Thermal-hydraulics/thermal-mechanics temporal coupling for unprotected loss of flow accidents simulations on a SFR - Archive ouverte HAL Access content directly
Journal Articles EPJ N - Nuclear Sciences & Technologies Year : 2016

## Thermal-hydraulics/thermal-mechanics temporal coupling for unprotected loss of flow accidents simulations on a SFR

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Cyril Patricot

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#### Abstract

In the frame of ASTRID designing, unprotected loss of flow (ULOF) accidents are considered. As the reactor is not scrammed, power evolution is driven by neutronic feedbacks, among which Doppler effect, linked to fuel temperature, is prominent. Fuel temperature is calculated using thermal properties of fuel pins (we will focus on heat transfer coefficient between fuel pellet and cladding, $H_{gap}$ , and on fuel thermal conductivity, $\lambda_{fuel}$) which vary with irradiation conditions (neutronic flux, mass flow and history for instance) and during transient (mainly because of dilatation of materials with temperature). In this paper, we propose an analysis of the impact of spatial variation and temporal evolution of thermal properties of fuel pins on a CFV-like core behavior during an ULOF accident. These effects are usually neglected under some a priori conservative assumptions. The vocation of our work is not to provide a best-estimate calculation of ULOF transient, but to discuss some of its physical aspects. To achieve this goal, we used TETAR, a thermal-hydraulics system code developed by our team to calculate ULOF transients, GERMINAL V1.5, a CEA code dedicated to SFR pin thermal-mechanics calculations and APOLLO3$^®$ , a neutronic code in development at CEA.

#### Domains

Physics [physics]

### Dates and versions

cea-02304347 , version 1 (03-10-2019)

### Identifiers

• HAL Id : cea-02304347 , version 1
• DOI :

### Cite

Cyril Patricot, Grzegorz Kepisty, Karim Ammar, Guillaume Campioni, Edouard Hourcade. Thermal-hydraulics/thermal-mechanics temporal coupling for unprotected loss of flow accidents simulations on a SFR. EPJ N - Nuclear Sciences & Technologies, 2016, 2, pp.2. ⟨10.1051/epjn/e2015-50036-x⟩. ⟨cea-02304347⟩

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