Abstract

Abstract The decay heat removal system (DHRS) for the European sodium-cooled fast reactor (ESFR) concept consists of three cooling systems, which provide highly reliable, redundant, and diversified decay heat removal functions. Two of the systems provide a strong line of defense, whereas the third system provides long term-heat removal. This third DHR system, DHRS-3, involves in separating oil, and water-cooled loops integrated in the reactor pit serves the purpose of the safety vessel. It is expected that the proposed DHR concept enables a robust demonstration of the practical elimination of the prolonged loss of the decay heat removal function. For its confirmation, detailed numerical analysis is needed as a basis for further investigation. Supporting this approach, the current evaluation with means of computational fluid dynamic (CFD) provides a preliminary thermal analysis of the capability of the oil cooling system in the reactor to be used for residual heat removal in the pit in case of emergency. For the evaluation, different heat flux values are assumed at the vessel wall to examine the range of the resulting temperatures. The temperature of the main vessel wall should be below 800 °C. Furthermore, a sodium leakage at 500 °C into the reactor pit is assumed. The concrete structure is below 70 °C.

Highlights

  • The European sodium-cooled fast reactor (ESFR) is a large pool-type oxide fueled sodium-cooled fast reactor (SFR) concept, which has been developed within the Euratom FP7 project CPESFR [1]

  • The decay heat removal system (DHRS) for the ESFR concept consists of three cooling systems, namely, DHRS-1, DHRS-2, and DHRS-3, which are described in detail in Refs. [5,6]

  • This paper describes the overall design of the reactor pit, including the preliminary parametric calculations of temperature distributions for various design scenarios

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Summary

Introduction

The European sodium-cooled fast reactor (ESFR) is a large pool-type oxide fueled sodium-cooled fast reactor (SFR) concept, which has been developed within the Euratom FP7 project CPESFR [1]. The DHRS-3 is a part of the safety innovation related to the replacement of the safety vessel with a reactor pit which is able to provide improved operational and safety functions of both the decay heat removal system and the containment function. The DHRS-3 consists of several independent oil/water systems to ensure redundancy and is installed between the primary vessel and the liner It is used both for cooling the reactor pit in normal operation and for DHR function when needed. About 3 MW have to be removed at a top cooling temperature of approximately 200 deg This CFD computation provides a preliminary thermal analysis of the capability of the oil cooling system in the reactor to be used for residual heat removal pit in case of an emergency. The third DHR system, DHRS-3, is implemented in the reactor pit with two independent cooling circuits, one with an oil heat exchanger brazed on the liner and the other one with water inside

European Sodium-Cooled Fast Reactor Concept
Reactor Pit
Cooling of the Concrete Structure in Case of Sodium
Conclusion
Findings
Funding Data
Full Text
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