Issue |
EPJ Nuclear Sci. Technol.
Volume 8, 2022
Fuel Cycle Simulation TWoFCS 2021
|
|
---|---|---|
Article Number | 15 | |
Number of page(s) | 12 | |
DOI | https://doi.org/10.1051/epjn/2022005 | |
Published online | 17 August 2022 |
https://doi.org/10.1051/epjn/2022005
Regular Article
Approach for the adaptations of a nuclear reactor model towards more flexibility in a context of high insertion of renewable energies
1
CEA, DES, IRESNE, DER, 13108, Saint Paul lez Durance, France
2
Univ. Grenoble Alpes, CNRS, Grenoble INP**, G2Elab, 38000 Grenoble, France
3
Energy Research Institute at NTU, Nanyang Technological University, Singapore
4
CEA, LITEN, 73375 Le Bourget-du-Lac, France
* e-mail: anne-laure.mazauric@cea.fr
Received:
14
July
2021
Received in final form:
22
March
2022
Accepted:
26
April
2022
Published online: 17 August 2022
The massive penetration of renewable energy sources (RES) that are variable and not “dispatchable”, may weaken the power system supply-demand balance. Nuclear power plants (NPP) contribute in part to this daily and seasonal balance thanks to the “load-following” mode in France for example, but there are still limits to their use. These limits prevent a nuclear power modulation as efficient and quickly as the conventional thermal power plants. The need in terms of power ramps for nuclear in a constrained power system has been quantified in previous studies. Nuclear may compensate for the removal of thermal power plants, in order to fulfill energetic strategies of CO2 reduction. The possibility that nuclear reactors can achieve power ramps of significant values (>5%Pn/min) is put forward and could make possible to replace the services currently provided by thermal power plants. The objective of the study is then to use these power system requirements as the main input parameter for the modelling of a current simplified nuclear reactor capable of responding to frequency control within a specific hypothesis framework. In this paper, a French 1300 MW pressurized water reactor is modelled. Parametric studies are carried out in order to reveal technical and technological constraints when increasing electric power ramp. The study explores ways of design, which may influence reactor flexibility, such as the neutron parameter, Doppler coefficient, or the thermohydraulic parameter, delay in the primary loop.
© A.-L. Mazauric et al., Published by EDP Sciences, 2022
This is an Open Access article distributed under the terms of the Creative Commons Attribution License (https://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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