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Passive Isolation Condenser

Deliverables

Identification of enveloping transient and system configuration for reactor technologies of European interest

The deliverable contains the definition of enveloping transients of interest to be analyzed for the LFR and ADS reactors . These are the accidental scenario for the reactor technology for which the safety system is intended to provide the maximum benefit. Since the removal of the decay heat and the prevention of freezing are conflicting requirements, two opposition scenarios will be considered and described in the report

Communication plan

The report will cover the communication plan and will contain well-planned and concerted actions aimed to promote PIACE ideas on innovative passive systems among the key nuclear industry players and its potentiality in increasing the safety of European citizens, as well as to ensure project visibility at international level.

Test Matrix Definition for the LFR reference reactor

The deliverable deals with the test matrix relevant for the experimental characterization on SIRIO facility, on its first configuration, for the LFR reference reactor technology. The test matrix will include operating parameters and operation procedure based on the feedback received from WP1, and it will take in account specific tests for STH code validation, needed for the activity scheduled on WP4.

Test Matrix Definition and Facility Upgrade for ADS reference Reactor

The report describes the SIRIO facility upgrading aiming at experimentally reproduce the behaviour of the selected ADS reference reactor technology (the MYRRHA reactor), the finalization of a test matrix suitable for characterizing the SIRIO facility application on MYRRHA reactor, and the pre-test simulations, through means of STH codes, of the planned experiments.

Project Presentation

The deliverable contains a short presentation of the project objectives and activities to be published for giving to the public at large an overview of the content of the project

Modelling of safety system and safety analyses for reactor technologies of European interest

The report contains the description of the development or update of a model representative of the reactor coolant system and the safety system by means of the system code (RELAP5, TRACE, APROS, or alternative system code). Application of the numerical model and the simulation for the identified accident scenario(s) will be outlined

Test Matrix Definition and Facility Upgrade for PHWR reference Reactor

Starting from the input provided by WP1, the following minimum set of operating parameters will be considered in the beginning in the test matrix for PHWR reference reactor: feedwater pressure in the secondary side of the Steam Generator, feedwater mass flow and temperature, Steam Generator water level and primary coolant temperature, as well as the DHR isolation condenser pressure and temperature. The parameters represent the starting point of facility upgrading able to ensure its integration in the safety system of PHWR. The appropriate instrumentation, components and layout as well as operation procedures will be provided.

Test Matrix Definition and Facility Upgrade for BWR reference Reactor

The report includes, in first place, a proposal of upgrade of the SIRIO facility regarding instrumentation, layout & components and logical controls needed to better simulate the phenomena and system behavior highlighted in WP1 for BWR. In second place, it includes a test matrix relevant for the experimental characterization on SIRIO facility, on the proposed upgraded configuration, for the BWR reference reactor technology.

Plan for Exploitation and Dissemination of PIACE’s Results (PEDR)

The plan contains the exploiting and dissemination measures to be adopted, consisting in: strategic vision on exploiting (objective, selection criteria for results and stakeholders), means for exploiting and dissemination, implementation plan for exploiting (actions, responsible and planning), dissemination plan for the overall project. The exploiting is oriented to the targeted audience able to speed the implementation of the innovative results (closer to market concept).

Test Matrix Definition and Facility Upgrade for PWR reference Reactor

The deliverable will be based on the input provided by WP1. It will summarize the proposed SIRIO facility upgrades, which will be relevant for experimental reproduction of the phenomena identified in the PWR reference reactor operation with isolation condenser. D2.3 will define the upgrades for the SIRIO facility: instrumentations, layout & components and logical controls needed to better simulate the phenomena and system behavior highlighted in WP1 for PWR. Moreover, the task will define the test matrix relevant for the experimental characterization on SIRIO facility, on the proposed upgraded configuration, for the PWR reference reactor technology. The test matrix will include operating parameters and operation procedures, defined by JSI with the support of SIET as facility operator, and will be based on the feedback received from WP1. The test matrix should also account for specific tests devoted to system code(s) validation needed for the activity scheduled on WP4.

Data Management Plan

The report consist in the plan for the management of the data produced in the project. The report describes the data management life cycle for the data to be collected, processed and/or generated. I willinclude information on: the handling of research data during & after the end of the project what data will be collected, processed and/or generated which methodology & standards will be applied whether data will be shared/made open access and how data will be curated & preserved (including after the end of the project).

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