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Task 1.5.4 Containment Assessment

Task 1.5.4 Containment Assessment. IP-EUROTRANS DOMAIN 1 Design WP 1.5 Safety Assessment of the Transmutation System Design. Fission product confinement and control Protection against external events Biological shielding. Containment System Safety Functions.

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Task 1.5.4 Containment Assessment

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  1. Task 1.5.4 Containment Assessment IP-EUROTRANS DOMAIN 1 Design WP 1.5 Safety Assessment of the Transmutation System Design

  2. Fission product confinement and control Protection against external events Biological shielding Containment System Safety Functions

  3. Limitation of radionuclide releases Fission and spallation product removal mechanisms Containment isolation Leak tightness Containment integrity Structural behaviour Energy management system Fission product confinement and control

  4. Representative events selection DBC/DEC Definition of mass/energy releases Source term definition Definition of fuel damage extension Dose calculation. Different hypothesis Comparison with acceptance criteria Containment integrity requirements Containment Requirements

  5. DBC Primary HX tube ruptures Secondary coolant pipe breaks Cover gas system pipe break DEC Fuel sub-assembly blockage Representative events

  6. DBC conditions

  7. DEC conditions

  8. Relevant conclussions • High mass/energy release events not associated to DEC sequences • This allows to considering requirements for pressure relief separately from confinement requirements • Containment pressure relief system through a filtered venting system • Dose calculations to show compliance with acceptance criteria

  9. 10 % FUEL RODS FAILED (0.1 % during Normal Operation) EXCLUSION AREA BOUNDARY (EAB): 1000 m SOURCE TERM extrapolated from Superphenix MOX fuel LEAK RATE from containment: 1 % volume/day Acceptance criterion: DBC4  50 mSv (consequences have to be assessed for a long period – 50 years) Dose assessment

  10. Some credits that may be considered: Po WALL DEPOSITION Po TRAPPING (FILTERING SYSTEM) Po NON-VOLATILITY (% Po non-evaporated) I RELEASE-TO-CONTAINMENT FRACTION Cs DEPOSITION, FILTERING OR ANY OTHER WAY OF REMOVAL Credits

  11. Inhalation Dose Calculation equations Immersion Dose D(t): Dose after a given time t, [Sv] A’(t): Activity released from containment at a given time t, [Bq] FDC/FDT: Dose conversion factor for each radionuclide c/Q(t): Offsite atmospheric dispersion factor, [s/m3] BR: Breathing rate, [m3/s]

  12. Results * Mostly due to Cs

  13. Dose time-evolution for assessed cases

  14. Dose gets Safety Principles Limit for category 4 events (50 mSv) after 20 days in case 0 This limit has not been reached for any other cases during the 1st year Preliminary conclusions

  15. Update source term (which has been extrapolated from Superphenix reactor) in order to obtain more realistic results Further considerations about Po and Hg should be taken into account regarding chemical toxicity that have not been considered in these radiological dose calculations Objectives

  16. Subtasks definition Source Term Behaviour Subtask 1.5.4.2a Bounding definition of potential releases to the containment and its behaviour on the basis of the different source term information available from Work Package 1.5.3 and the above analyses Subtask 1.5.4.2b Fission products and Polonium transport mechanism will also be evaluated. Subtask 1.5.4.2c The potential dose to the operators and the environment from the above source terms will be calculated. Subtask 1.5.4.2d Recommendations, if required, for radioactive and fission product removal will be analysed.

  17. Subtasks definition Containment Requirements for the XT-ADS and EFIT Designs Subtask 1.5.4.3a Evaluation of containment function performance requirements for both designs, based on the data gathered from the above activities and WP 1.2 results Subtask 1.5.4.3b Evaluation of containment function taking into account the main features related to the following: Limitation of radionuclide releases (confinement function) Containment integrity Subtask 1.5.4.3c Evaluation of other features such as protection against external hazards, HVAC/Filtering requirements or biological shielding Subtask 1.5.4.3d Consideration of specific conditions that may be imposed on containment and confinement requirements

  18. Subtask Responsibilities The Task Partners are: KTH, FZK and EA The following split of responsibilities for the elaboration of Task 1.5.4 deliverables is proposed: Subtask 1.5.4.1a FZK Subtask 1.5.4.1b KTH Subtask 1.5.4.1c KTH Subtask 1.5.4.1d EA Subtask 1.5.4.2a FZK/KTH Subtask 1.5.4.2b FZK/KTH Subtask 1.5.4.2c EA Subtask 1.5.4.3a EA Subtask 1.5.4.3b EA Subtask 1.5.4.3c EA Subtask 1.5.4.3d EA

  19. Budget The assigned total budget allocation for Task 1.5.4 is as follows: EA 4 m/m FZK 4 m/m KTH 4 m/m

  20. CONTENTS 1. INTRODUCTION AND PURPOSE 2. INTERNATIONAL GENERAL DESIGN CRITERIA FOR CONTAINMENT 3. GENERAL SAFETY CRITERIA. CONTAINMENT CRITERIA 3.1 DEFENCE-IN-DEPTH 3.2 SAFETY FUNCTIONS 3.3 LINES OF DEFENCE (LOD) METHODOLOGY 4. GENERAL FUNCTIONS OF THE CONTAINMENT 4.1 CONFINEMENT AND CONTROL OF RADIOACTIVE PRODUCTS 4.2 PROTECTION AGAINST EXTERNAL EVENTS 4.3 CONTAINMENT ACCESIBILITY 5. BARRIERS AGAINST THE RELEASE OF RADIOACTIVE PRODUCTS 5.1 BARRIERS AGAINST THE RELEASE OF RADIOACTIVE PRODUCTS FROM THE FUEL 5.2 BARRIERS AGAINST THE EMISSION OF RADIOACTIVE PRODUCTS FROM THE TARGET 6. DESIGN BASIS CONDITIONS. CONTAINMENT DESIGN REQUIREMENTS 6.1 DESIGN BASIS CONDITIONS. LBE-COOLED XADS DESIGN 6.2 DESIGN BASIS CONDITIONS. GAS-COOLED XADS DESIGN 7. DESIGN EXTENSION CONDITIONS. REQUIREMENTS FOR THE DESIGN OF THE CONTAINMENT 7.1 CONTAINMENT HEAT REMOVAL SYSTEMS 7.2 LBE-COOLED XADS DESIGN 7.3 GAS-COOLED XADS DESIGN 8. SUMMARY OF CONTAINMENT DESIGN REQUIREMENTS 8.1 CONTAINMENT GENERAL ARRANGEMENT 8.2 CONTAINMENT HEAT REMOVAL 8.3 CONTAINMENT LEAKTIGHTNESS 8.4 STRUCTURAL DESIGN 8.5 CONTAINMENT ISOLATION 8.6 RADIATION PROTECTION 9. PENDING ITEMS 10. REFERENCES APPENDIX A TABLES APPENDIX B GENERAL DESIGN CRITERIA FOR CONTAINMENT IN AMERICAN, GERMAN, IAEA AND EUR STANDARDS B.1 CURRENT GERMAN CONTAINMENT FUNCTION-RELATED REGULATIONS B.2 CURRENT USA CONTAINMENT FUNCTION-RELATED REGULATIONS B.3 CURRENT EUROPEAN UNION REGULATORY CRITERIA B.4 CURRENT INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA) CRITERIA B.5 EUR CRITERIA RELATED TO CONTAINMENT FUNCTION B.6 KEY CRITERIA

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