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PHENIICS Fest 2017

May 30 – 31, 2017
Laboratoire de l'Accélérateur Linéaire (LAL)
Europe/Paris timezone

Organizing commitee

Session

Nuclear energy

May 31, 2017, 5:45 PM
Amphithéâtre Pierre Lehman (Laboratoire de l'Accélérateur Linéaire (LAL))

Amphithéâtre Pierre Lehman

Laboratoire de l'Accélérateur Linéaire (LAL)

Bâtiment 200, 91440 Orsay, France

Description

Chairperson: Ms. Alice Somaini

Presentation materials

There are no materials yet.

  1. 60. Study on X-ray diagnosis for phase distribution during corium-sodium interaction
    Ms Shifali SINGH (CEA, Cadarache)
    5/31/17, 5:45 PM
    Talk
    In case of a severe accident scenario in sodium-cooled fast reactors, the fuel in the core would melt, generating a hot mixture termed as corium. This corium will then be discharged into the sodium pool through the guide tubes. When the hot molten corium comes in contact with sodium, called Molten Fuel-Coolant Interaction (MFCI), it might generate a violent explosion. Such an explosion can be...
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  2. 3. Quench Tests Analyses of the First JT-60SA Toroidal Field Coils
    Mr Yawei HUANG (CEA Saclay)
    5/31/17, 6:05 PM
    Talk
    **JT-60SA** is a fusion experiment which is jointly constructed by Japan and Europe, and which shall contribute to the early realization of fusion energy by providing support to the operation of ITER and by addressing key physics issues for ITER and DEMO. The JT-60SA is based on the existing infrastructure of JT-60U experiment and is upgraded by using **superconducting coils**. JT-60SA tokamak...
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  3. 29. Polynomial Axial Expansion for 3D method of characteristics applied to neutron transport
    Mr Laurent Graziano (CEA)
    5/31/17, 6:25 PM
    Talk
    In the recent years a solver based on the Method of Characteristics (MOC) allowing the treatment of 3D extruded geometries has been developed inside the TDT module of APOLLO3®. The standard Step Characteristics (SC) approximation is used and results show an excellent agreement with Monte-Carlo simulations. However a fine mesh refinement is needed to converge the strong flux gradients...
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  4. 17. Learning of the importance map in a direct Monte Carlo shielding calculation with the particle transport code TRIPOLI-4(R)
    Michel Nowak (CEA)
    5/31/17, 6:45 PM
    Talk
    TRIPOLI-4® is a Monte Carlo code that simulates the transport of particles (Neutrons, Photons, Electrons) and provides reference solutions that are used to validate faster deterministic codes. In radiation shielding studies, engineers use Monte-Carlo codes to estimate radiation doses rate due to radioactive sources, given a description of the problem geometry. However, Monte Carlo methods may...
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