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ENSAR2 workshop: GEANT4 in nuclear physics

24–26 Apr 2019
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Europe/Zurich timezone

Session

Energy applications

EA
25 Apr 2019, 14:20
Other Institutes

Other Institutes

CIEMAT Main auditorium - building 1 Avda. Complutense 40 28040 Madrid Spain

Conveners

Energy applications: Energy applications

  • Hector Alvarez Pol (Universidad de Santiago de Compostela)

Description

This session is dedicated to GEANT4 developments for simulation of fission and fusion nuclear systems.

Presentation materials

There are no materials yet.

  1. 5. Calculation of Delayed-Photoneutron Production in Heavy-Water Reactors using Geant4
    Dr Evan Rand (Canadian Nuclear Laboratories)
    25/04/2019, 14:20
    Nuclear reactions at low and intermediate energies
    Oral

    Understanding and predicting the dynamic behaviour of nuclear reactors is of paramount importance for reactor safety. This time-dependent behaviour is primarily driven by the emission of beta-delayed neutrons and photoneutrons following the decay of neutron-rich fission products. It is the production of these delayed neutrons which allows for a system-dependent “sluggishness” during power...

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  2. 41. Geant4 simulation of ADS
    Vladimir Grichine (Russian Academy of Sciences (RU))
    25/04/2019, 14:40
    Energy applications
    Oral

    Acceletator driven system (ADS) is simulated by the Geant4 tools - the mass layered geometry and scoring. The ADS target was simulated with different geometries of cooling layers. The neutron output spectra as well as energy deposition profiles are shown. The ADS power (and other parameters) dependence on driver thickness are shown. The medical isotope production is simulated in the batch mode...

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  3. 60. Adaptation of GEANT-4 to Criticality Calculations for Nuclear Reactors
    Adriaan Buijs (M)
    25/04/2019, 15:00
    Energy applications
    Oral

    GEANT-4 is well suited for criticality calculations in nuclear reactors, thanks to its ability to track particles, in this case neutrons, in time as well as in space. This sets it apart from traditional Monte Carlo codes such as MCNP, which treat neutrons on a generation-by-generation base. The latter gives inherently incorrect results, in particular for systems that are far from critical. ...

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