Abstract

The Advanced Boiling Water Reactor (ABWR) and the Economic Simplified Boiling Water Reactor (ESBWR) are two kinds of contemporary, advanced, commercially available nuclear power reactors. Reactor internal pumps in an ABWR improve performance while eliminating the large recirculation pumps in earlier BWRs. The utilization of natural circulation and passive safety systems in the ESBWR design simplifies nuclear reactor system designs, reduces cost, and provides a reliable stability solution for inherently safe operation. The conceptually reliable stability solution for inherently safe ESBWR operation is developed by establishing a sufficiently high natural circulation flow line, which has a core flow margin at least 5% higher than the stability boundary flow at 100% rated power of a conventional BWR, and then by designing a high flow natural circulation system to achieve this high natural circulation flow line. The performance analyses for the ESBWR Emergency Core Cooling System (ECCS) show that: (1) the core remains covered with a large margin and there is no core heat up in the ESBWR for any break size, (2) the long-term containment pressure increases gradually with time, in the order of hours, and the peak pressure is below the design value with a large margin, and (3) the margins depend on the containment volumes and water inventories. These safety design features ensure inherently safe ESBWR operation. Enhanced safety features based on lessons learned from the Fukushima nuclear accident are added in ABWR’s and ESBWR’s safety designs. The major enhancements are the further prevention of station blackout and loss of ultimate heat sink.

Highlights

  • Reactor safety is essential and vital for nuclear power reactor operations

  • These calculations accounted for uncertainties and biases in the computer models and used conservative initial conditions and plant parameters. Results of these performance analyses show that: (1) core remains covered with large margin and there is no core heatup in the Economic Simplified Boiling Water Reactors (BWRs) (ESBWR) for any break size, (2) the long-term containment pressure increases gradually with time, in the order of hours, and the peak pressure is below the design value with a large margin, and (3) the margins depend on the containment volumes and water inventories

  • Reactor internal pumps have been used in Advanced BWR (ABWR) to improve performance while eliminating the large recirculation pumps in earlier BWRs

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Summary

INTRODUCTION

The Boiling Water Reactors (BWRs) have evolved from natural circulation in the Dodewaard BWR to external recirculation pump in BWR-2, to jet pump in BWR-3 to BWR-6, to internal recirculation pump in Advanced BWR (ABWR), and back to natural circulation in Economic Simplified BWR (ESBWR) [1-3]. Reactor internal pumps are used in ABWRs to improve performance while eliminating the large recirculation pumps in earlier BWRs. The utilization of natural circulation and passive safety systems in the ESBWR design simplifies nuclear reactor system designs, reduces cost, and provides a reliable stability solution for inherently safe operation. In the US, DTE Energy received the first ESBWR-based combined construction and operating license from the Nuclear Regulatory Commission in 2015 and Dominion Virginia Power has selected the ESBWR as its technology of choice for a potential third reactor at the North Anna site

Safety Feature of ABWR The safety features of an ABWR include
Performance Analyses of ECCS and Containment System
Findings
Conclusions
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