This work is the extension to a fuli reactor geometry of a former activity lmited to shielding calculation up to the reactor vessel for the IRIS (International Reactor Innovative and Secure) project The IRIS is a advanced medium size Light Water Reactor (LWR), being developed through an international partnership for a near term deployment to offer a simple nuclear plant with outstanding safety, attractive economics and enhanced proliferation resistance characteristics. It provides a viable bridge to Generation IV reactors and has excellent capability to satisfy in the near/mid-term timeframe the International Global Nuclear Energy Partnership (GNEP-I) requirements for small-scale reactors. The present document extends the Shielding activity carried out during the year 2009 at ENEA by means of the TORT (Three-dimensional discrete ordinates neutron/photon) ver. 3.2 deterministic code. The initial objectives of the analysis were the evaluation of the fast neutron fluence above 1 MeV (and DpA) on Pressure Vessel and a raw estimation of activation in the 'first' concrete. Finaily a full geometrical description has been performed in order to evaluate doses in the control room during normal operation.

Deterministic Shielding Calculations for the IRIS Reactor: Extended Geometry

Ciotti, M.
2010-10-05

Abstract

This work is the extension to a fuli reactor geometry of a former activity lmited to shielding calculation up to the reactor vessel for the IRIS (International Reactor Innovative and Secure) project The IRIS is a advanced medium size Light Water Reactor (LWR), being developed through an international partnership for a near term deployment to offer a simple nuclear plant with outstanding safety, attractive economics and enhanced proliferation resistance characteristics. It provides a viable bridge to Generation IV reactors and has excellent capability to satisfy in the near/mid-term timeframe the International Global Nuclear Energy Partnership (GNEP-I) requirements for small-scale reactors. The present document extends the Shielding activity carried out during the year 2009 at ENEA by means of the TORT (Three-dimensional discrete ordinates neutron/photon) ver. 3.2 deterministic code. The initial objectives of the analysis were the evaluation of the fast neutron fluence above 1 MeV (and DpA) on Pressure Vessel and a raw estimation of activation in the 'first' concrete. Finaily a full geometrical description has been performed in order to evaluate doses in the control room during normal operation.
Rapporto tecnico;Reattori nucleari ad acqua;Schermaggio delle radiazioni;Metodi deterministici
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/5418
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