Relaxation of the requirements on loop height and heat transfer area of a passive heat removal system in integral SMR using a self-powered booster
Introduction
In most of integral reactor designs, reactor core, coolant pumps, steam generators and pressurizer are all packed inside the reactor pressure vessel (Buongiorno et al., 2012, Fetterman et al., 2011, Wu et al., 2016, Wang et al., 2020a, Wang et al., 2020b) to form a compact system, as shown in Fig. 1. Such configuration makes it possible for pre-fabrication and testing at factories, which simplifies on-site installation process, reduces the number of auxiliary systems, and eliminates many pipe connections, thus, reducing the potential risks sources of loss of coolant accidents. Due to these unique advantages, the integral reactors have been chosen as a preferred configuration by several small modular reactor (SMR) types (Yang et al., 2008, Butt et al., 2016, IAEA, 2016), including reactors installed in limited spaces, such as onboard ships and submarines (Saunders, 2015, Yamaji and Sako, 1994, Zverev et al., 2013).
To improve safety of the reactors, passive heat removal systems, based on gravity driven natural circulation, have been adopted in many designs, such as MRX (Kusunoki et al., 2000), SMART (Kim et al., 2016) and WSMR (Buongiorno et al., 2012, Smith and Wright, 2012). As it is well known, in natural circulation systems, the fluid moves through a loop using inherent gravity force generated by the density differential between the cold and hot water in vertical pipes of the loop. This allows the residual heat to be removed out of the reactor core even during a complete loss of power.
On the other hand, among other things, such as temperature differential and the heat transfer areas, the gravity generated driving force is directly proportional to the loop height. Unfortunately, this height-dependence conflicts with the philosophy of compactness in integral SMRs. Furthermore, the gravity induced driving force is much weaker than pump induced force (IAEA, 2005, IAEA, 2009, IAEA, 2013). For a certain designed heat removal rating, a larger heat exchange is often needed in a natural circulation based system (Vijayan and Nayak, 2010) as compared with an externally powered forced flow system. This larger area requirement is again undesirable when one tries to make the overall system compact. In the current design of integral reactor systems, significant efforts have been made to improve compactness of the plant (Shirvan et al., 2016), by using reactor fuels with higher power density (Shirvan et al., 2012), compact steam generators (Zaman et al., 2017, Xiao et al., 2018) and supercritical CO2 Brayton cycle with reduced size, for different types of SMRs, including the IRIS (Carelli et al., 2004), and SMART (Yoon et al., 2012).
Despite the above efforts, the study on reduction of the physical size of the natural circulation systems in a passive heat removal system has not been found. As a result, the total space occupied by the natural circulation based residual heat removal system is also disproportionally large as compared to other sub-systems, considering that the decay heat often counts for only a few percent of the total unit power (Agnew, 1981, Ragheb, 2011, Yan and Hino, 2016).
To reduce the size of the heat removal system, a novel technique is developed, in which a self-powered efficiency booster is adopted. The booster converts part of the heat energy of working fluid in the loop itself into electrical power with thermoelectric generator (TEG). The electrical power is then used to generate drive force and enhance the circulation flow. Power conversion of the booster is independent of the gravity difference generation. As a result, one can potentially reduce the height of the natural circulation column and adopt smaller heat exchanger area without jeopardizing safety of the reactor.
In previous study of the authors’ research group, design and analysis of the booster in heat transfer capacity enhancement of natural circulation systems have been performed (Wang et al., 2017, Wang et al., 2020a, Wang et al., 2020b). While the current paper focuses on compactness improvement of the natural circulation system in integral SMRs with the booster.
To prove the concept of compactness improvement with the booster, both numerical simulation and experimental tests have been conducted. Special attentions have been paid to examine the relationships between the heat removal performance of the system and the loop height, and the heat exchanger area. The results have conclusively shown that, by using such a booster, the loop height of the heat removal system can be reduced by as much as 90%, and the heat exchanger area can be reduced by a factor of 25%–78%.
The rest of the paper is organized as follows. In Section 2, the problem under investigation is formulated and the solution process is proposed. The influence of the booster on the loop height and heat exchanger area has been numerically analyzed in Section 3. In Section 4, the results of experimental studies are presented. Finally, some conclusions are drawn in Section 5.
Section snippets
Natural circulation in safety systems of integral SMR reactors
In this section, passive residual heat removal systems based on natural circulation in WSMR is briefly examined. For the convenience of presentation, even though the natural circulation system of WSMR is used as an example system, the concept is applicable to those in other SMRs as well. In WSMR system, two natural circulation loops in series are used to remove the residual heat from the reactor core in accident conditions, as shown in Fig. 2(a) (Smith and Wright, 2012).
Within Loop 1, the
Numerical studies of the system with respect to loop heights and heat exchanger areas
To prove the concept of compactness improvement with the booster, modeling and numerical simulation of the booster involved system is performed, with respect to changes in the loop heights and heat exchanger areas. To ensure universality of the analysis results, the simulation work is carried out with a general natural circulation loop as indicated in the Loop 2 of Fig. 2(b), in which the designed booster is equipped. The simulation results are also compared with those of a natural circulation
Structure and operation of the experiment
To further valid the concept of reducing the dependence on the loop height by using a self-powered booster, the lab-scale proof-of-concept experimental investigations have been carried out as well. The experimental apparatus has been constructed, which consists of a hot-water tank as the heat source, a cold-water tank as the upper heat sink, two sets of heat exchangers, a TEG powered pump for driving force production, and associated connecting pipes. The set of four heat exchangers with TEG are
Conclusions
In this paper, a TEG based efficiency booster is proposed to improve the compactness of a natural circulation based passive residual heat removal system used in internal SMRs. Numerical simulation and experimental validation have been conducted to demonstrate that a self-powered booster can reduce the dependence on the loop height and the requirement on the heat exchanger area. Consequently, loop height of the system can be reduced by as much as 90% for a given heat transfer capacity without
CRediT authorship contribution statement
Dongqing Wang: Methodology, Software, Investigation. Jin Jiang: Funding acquisition, Investigation, Software, Supervision. Yu Liu: Investigation.
Declaration of Competing Interest
The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.
Acknowledgement
The authors acknowledge the financial supports from National Natural Science Foundation of China No. 12005317. The Canadian author also acknowledges the financial support from The Natural Sciences and Engineering Research Council of Canada (NSERC) and The University Network of Excellence in Nuclear Engineering (UNENE) for this work.
References (44)
- et al.
Assessment of passive safety system of a Small Modular Reactor (SMR)
Ann. Nucl. Energy
(2016) - et al.
Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants
Nucl. Eng. Des.
(2013) - et al.
The design and safety features of the IRIS reactor
Nucl. Eng. Des.
(2004) - et al.
IAEA activities on passive safety systems and overview of international development
Nucl. Eng. Des.
(2000) - et al.
Application of direct passive residual heat removal system to the SMART reactor
Ann. Nucl. Energy
(2016) - et al.
Design of advanced integral-type marine reactor
MRX. Nucl. Eng. Des.
(2000) - et al.
Methodology for the reliability evaluation of a passive system and its integration into a Probabilistic Safety Assessment
Nucl. Eng. Des.
(2005) Westinghouse AP1000 advanced passive plant
Nucl. Eng. Des.
(2006)- et al.
Technology selection for offshore underwater small modular reactors
Nucl. Eng. Technol.
(2016) - et al.
The design of a compact integral medium size PWR
Nucl. Eng. Des.
(2012)