BELLA: a multi-point dynamics code for safety-informed design of fast reactors

Bortot, Sara; Suvdantsetseg, Erdenechimeg; Wallenius, Janne

doi:10.1016/j.anucene.2015.05.017

Cited by 19 publications

(6 citation statements)

References 11 publications

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“…In order to assess the system behaviour during transients the model was incorporated in the in-house transient analysis code BELLA. BELLA is a multipoint dynamics code, based on a lumped parameter approach and point-wise description of reactor components, such as the core, the primary system, steam generator, and secondary system [13].…”

Section: Numerical Simulation Methodsmentioning

confidence: 99%

Investigation of a Self-Actuated, Gravity-Driven Shutdown System in a Small Lead-Cooled Reactor

et al. 2021

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Passive safety systems in a nuclear reactor allow to simplify the overall plant design, beside improving economics and reliability, which are considered to be among the salient goals of advanced Generation IV reactors. This work focuses on investigating the application of a self-actuated, gravity-driven shutdown system in a small lead-cooled fast reactor and its dynamic response to an initiating event. The reactor thermal-hydraulics and neutronics assessment were performed in advance. According to a first-order approximation approach, the passive insertion of shutdown assembly was assumed to be influenced primarily by three forces: gravitational, buoyancy and fluid drag. A system of kinematic equations were formulated a priori and a MATLAB program was developed to determine the dynamics of the assembly. Identifying the delicate nature of the balance of forces, sensitivity analysis for coolant channel velocities and assembly foot densities yielded an optimal system model that resulted in successful passive shutdown. Transient safety studies, using the multi-point dynamics code BELLA, showed that the gravity-driven system acts remarkably well, even when accounting for a brief delay in self-actuation. Ultimately the reactor is brought to a sub-critical state while respecting technological constraints.

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Section: Numerical Simulation Methodsmentioning

confidence: 99%

Investigation of a Self-Actuated, Gravity-Driven Shutdown System in a Small Lead-Cooled Reactor

et al. 2021

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“…Under this circumstance, the cladding temperature increased to a very high value, where all the failure-related behaviors will be accelerated, like corrosion, creep and rupture. Transient analyses for CiADS using the extended BELLA code are shown in Figure 4 [56,60]. Compared with the industrial EFIT design, CiADS is a 10 MW LBE-cooled subcritical reactor designed to demonstrate the engineering feasibility of the ADS concept.…”

Section: Transients and Reactor Dynamicsmentioning

confidence: 99%

Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects

Wang,

Yun

2023

Metals

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Lead-cooled fast reactors (LFRs) are considered one of the most promising technologies to meet the requirements introduced for advanced nuclear systems. LFRs have higher neutron doses, higher temperatures, higher burnup and an extremely corrosive environment. The failure studies of claddings play a vital role in improving the safety criteria of nuclear reactors and promoting research on advanced nuclear materials. This paper presented a comprehensive review of the extreme environment in LFRs based on the fuel performance analyses and transient analyses of reference LFRs. It provided a clear image of cladding failure, focusing on the underlying mechanisms, such as creep, rupture, fatigue, swelling, corrosion, etc., which are resulted from the motions of defects, the development of microcracks and accumulation of fission products to some extent. Some fundamental parameters and behavior models of Ferritic/Martensitic (F/M) steels and Austenitic stainless (AuS) steels were summarized in this paper. A guideline for cladding failure modelling was also provided to bridge the gap between fundamental material research and realistic demands for the application of LFRs.

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“…In this respect, the use of system codes to describe the dynamics of such complex systems is crucial to evaluate the dynamic behavior of the coupled timedependent neutron kinetics and thermal hydraulics. 2 There are some qualified codes especially used in nuclear power reactors licensing, such as RELAP, TRAC, CATHARE, ATLHETE, and others. These codes can solve the mass, energy, and momentum equations form 1-D up to 3-D for one-and two-phase flow.…”

Section: Introductionmentioning

confidence: 99%

Development of a zero‐dimensional dynamic simulator of a power conversion system with a high‐temperature gas reactor

Juárez‐Martínez

Espinosa-Paredes

2021

Int J Energy Res

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The HTTR-GT/H2 plant is a nuclear power cogeneration plant for hydrogen production. The hydrogen production is based on the thermochemical sulfuriodine cycle able to produce about 30 NM 3 /h of hydrogen and 15 Nm 3 /h of oxygen. The power conversion system consists of a Bryton-cycle helium gas turbine designed to produce 1 MWe electric of power output, and the source of heat is the high temperature engineering test reactor designed by the Japan Atomic Energy Agency. In this work, a preliminary dynamic simulator for the power conversion system was developed. The plant simulator couples the dynamics of the nuclear reactor, the internal heat exchanger, and plant components, such as heat exchangers, coolers, recuperators, compressors, and turbines. Despite the simplicity of modeling, the use of zero-dimensional models showed a good agreement with the reported values, being 0.67% of difference for reactor's power, 0.22% of difference for the coolant outlet temperature, and the differences of the conversion system components compared to the reference ranges between 0.0 and 0.26%.

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BELLA: a multi-point dynamics code for safety-informed design of fast reactors

Cited by 19 publications

References 11 publications

Investigation of a Self-Actuated, Gravity-Driven Shutdown System in a Small Lead-Cooled Reactor

Investigation of a Self-Actuated, Gravity-Driven Shutdown System in a Small Lead-Cooled Reactor

Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects

Development of a zero‐dimensional dynamic simulator of a power conversion system with a high‐temperature gas reactor

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