On-going activities in Belgium in the field of FR & ADS, 2015 status

Transcription

1 On-going activities in Belgium in the field of FR & ADS, 2015 status Didier De Bruyn(), on behalf of the Belgian actors IAEA TWG FR&ADS48 th annualmeeting Obninsk (Russia), May 2015

2 MYRRHA engineering at, with current versions of Primary system Building design & plant layout Engineering work by FEED contractor Licensing activities R&D achievements at, including the collaboration agreements and the FP7 programmes Contents 2

3 MYRRHA is explicitly in the 2014 BE Gov. Declaration The Belgian Government will support in a progressive way the MYRRHA project or any equivalent project at aiming to continue the needed research for innovative solutions for High level waste, qualification of materials for fusion, the production of radioisotopes for medical applications in our country and fundamental nuclear research in collaboration with the universities and sister organisation of 3

4 Most recent design (1.6): view of reactor vessel & internals 4

5 Most recent design: Diaphragm 1/2 Main dimensions Outer diameter: 10 m Height: 10.3 m Bottom plate thickness: 80 mm Top plate thickness: 80 mm Shell thickness: 50/80 mm Penetrations thickness 30/50 mm PP&PHXcollars thickness: 50 mm Baffle thickness: 30 mm Support flange thickness: 50 mm Material : AISI316L Mass : About 320 t 5

6 Most recent design: Diaphragm 2/2 CC: Core Cradle (1) PP: Primary pump (2) PHX: Primary Heat Exchanger (4) IVFHM: In vessel fuel handling machine (2) FTC: Fuel transfer channel (2) FFDD: Failed fuel detection device (2) LBEi: LBE inlet (2) IVFSv: In vessel fuel storage valve (4) BPv: By-pass valve (12) 6

7 Horirontal section in the critical core Control rod Thermal spectrum IPS Reflector SA LBE dummy SA NTD Si Scram rod FA Fast Spectrum IPS 7

8 Vertical section in the Reactor building 8

9 The licensing activities have started in 2011 already The last reactor built in Belgium started in 1985, moreover fast reactor and LBE technologies are new for the safety authorities; In the first years (until 2016) we are in the pre-licensing phase, where we demonstrate that nuclear safety, security and safeguards aspects are in line with the design options; A series of focus points, specific to the innovative character of MYRRHA and that may impact the safety, have been identified and are currently been jointly evaluated; The structure of the Design Options and Provisions File (DOPF) has been developed by the authorities. Its purpose is to define the safety approach, security and safeguards are to be integrated. 9

10 Consequences for the FEED contract In order to fit with MYRRHA schedule constraints, priorities and objectives, we have reshuffled the supply of the FEED deliverables in 4 colored phases: Yellow phase (10/ /2015) : Top priority, should give direct answers to focus points and input to DOPF; work is concentrated on decay heat, confinement, radioprotection, LBE management, reactor design and nuclear buildings; Green phase (2015): Next needed to determine major cost drivers; Blue phase (2016): Needed to allow positive pre-licensibility statement, among others environmental and decommissioning reports ; Red phase (2016): All of the rest needed to cover full FEED scope. 10

11 However, this 1.6 version has to be revised too: R&D results put into question the design of the current HX concept double wall concept to be developed; Large vessel and component dimensions impact on cost and manufacturability. Vessel and component size reduction is envisaged; New optimized MYRRHA design by September 2015, With analysis of several options supported by dedicated studies; Consequently: FEED is suspended temporarily to prevent work that will become useless; Aim to restart FEED in September, after having defined the optimized MYRRHA concept and having updated the Functional Specifications of MYRRHA systems; R&D programs continues as foreseen. 11

12 Accelerator (MAX, MYRTE) R&D Topics and related European Projects Materials (GETMAT, MATTER, MATISSE) Fuel (MAXSIMA, MYRTE) LBE Technology Components & Experiments (THINS, SEARCH, MAXSIMA, ESNII+, MYRTE, SESAME) Chemical Conditioning Programme (SEARCH, MYRTE) Instrumentation & Control (CDT, LEADER, ESNII+, LCI) Computer code (FREYA, ARCAS, ANDES, MYRTE) Other EU Projects: Safety related experiments (THINS, SEARCH, MAXSIMA) Design & Licensing (SARGEN, SILER, CDT) 12

13 MYRRHA Linear Accelerator: R&D fields 13

14 R&D line Goals Test platform: experimentally address the injector design though prototyping tool for relevant reliability minded experience Main topics: Beam characterization CW operation of the 4-rod RFQ SS RF MHz 160kW Diagnostics for high current beams 3-tier Control System Long reliability runs 4-rod RFQ Principal partners: FP7-MAX H2020MYRTE Researchorganisations: CERN, CEA, IPNO, LPSC, IAP, UCL/CRC,, U Darmstad, industries: ACS, ADEX,EA,IBA, Thales ED, NTG, Pantechnik, Cosylab QWR CH1 CH2 CH3 CH4 Rebuncher CH6/7 CH8/9 CH10/ MeV 3.6 MeV 17.0 MeV 14 14

