INNOVATIVE SCO2-BASED HEAT REMOVAL TECHNOLOGY FOR AN INCREASED LEVEL OF SAFETY OF NUCLEAR POWER PLANTS

Project Information

sCO2-4-NPP

Grant agreement ID: 847606

DOI

10.3030/847606

Project closed

EC signature date 13 May 2019

Start date 1 September 2019

End date 31 August 2022

Funded under

• Euratom

Total cost

€ 2 786 971,25

EU contribution

€ 2 352 452,01

Coordinated by

ELECTRICITE DE FRANCE
France

Periodic Reporting for period 2 - sCO2-4-NPP (INNOVATIVE SCO2-BASED HEAT REMOVAL TECHNOLOGY FOR AN INCREASED LEVEL OF SAFETY OF NUCLEAR POWER PLANTS)

Reporting period: 2021-03-01 to 2022-08-31

Summary of the context and overall objectives of the project

The main aim of the sCO2-4-NPP project is to bring an innovative technology based on supercritical CO2 (sCO2) for heat removal in nuclear power plants (NPPs) closer to the market. sCO2-4-NPP builds on results of the previous H2020 sCO2-HeRo project, where the technology was first developed and brought to TRL3. The sCO2-4-NPP technology is designed to be a backup cooling system, attached to the secondary side of a pressurized water reactor, which will considerably delay or eliminate the need for human intervention (>72 hours) in case of accidents such as StationBlackOuts, thus replying to the need for increased safety in NPPs. Thanks to the compact size and modularity of the system, it can be retrofitted into existing NPPs and included in future NPPs under development.

Work performed from the beginning of the project to the end of the period covered by the report and main results achieved so far

The project has released 25 public deliverables as well as several scientific publications available through CORDIS and through the project website. First period results are reported in detail in deliverable 9.3 “Interim technical review”. Final results are summarized in the deliverable 8.5 “sCO2-4-NPP Symposium”. The exploitation plan is provided in deliverable 7.2 “sCO2-4-NPP exploitation plan”.
A summary of the main project results against high-level objectives is provided below.
1. Validation of sCO2 models in thermal-hydraulic system codes on lab scale
Testing and data generation on performance of sCO2-HeRo system
Validation of ATHLET, ATHLET/Modelica and CATHARE codes

2. Specification of an upscaled system, boundary conditions and simulations for implementation of sCO2-4-NPP loop in a full-scale NPP (PWR)
Definition of initial and boundary conditions for SBO accident
Simulation of sCO2-4-NPP loop using scaled-up component models

3. Preparation of a licensing roadmap of the sCO2-4-NPP system to ensure compliance with application regulation
Identification of the regulatory elements to be considered in the design of components and system and for reference plant modification on heat recovery system installation
Design bases and safety analyses for system and component and requirements for testing and operation
Independent review of requirements

4. Design of components for the sCO2-4-NPP loop in the context of licensing requirements
Improvement and design of the sCO2-4-NPP turbomachine
Conceptual design and optimization of the heat sink heat exchanger and heat recovery exchanger (HX)
Qualification according to nuclear requirements for turbomachinery and HX

5. Final design of the system architecture of sCO2-4-NPP integrated in a full-scale NPP
System architecture design parameters
Thermodynamic cycle design
Simulation of sCO2-4-NPP loop in a real NPP using real design parameters
Dynamic simulations and control system modifications
Real-time simulations for implementation in PWR simulator

6. Validation of sCO2-4-NPP loop in a virtual “relevant nuclear environment” PWR
Defining interface for sCO2 system code to be implemented to simulator
Implementation of sCO2-system code into PWR simulator environment and running Transients

7. Prepare technical, regulatory, financial and organisational roadmaps to bring sCO2-4-NPP to market
Technological, regulatory, financial and organisational roadmaps to reach TRL9

Based upon the results achieved so far (TRL-5), plant simulations for EPR, KONVOI-type PWR, and VVER-1000 indicate that one 10MW-cycle per 1000MWth would be capable to safely remove the decay heat for far more than 72 hours. This encouraging result must be further evaluated to bring the sCO2-based heat removal system to a higher TRL.

Progress beyond the state of the art and expected potential impact (including the socio-economic impact and the wider societal implications of the project so far)

Through a close collaboration between major industrial actors, research centers and highly-skilled academic institutions, the sCO2-4-NPP partners brought the full system to TRL5 and parts of it to TRL6-7 by carrying out experiments, simulations, design, upscaling and validation of the technology in a real NPP PWR simulator. Regulatory requirements have been considered in the conceptual design of components and the system architecture to increase the chances of acceptance by European nuclear safety authorities and speed up the road to the market. Detailed technical, regulatory, financial and marketing roadmaps have been developed for bringing the technology to industrial use (TRL 9) after the project. The sCO2-4-NPP technology will increase NPP safety, decrease the plant overall environmental footprint and potentially lower costs for energy consumption, thus increasing the competitiveness of European NPP operators.

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