Published 2021 | Version v1
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Coupling fast reactor design and scenario calculations: a new methodology applied to scenario optimization

  • 1. DES/IRESNE/DER/SPRC, CEA Cadarache, Saint Paul-lez-Durance, (France)
  • 2. DES/IRESNE/DER/SPESI, CEA Cadarache, Saint Paul-lez-Durance, (France)
  • 3. Laboratoire de Physique Subatomique et de Cosmologie (France)

Description

There is currently a sequential relation between reactor design studies and scenario studies. Generally speaking, it goes as follows: after establishing a set of objectives for the nuclear fleet, reactor concepts are designed to meet constraints and performance criteria coming from reactor physics (safety and efficiency aspects) and scenarios (minimizing plutonium inventory, minimizing natural uranium consumption...). Once the design phase is over, numerical models of the reactors are generated. The purpose of these numerical models is to simulate the irradiation by adapting the flux and the cross sections for given fresh fuel compositions, without accounting for reactor performances. In scenario calculations, these models are considered as fixed entries whereas scenario parameters such as reprocessing strategy, deployment dates or batch composition are adjustable. This sequential logic may not be optimal from both reactor design and scenario calculations points of view. From reactor design perspective, it is known for example that plutonium isotopy has an impact on reactor performances such as reactivity loss per cycle or maximum linear power which can lead to limitations on core parameters like cycle length or reactivity control system dimensioning. Taking into account the data of plutonium evolution coming from scenario calculations would enable a better dimensioning of reactivity control systems and a better monitoring of safety estimators. From a scenario perspective, using set reactor models may prevent the access to optimized results regarding given criteria. By considering an adaptive reactor which design can be modified online as an optimization lever, it is expected to get access to new optimized scenarios, while making sure that reactor safety indicators are acceptable at every moment of the simulation. The main goal of this paper is to present a new methodological approach that consists in using adaptive reactor design in scenario calculations in the case of sodium-cooled fast reactors (SFR). The construction of the adaptive fast reactor design using artificial neural network is presented as well as an explanation of the optimization loop that makes the link between the adaptive fast reactor and the scenario calculation. Then, this methodology is applied to an example: the minimization of plutonium inventory in a mixed fleet PWR-SFR. (authors)

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Part of:
Booklet of abstracts of the 5. Technical Workshop on Nuclear Fuel Cycle Simulation 2021 - TWoFCS 2021

Additional details

Publishing Information

Imprint Pagination
47 p.
Journal Page Range
p. 19
Report number
INIS-FR--24-2011

Conference

Title
5. Technical Workshop on Nuclear Fuel Cycle Simulation 2021
Acronym
TWoFCS 2021
Dates
28 Jun - 2 Jul 2021
Place
Aix en Provence (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
56003365
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; FAST REACTORS; NEURAL NETWORKS; PLUTONIUM; SODIUM COOLED REACTORS
Descriptors DEC
ACTINIDES; ELEMENTS; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTORS; TRANSURANIUM ELEMENTS

Optional Information

Notes
Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses