Small Modular Reactors: An Overview of Modeling, Control, Simulation, and Applications

被引：19

作者：

Wang, Yulin ^{[1
]}

Chen, Weiran ^{[1
]}

Zhang, Linxuan ^{[1
]}

Zhao, Xinyu ^{[1
]}

Gao, Yiming ^{[1
]}

Dinavahi, Venkata ^{[1
]}

机构：

[1] Univ Alberta, Dept Elect & Comp Engn, Edmonton, AB T6G 2R3, Canada

来源：

IEEE ACCESS | 2024年 / 12卷

基金：

加拿大自然科学与工程研究理事会;

关键词：

Inductors; Coolants; Mathematical models; Fuels; Safety; Neutrons; Computational modeling; Power system control; Nuclear power generation; Boiling water reactor; computational fluid dynamics; digital simulation; dynamic matrix controller; gas-cooled reactor; light water reactor; liquid metal-cooled reactor; mathematical modeling; molten salt breeder reactor; molten salt reactor; nuclear power; power system control; pressurized water reactor; reactor applications; reactor control; reactor design; small modular reactors; sodium-cooled fast reactor; very high-temperature reactor; MOLTEN-SALT REACTOR; GAS-COOLED REACTOR; DYNAMIC-MODEL; NUCLEAR-REACTORS; LEVEL CONTROL; ANALYSIS CODE; FUEL-CYCLE; SYSTEM; DESIGN; PERFORMANCE;

D O I：

10.1109/ACCESS.2024.3351220

中图分类号：

TP [自动化技术、计算机技术];

学科分类号：

0812 ;

摘要：

A small modular reactor (SMR) is a nuclear reactor that is characterized by its smaller size and capacity when compared to traditional large-scale nuclear reactors. An SMR is often categorized as having an electrical output of less than 300MW and is built to be more mobile, safe, and extensible to deploy. It has been established that SMRs can provide economic and flexibility advantages in a variety of industries thanks to the development, study, and use of multiple types of SMRs in recent years. The goal of this paper is to present a comprehensive overview of several SMR types, including light water reactors (LWRs), liquid metal-cooled reactors (LMRs), molten salt reactors (MSRs), and gas-cooled reactors (GCRs). Each type of reactor is reviewed in terms of its structural design, modeling control implementation, applications, and impacts concerning the power system.

引用

页码：39628 / 39650

页数：23

共 191 条

[1] Liquid metal cooled fast reactor thermal hydraulic research development: A review [J].

Agbevanu, Kafui Tsoeke ;

Debrah, Seth Kofi ;

Arthur, Emmanuel Maurice ;

Shitsi, Edward .

HELIYON, 2023, 9 (06)

[2]

Al-Dawood K.A, 2021, Modeling, Simulation and Optimization of Lead-CooledFast Reactors

[3] TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system [J].

Al-Yahia, Omar S. ;

Clifford, Ivor ;

Nikitin, Konstantin ;

Liu, Prosper ;

Ferroukhi, Hakim .

NUCLEAR ENGINEERING AND DESIGN, 2023, 406

[4] Overview of lead-cooled fast reactor activities [J].

Alemberti, Alessandro ;

Smirnov, Valery ;

Smith, Craig F. ;

Takahashi, Minoru .

PROGRESS IN NUCLEAR ENERGY, 2014, 77 :300-307

[5]

Ali M.R. A., 1976, Lumped parameter, state variable dynamic models for U-tube recirculation type nuclear steam generators

[6]

Andrews H., 2021, P 12 NPIC HMIT, P723, DOI [DOI 10.13182/T124-34454, 10.13182/T124-34454]

[7]

[Anonymous], 2014, Preliminary Study of the Use of Freeze-Valves for a Passive ShutdownSystem in Molten Salt Reactors

[8]

[Anonymous], 2011, Status of Small and Medium Sized Reactor Designs: A Supplement tothe IAEA Advanced Reactors Information System (ARIS)

[9]

[Anonymous], 2020, Pussive Shutdown Systems for Fast Neutron Reactors

[10]

[Anonymous], 2017, Integral Pressurized Water Reactor Simulator Manual

← 1 2 3 4 5 6 7 8 9 10 →