Transient analyses for China initiative Accelerator Driven System using the extended BELLA code

Wang, Guan; Wallenius, Janne; Yu, Rui; Jiang, Wei; Zhang, Lu; Sheng, Xin; Yun, Di; Gu, Long

doi:10.1016/j.anucene.2023.109892

Cited by 4 publications

(3 citation statements)

References 27 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…For innovative reactor systems such as GEN-IV LFRs, transient analyses play an important role and provide references of the relatively realistic in-pile environments for research and experiments on nuclear materials. In this paper, transient analyses of DBCs for EFIT and CiADS were summarized and compared [55][56][57], including beam-trip transients, unprotected beam overpower (UBOP), unprotected loss of flow (ULOF), unprotected and protected loss of heat sink (ULOHS and PLOHS). The "protected" for ADSs without control rods means a beam interruption is triggered at the beginning of accident sequences.…”

Section: Transients and Reactor Dynamicsmentioning

confidence: 99%

“…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%

“…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%

See 2 more Smart Citations

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

Wang,

Yun

2023

Metals

Self Cite

View full text Add to dashboard Cite

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.

show abstract

Section: Transients and Reactor Dynamicsmentioning

confidence: 99%

Section: Transients and Reactor Dynamicsmentioning

confidence: 99%