Fuel behavior analysis code FEMAXI-FBR development and validation for core disruptive accident

Okawa, Tsuyoshi; Tatewaki, Isao; Ishizu, Tomoko; Endô, Hiroshi; Tsuboi, Yasushi; Saitou, Hiroaki

doi:10.1016/j.pnucene.2014.11.002

Cited by 10 publications

(2 citation statements)

References 3 publications

(1 reference statement)

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“…As a result, a majority of the codes (e.g., LIFE, FEMAXI, TRANSURANUS) represent the cylindrical fuel rod in a so-called one-and-a-half dimension (1.5D) and are capable of conducting performance analyses for the whole fuel pin under nominal and off-normal conditions. Table 6 collects most of the FPCs for fast reactors worldwide [105][106][107][108][109][110][111][112][113][114][115].…”

Section: Cladding Failure Modellingmentioning

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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Section: Cladding Failure Modellingmentioning

confidence: 99%

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

Wang,

Yun

2023

Metals

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“…This means that the reactor design must ensure its safety in the case of this accident. Several system computer codes have been developed to assess the safety of reactors with liquid metal coolants: SIMMER-III [1], FEMAXI-FBR [2], EUCLID/V1 [3] and others. These system codes make it possible to reproduce the progress of an accident on the scale of the entire reactor installation and predict its response to various emergency events.…”

Section: Introductionmentioning

confidence: 99%

Model of interaction of a steam-water cavity with a molten metal near a solid wall

Melikhov,

Finoshkina

2023

E3S Web of Conf.

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To evaluate the consequences of an accidental rupture of a steam generator heat exchange tube in a reactor with a heavy liquid metal coolant, a mathematical model of the interaction of a steam-water cavity with molten metal near a solid wall was developed. The melt flow is considered as a potential flow of an incompressible fluid. The heat exchange between the melt and the steam-water mixture is not taken into account. The steam-water mixture is modeled by an equilibrium two-phase model. It is believed that the evolution of the steam-water cavity is an isentropic process. The numerical implementation of the mathematical model was performed using the boundary element method. Verification of the developed model using a numerical solution of a spherically symmetric problem of the interaction of a spherical steam-water cavity with a melt in infinite space, obtained using the Rayleigh-Plesset equation, showed good agreement between the solutions obtained by different methods. Using the developed model, a test calculation of the interaction of a steam-water cavity with the surrounding molten metal near a solid wall was performed. Analysis of the calculation revealed several stages of this interaction

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