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WP3: Plant Requirements (EA)


After a careful revision of the information coming from 5th and 6th Framework Programme, this work package will be aimed to perform the required auxiliaries or 'balance of plant' studies. These studies will comprise all the FASTEF facility infrastructures, except the primary and secondary systems, spallation loop, accelerator and the beam line.
This study will result in a comprehensive functional description complemented with the characteristics, and main technical requirements, of the auxiliaries to fulfil all plant functions and requirements for both the sub-critical and the critical options as well as in an overall plant layout. In this study site specific conditions related to the Mol-site will be taken into account.

Every resultant deliverable will contain a description of the work, conceptual Process & Instrumentation Diagrams (P&IDs) and drawings, required calculations an a conceptual specification of the involve systems (except for the overall layout, which will only include description and drawings).
This WP will also include a specific task on I&C for subcritical & critical mode operation. In this task, the necessary instrumentation for the nuclear island and accelerator will be identified. The necessary reactor control and scram logic and interlocks will be also defined.

Description of work

The Work package is subdivided in six tasks as follows:
T 3.1. Reactor building (EA, SCK•CEN,SENER, OTL)
The objective of this task is to define the requirements and criteria applicable to the reactor building, including containment, and to define it preliminary as input for the containment analysis.
The impact on the Reactor Building design of the different refuelling, maintenance and manipulations strategies will be assessed. The impact of the different location of seismic isolators will also be assessed if needed.
The following aspects will be specifically addressed in this task:

• Reactor (containment) building
• Reactor component maintenance (contaminated (with Po), activated) and robotics
• Experimental devices (out of pile hot cells, dismantling of devices)
• Manipulations (overhead cranes, …)

EA will carry out the basic design of the reactor building containment, considering several options. Containment requirements definition needs information from the analysis of design basis events and design extension condition to take into account conditions imposed by the different events considered in the design.

This activity should go through all analysed events in order to find a set of bounding conditions to be taken into account in the definition of containment requirements based on currently used design codes & standards (with possible extensions) and in the near future comply with the EUR requirements.

EA will integrate in the design the experimental devices the remote handling equipment and manipulators.
The calculation of the seismic response spectra at the most critical components location shall be performed taking into account the site seismic input.

SCK•CEN, OTL and EA will detail reactor component maintenance (contaminated (with Po), activated) and robotics.
SCK•CEN will assess experimental devices as out of pile hot cells and dismantling of devices. SCK•CEN will contribute also by developing an installation procedure.

SCK•CEN and EA will assess the dimensioning and location of cranes and other manipulation devices
SENER will contribute as a document reviewer.

T 3.2. Fuel handling systems (EA, SCK•CEN)
The following aspects will be specifically addressed in this task:

• Fresh fuel handling (reception, storage, fuel transfer systems)
• spent fuel handling (fuel transfer system from reactor, intermediate storage, decontamination (Pb, Po), long-term storage on-site, evacuation)
EA will design and optimize the reception, storage and transfer of fresh fuel facilities and procedures, as well as the corresponding activities for the spent fuel: fuel transfer system from reactor, intermediate storage, decontamination, long term storage on-site and finally, evacuation.
Under this task EA will provide a pre-dimensioning of the storage facilities and radwaste building, as well as the requirements for the fuel storage pools/compartments and handling equipment.
SCK•CEN will provide its point of view with focus on the installation procedures.

T 3.3 Radiological infrastructure (EA, SCK•CEN)
The following aspects will be specifically addressed in this task:
• Radioprotection: zone separation, radiation monitoring, shield calculations
• Decontamination: personnel, material, waste
• Radioactive waste handling systems: solid waste, effluent waste
• Hot cells requirements and conceptual design
EA will be responsible of the definition of the systems for radioprotection, decontamination, hot cell requirements and radioactive waste handling (solid waste and effluent waste). These tasks will include the definition of zone separation, instrumentation necessary, and personnel.
SCK•CEN will assess the different options developed by EA in order to guarantee the feasibility and installation of the different systems and will review the documentation generated. In particular SCK•CEN will evaluate the optimization of the hot cells requirements.

Task.3.4 Auxiliary systems (EA, SCK•CEN, SENER)
The following aspects will be specifically addressed in this task:
• Primary Coolant Cleanup support system(s)
• Water infrastructure (source, process, storage, water lines purification, drinking water,…)
• Compressed air infrastructure
• Cryogenics
• Vacuum system
• Non-radioactive effluents (collection, treatment and evacuation)
• All cooling systems (beyond the secondary circuits): tertiary cooling, [non-]nuclear auxiliaries cooling
• Ventilation systems (nuclear zones, non-nuclear zones, filters, vanes, treatment, over/underpression,…)
• air conditioning system (control room, cells, offices)
• offices heating
EA will develop the effluent infrastructure, including water, compressed air, cryogenics, vacuum system and non-radioactive effluents (collection, treatment and evacuation). In addition, EA will define all the tertiary cooling and all non-nuclear auxiliary cooling systems.
SCK•CEN will assess the different options developed by EA in order to guarantee the feasibility and installation of the different systems and will contribute as document reviewer
SENER will design ventilation, air conditioning and heating systems and will contribute as document reviewer.

Task 3.5. Overall plant layout (EA, SCK•CEN, SENER)
The objective of this activity is to define the civil works and the overall plant layouts integrating the containment as input for the cost estimation.
The general arrangement drawings will be developed with sufficient level of detail to include:
• Plot plan (site mapping with layout of the buildings)
• General arrangement definition (including technical equipment)
• Interconnection between buildings (roads, underground suppliances)
• Main handling equipment
• Fresh and spent fuel storage pools
• Shielding preliminary requirements & ALARA review
• Site fencing and physical protection infrastructure
• Structural/civil design requirements (Containment and Nuclear buildings)
• Site requirements
EA will be responsible of the design of the overall plant layout.
SCK•CEN will support EA in the location of the main technical equipment and experiments interfaces optimization.
SENER will contribute as document reviewer.
Task 3.6. Instrumentation and Control (SENER, CNRS, ADEX, SCK•CEN)
WP2 task 2.1, 2.2 and 2.3 will provide the important parameters for control, safety and design verification and the space limitation for the desired measurements. These to be measured parameters, like neutron flux, temperature, flow, level, pressure, chemical composition etc., have to be listed and the range must be defined. Existing devices will be selected or development needs will be defined for the necessary sensors. During the selection process, aspects such as space limitations, effects on the core (nuclear and thermo-hydraulic) and compatibility with the measurement environment (temperature, fluid, radiation) are included. For this analysis, a comparison with instrumentation of past and existing fast reactor systems will be performed.
In subcritical-configuration, the measurements of the accelerator and the beam guide equipment should be considered. This includes the specialised transducers for control and diagnostics, and the more classical instrumentation for the auxiliary equipment of the accelerator such as the e.g. ion-pumps and cooling-equipment. Especially, in this task, a list of accelerator signals will be made which are relevant for the FASTEF control and its safe operation. In addition, specific instrumentation for the coupled working mode with the spallation target has to be foreseen.
In this design it is necessary to integrate the relevant measurements of the nuclear island, the accelerator in case of the subcritical FASTEF and some relevant other signals defined in WP3. The different alarms and safety actions have to be worked out. An overall logic for alarm and scram signals has to be established.


D3.1 Containment system requirements(EA) (M24)
D3.2 Fuel handling requirements (EA) (M24)
D3.3 Radiological infrastructure requirements (EA) (M24)
D3.4 Auxiliary systems requirements(EA) (M36)
D3.5 Overall plant layout (EA) (M36)
D3.6 Instrumentation and control (SENER) (M36)