Parametric study of sloshing effects in the primary system of an isolated lead-cooled fast reactor
2015 (English)In: Nuclear Technology, ISSN 0029-5450, Vol. 190, no 1, 1-10 p.Article in journal (Refereed) Published
Risks related to sloshing of liquid metal coolant due to seismic excitation need to be investigated. Sloshing effects on reactor performance include first, fluid-structure interaction and second, gas entrapment in the coolant with subsequent transport of void to the core region. While the first can hypothetically lead to structural damage or coolant spill, the second increases the risk of a reactivity insertion accident and/or local dryout of the fuel. A two-dimensional computational fluid dynamics study is carried out in order to obtain insights into the modes of sloshing depending on the parameters of seismic excitation. The applicability and performance of the numerical mesh and the Eulerian volume of fluid method used to track the free surface are evaluated by modeling a simple dam break experiment. Sloshing in the cold plenum free surface region of the European Lead-cooled SYstem (ELSY) conceptual pool-type lead-cooled fast reactor (LFR) is studied. Various sinusoidal excitations are used to imitate the seismic response at the reactor level. The goal is to identify the domain of frequencies and magnitudes of the seismic response that can lead to loads threatening the structural integrity and possible core voiding due to sloshing. A map of sloshing modes has been developed to characterize the sloshing response as a function of excitation parameters. Pressure forces on vertical walls and the lid have been calculated. Finally, insight into coolant voiding has been provided.
Place, publisher, year, edition, pages
2015. Vol. 190, no 1, 1-10 p.
IdentifiersURN: urn:nbn:se:kth:diva-165389DOI: 10.13182/NT14-8ISI: 000352678000001OAI: oai:DiVA.org:kth-165389DiVA: diva2:808226
QC 201505132015-04-272015-04-272015-05-13Bibliographically approved