Dario Carloni

LOCA Accident for the DEMO Helium Cooled Blanket

The exploitation of Fusion as energy source requires also the demonstration of a limited impact in terms of risk to the staff, to the public, and to the environment, well below the limits established by international committees and national safety authorities. Therefore, a systematic safety analysis has to follow the design development to demonstrate that the safety objectives are met for each proposed solution. This analysis points out the dominant accident sequences and outlines the possible prevention, protection and mitigation actions and their associated systems. This analysis points out the dominant accident sequences and outlines the possible prevention, protection and mitigation actions and their associated systems. One of the most challenging accidents is a large break Loss of Coolant Accident (LOCA) of the Primary Heat Transfer System (PHTS) outside the Vacuum Vessel (VV), due to the possible consequences in terms of radiological releases to the environment. However, because of the relative small radiological inventory and to the lower decay heat density, the risk associated with a break of the primary cooling loop in a fusion reactor is lower than the risk of the same event in a fission reactor. Nevertheless the consequent peak of pressure in the Expansion Volume located within the Tokamak Building could severely impact the confinement function, hence the overall safety of the plant. For this purpose a numerical assessment of a blanket PHTS ex-vessel LOCA has been carried out considering two possible layout solutions. This analysis has been performed employing MELCOR 1.8.2 and aims to support the design of the Blanket and its PHTS with some safety-related considerations.

Application of PACTITER v3.3 Code to the ACPs Assessment of ITER Neutral Beam Injectors Primary Heat Transfer System

Abstract Activated Corrosion Products (ACPs) will be present in the various coolant loops of ITER: in-vessel and vacuum vessel, test blanket modules, auxiliary heating or diagnostic equipments. ACPs impact occupational exposure, routine effluents to the environment, and potential releases during accidents. Hence, the ACP inventory evaluation is an important task for ITER public and occupational safety. PACTITER v3.3 code is a computational tool derived from PACTOLE series of codes, modified in some modeling and computing capabilities. ITER Organization has included it as reference computer code for the ACP assessment. In the framework of its verification and validation activity, PACTITER v3.3 was used to assess the ACP inventory of the ITER Neutral Beam Injectors (NBIs) Primary Heat Transfer System (PHTS). This paper will document the preliminary results of this assessment, focusing on the impact of operation scenarios parameters (i.e. water chemistry, materials corrosion properties, etc.) and piping architecture.