15 Role of materials research for development of MYRRHA Design tools: Nuclear manufacturing codes: RCC-MRx, Fuel codes FE calculations Design Construction Materials properties Data Missing data for MYRRHA: Basic characteristics of candidate materials Effects of LBE & irradiation on material properties Physical effects 15

16 Corrosion Corrosion loop CRAFT Corrosion program Qualification of the selected materials Establishment of service envelope Underlying mechanisms investigation CORRIDA loop Stagnant conditions set-ups Very low oxygen Controlled oxygen 16

17 Mechanical tests Qualification of the 316L & for application in LBE Development of procedures for tests in liquid metals Assessment of LBE effects on mechanical properties Underlying mechanisms investigation FP7 / H2020 projects 17

18 Set-ups for mechanical tests in LBE LIMETS 1 Tensile & Fracture toughness tests in LBE LIMETS 3 Fatigue tests in LBE LIMETS 4 Tensile & Fracture toughness tests in LBE Hot cell 12 & LIMETS 2 Tensile and FT tests of irradiated* steels in liquid metal *Licensed for α (Po) contaminated specimens 18

19 Irradiation of materials : LEXUR II, RIAR (Russia), BR2 Irradiation of MYRRHA candidate materials in LBE environment Layout of irradiation rig Irradiation rig Capsules holder Holder with pressurized tubes & corrosion specimens capsules Capsule with specimens for mechanical tests Capsule with pressurized tube Capsule with corrosion specimens 19

20 HELIOS 3 Purpose Delivery of conditioned LBE for experiments in labs Study of the feasibility of gas recirculation for conditioning of LBE Build-up of conditioning know-how for scale up to large facilities 20

21 HELIOS 3 layout Melting (40 litres LBE) Storage (120 litres LBE) Conditioning (20 litres LBE ) 3.8 m 21

22 Heavy metal lab R&D activitieson chemistryin LBE chemistry and control of dissolved oxygen in LBE oxygen sensor development evaporation spallation and fission products from LBE Capture of spallation and fission products 22

23 Heavy metal lab - R&D contaminant evaporation oxygen chemistry mercury evaporation & capture oxygen sensors oxygen control 23

24 MEXICO Loop Purpose To develop and verify oxygen control system with PbOmass exchanger, electrochemical oxygen pumps, filter and cold trap PbO [Pb] LBE + [O] LBE 24

25 MEXICO LBE loop over 3000 h of experiment time, kg LBE circulated pilotscale demonstration of oxygen control technologies: accurate & stable oxygen control of 7000 kg of LBE oxygencontrol ON MEXICO loop 25

26 Isothermal pool facility RHAPTER Mechanical component tests for in-lbe robotics Interchangeable test modules Specifications C 50 l LBE Vacuum or gas cover Drive axle and load axle Variable torque and rotation speed Instrumentation Torque sensor Position encoder Accelerometer Thermocouples Pressure gauge Status: in operation since September

27 COMPLOT COMPLOT = COMponent LOop Testing Hydraulic and hydrodynamic behaviour of components Purpose Characterisation of component behaviour Qualificationof CFDandFE tools Operational experience of LBE systems Characteristics Representing one fuel channel/ips at full height LBEas working fluid Isothermal loop Interchangeable test modules Partially funded by FP7 MAXSIMA 27

28 COMPLOT: Main characteristics Parameter Value Design Pressure (Bar) 16 Material Operational temperature range ( C) 316L Flow rate range (m3/h) Flow rate range (kg/s) LBE Volume (litres) ~ 800 Installed tracing (kw) 75 Isothermal loop Two vertical test sections representative of one fuel channel/ips at full height Up to 11 m in vertical height Large range of flow rates Pump variable speed drive Flow control valve Bypass line withpressurecontrol valve Inlet& outlet buffers Loop vs. pool Eliminate swirl and velocity profile variations Reduce transient pressures 28

29 COMPLOT: Status 29

30 E-SCAPE E-SCAPE = European SCAled Pool Experiment Thermal-hydraulic behaviour of a flowing liquid metal in a pool geometry Purpose Characterisation of pool T/H phenomena Qualification of CFD and system tools Operational experience on LBE systems Characteristics 1/6 geometrical scale factor LBE as working fluid Forced and natural circulation Partially funded by FP7 THINS 30

31 - SCKCEN PLEASE NOTE! This presentation contains data, information and formats for dedicated use ONLY and may not be copied, distributed or cited without the explicit permission of the. If this has been obtained, please reference it as a personal communication. By courtesy of. Studiecentrum voor Kernenergie Centre d'etude de l'energie Nucléaire Belgian Nuclear Research Centre Stichting van Openbaar Nut Fondation d'utilité Publique Foundation of Public Utility Registered Office: Avenue Herrmann-Debrouxlaan 40 BE-1160 BRUSSELS Operational Office: Boeretang 200 BE-2400 MOL