Behavior of Fast Reactor Fuel During Transient and Accident Conditions

Papin, J.

doi:10.1016/b978-0-08-056033-5.00047-1

Cited by 15 publications

(2 citation statements)

References 10 publications

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“…Refs. [Perez-Martin 2013], [Fukano 2009], [Fukano 2010], [Charpenel 2000], [Papin 2012] describe these tests and the experimental data used in this report. The two of the tests adopted has VIGGEN-4 fuel pins (see Table 4.3.1.1 ) and three of the tests used SCARABIX fuel pins (see Table 4.3.1.1).…”

Section: Cabri-2 Slow Transient Over-power Benchmarksmentioning

confidence: 99%

Summary Report for U.S. and Japan Bilateral Collaborations (FY2019)

Grudziński

Wozniak

Lee

et al. 2019

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Within the frame work of the Civil Nuclear Energy R&D Working Group (CNWG), researchers from Argonne National Laboratory (ANL), Japan Atomic Energy Agency (JAEA) and Central Research Institute of Electric Power Industry (CRIEPI) have been participating in the R&D collaborations in three tasks that are related to the fast reactor technologies, which include metal fuel sodium-cooled fast reactor (SFR) core bowing analysis, modeling and simulation of Monju Turbine Trip Benchmark, and collaborative improvement of the SAS4A code. The core bowing analysis continued for two benchmark problems: IAEA bowing benchmark problem and ABR-1000 bowing problem. A correction was made to the IAEA VP4 bowing benchmark problem by adding in the clearance at the restraint rings, and the results were updated. The ABR-1000 bowing problem parameters were updated in this work to include analysis of the full core. Two accident cases, were introduced to investigate the response due to a single control-rod removal accident scenario. The input files were created and provided to Japanese collaborators. A NUBOW3D model was created for the ABR-1000 and preliminary results were obtained for all load cases for the ABR-1000 bowing benchmark problem. Finally, a new irradiation benchmark problem was introduced that included a single duct (CNWG-1A) to investigate irradiation swelling effects, and a two-duct contact problem (CNWG-1B) to investigate creep effects.

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Section: Cabri-2 Slow Transient Over-power Benchmarksmentioning

confidence: 99%

Summary Report for U.S. and Japan Bilateral Collaborations (FY2019)

Grudziński

Wozniak

Lee

et al. 2019

View full text Add to dashboard Cite

show abstract

“…This core has been designed in order to increase the time before boiling in case of ULOF transients and also to reduce the severity of a primary power excursion in case of severe accidents. For a classical core featured by a large positive sodium voiding effect, the sodium boiling transient resulting from a ULOF, would certainly lead to a large reactivity insertion that would cause a core power excursion [3]. The low void worth effect of the CFV core results mainly from the presence of a sodium plenum above the fissile zones [4] combined to the presence of a fertile plate in the inner core (FIG.…”

Section: Presentation Of the Cfv Core Conceptmentioning

confidence: 99%