Review of fuel assembly design in lead‐based fast reactors and research progress in fuel assembly of China initiative accelerator driven system

Yu, Rui; Gu, Long; Sheng, Xin; Li, Jinyang; Zhu, Yongxu; Lu, Zhengding; Jiang, Wei

doi:10.1002/er.6569

Cited by 20 publications

(7 citation statements)

References 43 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The main design parameters of the CiADS subcritical reactor are listed in Table 1. A hexagonal FA with a rigid duct and metal spiral wire wrapping to radially separate fuel pins (shown in Supplementary Figure S1), has been proposed by the FA research group of the CiADS project at IMP-CAS (Yu et al, 2021).…”

Section: Reactor Designmentioning

confidence: 99%

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Wang

Yun

2021

Front. Energy Res.

Self Cite

View full text Add to dashboard Cite

The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy of Sciences (IMP-CAS). And in the first phase, UO2 fuels will be loaded in the subcritical core to test the coupling technology and achieve a long-term steady operation. A brief description of CiADS subcritical reactor, fuel assembly and fuel element are presented here, and a multi-physics performance analysis and design evaluation of CiADS UO2 fuel are carried out by means of the FUTURE code. FUTURE is a fuel performance analysis code to evaluate the synergy of phenomena occurring in the fuel element and their impact on the fuel design improvement for the liquid metal fast reactor, which was developed jointly by IMP-CAS and Xi’an Jiaotong University (XJTU). In this paper, the FUTURE code was modified and updated focusing on characteristics of CiADS fuels. Relocation and densification models were added. Results of the hottest fuel element, mainly concerning the thermo-mechanical behaviors, are discussed concerning both fuel and cladding performance on the basis of indicative design limits. According to the preliminary design, the CiADS UO2 fuel exhibits good performance, and the main safety parameters are far below the indicative limits. The Fuel Cladding Mechanical Interaction (FCMI) is not very serious, and the permanent cladding strains and Cumulative Damage Fraction (CDF) are small and even negligible thanks to the low level of fuel temperature and corresponding stress. However, some critical issues may still exist, especially on LBE corrosion near the coolant inlet, where protective oxide layers are very thin from BoL to EoL. The modeling is useful for providing feedback to the conceptual design of the CiADS LBE-cooled subcritical reactor and the update of FUTURE code.

show abstract

Section: Reactor Designmentioning

confidence: 99%

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Wang

Yun

2021

Front. Energy Res.

Self Cite

View full text Add to dashboard Cite

show abstract

“…The actual average fuel rod and wrapping ). Meanwhile, the actual clad outer diameter of the CiADS LFR fuel assembly is 13.1 mm, and the wire diameter is 2.0 mm [19]; so, the test section is an expansion of the CiADS LFR fuel assembly with the ratio of 2 : 1. The wire-wrap spacers and the fuel rods were manufactured through a self-designed gear synchronous positioning device.…”

Section: Experimental Methodsmentioning

confidence: 99%

PIV and CFD Study on Crossflow Characteristics in a 7-Pin Wire-Wrapped Bundle Channel

Fan

et al. 2023

International Journal of Energy Research

Self Cite

View full text Add to dashboard Cite

China initiative Accelerator Driven System (CiADS) combines a linac, spallation target and a Lead-cooled Fast Reactor (LFR) together, which is designed to transmute nuclear waste and accelerate the progress of China’s energy technology research towards the goal of carbon neutrality. A LFR uses helical wire-wrap spacers as positioning components to enhance crossflow mixing in the reactor core. To study the velocity distribution and crossflow characteristics in wire-wrapped rod bundle channels, a 2 : 1 magnified scale 7-pin bundle fuel assembly model was fabricated using polymathic methacrylate. Particle image velocimetry (PIV) and computational fluid dynamics (CFD) simulations were used to investigate the velocity distribution in the 7-pin bundle flow channels at Reynolds number of 1250~5000 in the x z plane and Reynolds number of 1500 and 2500 in the x y plane. The deviation between CFD simulation results and PIV experimental data was small, and the Reynolds Average Navier-Stokes model could accurately simulate the flow characteristics of the wire-wrapped fuel rod bundle channels. The maximum crossflow velocity caused by helical wires was about 40% of the axial bulk velocity. The normalized crossflow velocity at the subchannel interface varied approximately sinusoidally with the axial height. As the Reynolds number increased, the velocity distribution trend and the loss rate of axial velocity in flow channels remained essentially constant while the peak value of crossflow velocity increased. The contour images of velocities with different axial heights were obtained from the x y plane, and their velocity distribution had a certain periodicity. The axial velocity loss rate in each subchannel caused by wire-wrap spacer resistance was between 7.35% and 38.51%, and the axial velocity loss rates in inner subchannels were usually higher than those in edge subchannels.

show abstract

“…The compatibility of structural and cladding materials with heavy liquid metals is a major concern in the development of the lead-cooled fast reactor (LFR), which is proposed as a most promising reactor for accelerator-driven systems (ADS) in China. [1][2][3] Leadbismuth eutectic (LBE) alloys, developed in parallel with pure lead, are considered promising coolants for generation-IV LFRs, owing to their good neutron properties, efficient heat transfer, and inherent safety characteristics. [4,5] The operating temperature of LFRs is determined by the melting point of the cooling medium, and a low melting point reduces the risk of uncontrolled freezing at low temperatures.…”

Section: Introductionmentioning

confidence: 99%

The effects of Si‐ion implantation and preoxidation on the corrosion behavior of a new steel SIMP in 550∘C ${\bf{55}}{{\bf{0}}}^{\circ }{\bf{C}}$ lead‐bismuth eutectic

Shen

et al. 2023

Materials & Corrosion

View full text Add to dashboard Cite

To improve the corrosion resistance of SIMP steel, we have investigated Si‐ion implantation and preoxidation effects on the corrosion behavior of SIMP steel samples, which have been in stagnant lead‐bismuth eutectic (LBE) with saturated oxygen at C for 1000 h. It was found that increasing Si content on the surface did not improve corrosion resistance performance. By contrast, the preoxidized sample demonstrated high resistance to LBE corrosion due to the presence of a thin Cr‐enriched oxide layer.

show abstract

Review of fuel assembly design in lead‐based fast reactors and research progress in fuel assembly of China initiative accelerator driven system

Cited by 20 publications

References 43 publications

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

PIV and CFD Study on Crossflow Characteristics in a 7-Pin Wire-Wrapped Bundle Channel

The effects of Si‐ion implantation and preoxidation on the corrosion behavior of a new steel SIMP in 550∘C ${\bf{55}}{{\bf{0}}}^{\circ }{\bf{C}}$ lead‐bismuth eutectic

Contact Info

Product

Resources

About