ◽  
pp. 93-102 ◽  
Author(s):  
Wim H. M. Nissen ◽  
Jaap Van Der Voet ◽  
Jadranko Karuza
2011 ◽  
Vol 38 (10) ◽  
pp. 2227-2237 ◽  
Author(s):  
Vikas Jain ◽  
P.P. Kulkarni ◽  
A.K. Nayak ◽  
P.K. Vijayan ◽  
D. Saha ◽  
...  

Author(s):  
Shengyao Jiang ◽  
Xingtuan Yang ◽  
Youjie Zhang

The experiments were performed on the test loop HRTL-5, which simulates geometry and system design of the 5-MW Nuclear Heating Reactor developed by the Institute of Nuclear Energy Technology, Tsinghua University. Because of the difference of the geometry design and operating conditions between the heating reactor and the boiling water reactor, the flow behavior presents great differences too, some of which haven’t been deeply studied so far. Results show that in heating reactor, sub-cooled boiling, condensation and flashing play an important role on the flow instabilities of the natural circulation system. Correspondingly, geysering instability, flashing instability, and flow excursion are the very typical instabilities occurring in the primary loop of HRTL-5, which are different from those in boiling water reactor conditions. The compressibility of the steam space on the top of the primary loop has also great influence on the instability of the natural circulation system.


1990 ◽  
Vol 92 (2) ◽  
pp. 260-268 ◽  
Author(s):  
Hideo Nagasaka ◽  
Takashi Sato ◽  
Hirohide Oikawa ◽  
Ryoichi Hamazaki ◽  
Kenji Arai ◽  
...  

2004 ◽  
Vol 47 (2) ◽  
pp. 277-286 ◽  
Author(s):  
Muhammad Hadid SUBKI ◽  
Masanori ARITOMI ◽  
Noriyuki WATANABE ◽  
Moon Ki CHUNG ◽  
Hiroshige KIKURA

1999 ◽  
Vol 127 (1) ◽  
pp. 38-48 ◽  
Author(s):  
Haico V. Kok ◽  
Tim H. J. J. van der Hagen

2018 ◽  
Vol 4 (3) ◽  
Author(s):  
Sapna Singh ◽  
Garima Singal ◽  
A. K. Nayak ◽  
Umasankari Kannan

In a natural circulation boiling water reactor (BWR), the core power varies in both axial and radial directions inside the reactor core. The variation along the axial direction is more or less constant throughout the reactor; however, there exists variation of reactor power in the radial direction. The channels located at the periphery have low power compared to the center of the core and are equipped with orifices at their inlet. This creates nonuniformity in the radial direction in the core. This study has been performed in order to understand the effect of this radial variation of power on the stability characteristics of the reactor. Four channels of a pressure tube type natural circulation BWR have been considered. The reactor has been modeled using RELAP5/MOD3.2. Before using the model, it was first benchmarked with experimental measurements and then the characteristics of both low power and high power oscillations, respectively, known as type-I and type-II instability, have been investigated. It was observed that the type-I instability shows slight destabilizing effect of increase in power variation among different channels. However, in the case of type-II instability, it was found out that the oscillations get damped with an increase in power variation among the channels. A similar effect was found for the presence of orifices at the inlet in different channels. However, the increase in number of orificed channels showed stabilizing effect for both type-I and type-II instabilities.


Author(s):  
Tomohiko Ikegawa ◽  
Yukiko Kawabata ◽  
Yoshihiko Ishii ◽  
Masayoshi Matsuura ◽  
Shizuka Hirako ◽  
...  

A new concept of a small and medium sized light water reactor, named the double MS: modular simplified and medium small reactor (DMS) was developed. The main features of the DMS relative to overcoming the scale demerit are the miniaturization and simplification of systems and equipment, integrated modulation of construction, standardization of equipment layouts, and effective use of proven technology. The decrease in the primary containment vessel (PCV) height is achieved by reducing the active fuel length of the DMS core, which is about 2 m compared with 3.7 m in the conventional boiling water reactor (BWR). The short active fuel length reduces the drop in core pressure and overcomes the natural circulation system. By using the lower steam velocity in the upper plenum in the reactor pressure vessel (RPV), we can adopt a free surface separation (FSS) system. The FSS eliminates the need for a separator and thus helps minimize the RPV and PCV sizes. In order to confirm transient performance, the DMS plant performance under transient conditions was evaluated using the TRACG code. TRACG code, which can treat multidimensional hydrodynamic calculations in a RPV, is well suited for evaluating the DMS reactor transient performance because it can evaluate the void fraction in the chimney and therefore evaluate the natural circulation flow. As a result, the maximum change in the minimum critical power ratio of the DMS was 0.14, almost the same as for the current advanced boiling water reactor (ABWRs). In order to improve safety efficiency, developing an emergency core cooling system (ECCS) for the DMS was considered. The ECCS configuration in the DMS was examined to achieve core coverage and economic efficiency from the following: (1) eliminating high-pressure injection systems, (2) adopting passive safety-related systems, and (3) optimizing distribution for the systems and power source for the ECCS. In this way, the configuration of the ECCS for the DMS was established, providing the same level of safety as the ABWR and the passive systems. Based on the results of the loss of coolant accident analysis, we confirmed that the core can be covered by this configuration. Therefore, the plant concept was found to offer both economic efficiency and safety.


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