A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors

被引：1

作者：

Abrate, Nicolo ^{[1
,2
]}

Aimetta, Alex ^{[1
]}

Massone, Mattia ^{[3
]}

Dulla, Sandra ^{[1
,2
]}

Ravetto, Piero ^{[1
,2
]}

机构：

[1] Politecn Torino, Dipartimento Energia, NEMO Grp, Corso Duca Abruzzi 24, I-10129 Turin, Italy

[2] Ist Nazl Fis Nucleare INFN, Sez Genova, Via Dodecaneso 33, I-16146 Genoa, Italy

[3] ENEA Ctr Ric Bologna, Dipartimento Nucleare, Via Mille 21, I-40121 Bologna, Italy

来源：

NUCLEAR SCIENCE AND ENGINEERING | 2025年

关键词：

Lead-cooled fast reactor; energy group structure optimization; genetic algorithm; nodal full-core calculation; DIFFUSION ANALYSES; METHODOLOGY; ALGORITHM; CROSSOVER; MUTATION;

D O I：

10.1080/00295639.2024.2446130

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

This work presents a novel genetic algorithm (GA) for optimizing the few-group energy grid structure used for full-core nodal calculations in lead-cooled fast reactors. The optimization is started considering a set of group constants computed on a reference 61-group structure from which the GA selects an optimal subset of groups. Compared to existing works in the literature, the number of groups is not defined a priori but varies within a user-defined range, allowing a better exploration of the solution space. This feature requires one to develop an adequate representation of the chromosomes used in the evolution process, which is examined with different definitions of the chromosomes. The work also proposes a suitable combination of physics-driven fitness functions (FFs) related to the effective multiplication factor, the power density, and the neutron flux. Different weights based on the adjoint flux are also studied for the flux FF, with the aim of improving the convergence of the evolution process. All the studies are performed focusing on a three-dimensional model of the Advanced Lead Fast Reactor European Demonstrator (ALFRED) core design, which is modeled using the multigroup diffusion module of the Fast REactor NEutronics/Thermal-hydraulICs (FRENETIC) multiphysics code. The results suggest that the energy grid can be profitably optimized using a representation with two chromosomes. The optimal solutions yielded by the GA are justified on a physical basis by looking at some relevant figures of merit.

引用

页数：26

共 26 条

[1]

ALCOUFFE R. E., 2009, LA-UR-08-07258, Los Alamos National Laboratory

[2]

BELL S., 1970, Nuclear Reactor Theory

[3] A ComDarison of Selection Schemes Used in Evolutionary Algorithms [J].

Blickle, Tobias ;

Thiele, Lothar .

EVOLUTIONARY COMPUTATION, 1996, 4 (04) :361-394

[4] A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors [J].

Bonifetto, R. ;

Dulla, S. ;

Ravetto, P. ;

Richard, L. Savoldi ;

Zanino, R. .

NUCLEAR ENGINEERING AND DESIGN, 2013, 261 :85-94

[5]

CORMEN TH, 2001, INTRO ALGORITHMS

[6] Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing-Part II: Methodology application [J].

Di Nora, V. A. ;

Fridman, E. ;

Nikitin, E. ;

Bilodid, Y. ;

Mikityuk, K. .

ANNALS OF NUCLEAR ENERGY, 2021, 163

[7] Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - Part I: Methodology demonstration [J].

Di Nora, V. A. ;

Fridman, E. ;

Nikitin, E. ;

Bilodid, Y. ;

Mikityuk, K. .

ANNALS OF NUCLEAR ENERGY, 2021, 155

[8]

FASINA O., 2022, P INT C PHYS REACT 2, p1340, Am

[9]

Goldberg D. E., 1991, Foundations of Genetic Algorithms, V1, P69

[10] The core design of ALFRED, a demonstrator for the European lead-cooled reactors [J].

Grasso, G. ;

Petrovich, C. ;

Mattioli, D. ;

Artioli, C. ;

Sciora, P. ;

Gugiu, D. ;

Bandini, G. ;

Bubelis, E. ;

Mikityuk, K. .

NUCLEAR ENGINEERING AND DESIGN, 2014, 278 :287-301

← 1 2 3 →