Renewed interest in lead cooled fast reactors

Wider, H.U.; Carlsson, Johan; Loewen, Eric P.

doi:10.1016/j.pnucene.2005.05.003

Cited by 19 publications

(2 citation statements)

References 1 publication

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“…The LFR shows great potential for industrial development due to the excellent transmutation capacity and inherent safety [1]. Motived by the properties, a lot of research has been performed on the design and application of the LFR, such as SSTAR [2] and SUPERSTAR [3] launched by USA, SVBR-100 [4], and BREST [5] in Russia, MYRRHA [6], and ALFRED [7] designed by the EU, etc.…”

Section: Introductionmentioning

confidence: 99%

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

Mao

Song

Liu

et al. 2018

Science and Technology of Nuclear Installations

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This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natural circulation conditions to remove decay heat inside the main vessel of the Lead-bismuth eutectic cooled Fast Reactor (LFR). The motivation of this research is to improve the inherent safety of the LFR based on the China Accelerator Driven System (ADS) engineering project. Usually the plant is damaged due to the failure of the main pumps and the main heat exchangers under the Station Blackout (SBO). To prevent this accident, we proposed the DHRS based on the diathermic oil cooling for the LFR. The behavior of the DHRS and the plant was simulated using the CFD code STAR CCM+ using LFR with DHRS. The purpose of this analysis is to evaluate the heat exchange capacity of the DHRS and is to provide the reference for structural improvement and experimental design. The results show that the stable natural circulations are established in both the main vessel and the DHRS. During the decay process, the heat exchange power is above the core decay heat power. In addition, in-core decay heat and heat storage inside the main vessel are efficiently removed. All the thermal-hydraulics parameters are within a safe range. Moreover, the highest temperature occurs at the upper surface of the core. A swirl occurs at the corner of the lateral core surface and some improvements should be considered. And the natural circulation driving force can be further increased by reducing the loop resistance or increasing the natural circulation height based on the present design scenario to enhance the heat exchange effect.

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Section: Introductionmentioning

confidence: 99%

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

Mao

Song

Liu

et al. 2018

Science and Technology of Nuclear Installations

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“…Nuclear energy is a competitive and reliable emission-free power source that meets all the criteria mentioned above but also has drawbacks, such as the production of high activity radioactive waste, the potential production of nuclear weapons or the accident risk. However, fast reactors with closed fuel cycle can drastically reduce the volume of waste and the risk of producing weapon grade material ( 239 Pu and 235 U) [Brook et al, 2014], improving the economic competitiveness of fission reactors and having great availability factor and load-following capabilities [Wider et al, 2005]. One of the main challenges is showing that they are as safe as other existing reactors when they are to be built (2040 -2050), being able to maintain the very low safety risk of the current responsibly managed nuclear power plants.…”

Section: Introduction 11 Motivationmentioning

confidence: 99%

Nuclear data analyses for improving the safety of advanced lead-cooled reactors

Otero¹

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BoC Beginning of Cycle BoL Beginning of Life CEA Commissariat à l'Énergie Atomique et aux énergies alternatives CIELO Collaborative International Evaluated Library Organization CLUTCH Contribution-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance CHaracterization CR Control Rods DA Data Assimilation DAWN Data Assimilation With summoN DICE Database for the International handbook of evaluated Criticality safety benchmark Experiments ENDF Evaluated Nuclear Data File

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Development and application of CFD and subchannel coupling analysis code for lead‐cooled fast reactor

et al. 2019

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Summary It is of necessity and importance for the simulation of the three‐dimensional thermal hydraulics problem of the pool type fast reactor. However, because of current computing power limitations and the complexity of the reactor core structure, for conventional reactor applications, it is still not possible to directly simulate the entire reactor flow with sufficient fine meshes for detailed pin geometry. Until now, there is a multiscale coupling method which is suitable to deal with this type of simulation challenge. Through the user‐defined function (UDF) of FLUENT, the coupling code FLUENT/KMC‐sub for thermal hydraulic (TH) analysis by coupling the dynamic link library (DLL) complied by the transient subchannel code KMC‐sub is developed by University of Science and Technology of China (USTC). As a code validation case, the steady‐state simulation of a 19‐rod assembly has been carried out by using coupling codes of FLUENT/KMC‐sub, FLUENT and KMC‐sub, and consequently good consistency has been achieved by comparison with experiment results. And coupled code is further tested by comparison with the transient‐state 19‐pin assembly test results of KMC‐sub and FLUENT simulation. This coupling code is then used for TH of M2LFR‐1000 (medium‐size modular lead‐cooled fast reactor) in unprotected loss of flow (ULOF) accident. The transient temperatures of coolant and fuel and multidimensional TH phenomena and safety analysis are presented and discussed in this article.

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Renewed interest in lead cooled fast reactors

Cited by 19 publications

References 1 publication

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

Nuclear data analyses for improving the safety of advanced lead-cooled reactors

Development and application of CFD and subchannel coupling analysis code for lead‐cooled fast reactor

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