1. INPRO Assessment of Safety of Innovative Nuclear Reactors and Fuel Cycle Facilities INPRO Assessment of Safety of Innovative Nuclear Reactors and Fuel Cycle Facilities Y. Busurin, B. Kuczera, IAEA CM on Analysis of User Requirements for the Establishment of INPRO Data Base, VIC, 30 Nov.-2 Dec. 2005

2. International Atomic Energy Agency 2 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO Table of Contents General features of INPRO methodology INPRO’s requirements in the area of safety –Innovative Nuclear Reactor Designs –Innovative Nuclear Fuel Cycle Facilities

3. International Atomic Energy Agency 3 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO Hierarchy of Demands on Innovative Nuclear Energy Systems (INS) INPRO Hierarchy of Demands on Innovative Nuclear Energy Systems (INS) Criterion consists of an Indicator (IN) and an Acceptance Limit (AL) Basic Principle (BP) 1 User Requirement (UR) 2 Criterion 3 b b a a a = Derivation of hierarchy b = Fulfilment of demands 1 ~ Goal in GIF 2 ~ Criteria in GIF 3 ~ Metrics in GIF = rule to guide RD&D = conditions for acceptance of User = enables judgement of potential of INS

4. International Atomic Energy Agency 4 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO General features of the INPRO Methodology General features of the INPRO Methodology INPRO Methodology (i.e. BPs, URs, INs and ALs) for the assessment of an INS is nuclear technology independent. INPRO Methodology provides guidance on how to apply these requirements in evaluating a given INS, taking into account local, regional and global boundary conditions of both, developing and developed IAEA Member States.

5. International Atomic Energy Agency 5 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO General features of the INPRO Methodology General features of the INPRO Methodology  Uranium/ Thorium Mining and Milling  Uranium Refining and Conversion  Uranium Enrichment  Fuel Fabrication  Nuclear Reactor  Spent Fuel Storage  Spent Fuel Reprocessing including MA partitioning  Re-fabrication including MA fuels and targets  Radioactive Waste Management  Waste disposal  Decommissioning  Transportation In the framework of INPRO, an INS includes the following components:

6. International Atomic Energy Agency 6 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO Basic Principles in the Area Safety of Nuclear Installations INPRO Basic Principles in the Area Safety of Nuclear Installations (IAEA-TECDOC-1434) Four Basic Principles (BPs): Innovative Nuclear Reactors and Fuel Cycle Installations shall: 1.Incorporate enhanced defence-in-depth; 2.Incorporate increased emphasis on inherent safety and passive features to minimize or eliminate hazards; 3.Be so safe that they can be sited in locations similar to other industrial facilities used for similar purpose; 4.Provide confidence based upon experience or appropriate RD&D. From these BPs 14 User Requirements and 38 Criteria have been derived.

7. International Atomic Energy Agency 7 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO Basic Principle BP1 on Safety INPRO Basic Principle BP1 on Safety BP 1: Installations of an INS shall incorporate enhanced defence-in-depth as a part of their fundamental safety approach and ensure that the levels of protection in defence-in-depth shall be more independent from each other than in existing installations. –UR1.1: Installations of an INS should be more robust relative to existing designs regarding system and component failures as well as operation. –UR 1.2: … –UR 1.3: …

8. International Atomic Energy Agency 8 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO Needs for an INPRO Manual Needs for an INPRO Manual Feedback from six national and eight individual Case Studies; For the assessment of an INS, the INPRO Manual shall: –Provide more background information on INs and ALs; –Provide, where appropriate, advice for INs and ALs to be quantified; –Provide some illustrative examples which may facilitate the actual determination of INs and ALs.

9. International Atomic Energy Agency 9 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO Different Manuals for Reactor Safety and Safety of Nuclear Fuel Cycle Facilities (NFCFs) Different Manuals for Reactor Safety and Safety of Nuclear Fuel Cycle Facilities (NFCFs) Differences between reactors and NFCFs: The reactor core of an NPP contains a very large inventory of radioactive material at high temperature, pressure, and within a relatively small volume; an NFCF operates at near ambient pressure and temperature. In NFCFs, the development of accidents is rather slow except in the case of criticality. High importance of NFCF ventilation systems in maintaining their safety functions, even under normal operation, due to direct contact of materials with ventilation or off-gas systems. A greater diversity of NFCF processes. In these processes use large quantities of hazardous chemicals are used which can be toxic, corrosive and/or combustible.

10. International Atomic Energy Agency 10 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO User Requirement UR1.1 on Reactor Safety INPRO User Requirement UR1.1 on Reactor Safety Example: Indicator of UR 1.1 IN1.1.1 Robustness of a nuclear reactor Increase of robustness can be achieved by a number of variables (e.g. improved materials, increased operating margins, extensive use of passive systems etc.) For an operating NPP, the level of robustness can be quantified via PSA by frequencies of relevant operation disturbances and initiating failures. For an INS, these PSA event frequencies represent Acceptance Limits not to be exceeded.

11. International Atomic Energy Agency 11 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO Example from INPRO Manual on Reactor Safety Example from INPRO Manual on Reactor Safety Operating BWR (Gundremmingen B)Innovative BWR (SWR 1000)

12. International Atomic Energy Agency 12 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO Manual : Risk Reduction Through Innovative Safety Improvements in Reactor INPRO Manual : Risk Reduction Through Innovative Safety Improvements in Reactor. Event Consequences (Damage, Dose) Event Frequency Accident frequency of an operating NPP Accident frequency of an innovative NPP improved relative to current plants

13. International Atomic Energy Agency 13 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO User Requirement UR1.5 on Reactor Safety INPRO User Requirement UR1.5 on Reactor Safety Example: UR 1.5 - No need for evacuation UR 1.5 demands that, for INS, there is “no need for evacuation and relocation measures” – even in case of severe accidents; Major release of radioactivity into the environment can be calculated using PSA, but the split of frequencies between core damage and claimed containment failure may be different for different NPP types (e.g. in water- cooled plants and gas-cooled plants); For UR 1.5, the INS Acceptance Limit is fulfilled if: –The predicted release frequency is less than 10 -6 per reactor operating year, or –Practical exclusion by design can be demonstrated.

14. International Atomic Energy Agency 14 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO Safety Issues of Nuclear Fuel Fabrication Facilities The variety of nuclear fuel types corresponds to the variety of nuclear reactors. Criticality accidents and the accidental release of hazardous materials are the major safety issues. In case of enriched U/Pu mixed oxide, special care to be taken to minimize contamination. Shielding may be needed for protection of the workers due to higher gamma dose rates.

15. International Atomic Energy Agency 15 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO User Requirement UR1.1 on Safety of Fuel Fabrication Facility INPRO User Requirement UR1.1 on Safety of Fuel Fabrication Facility Example: Indicator IN1.1.1 of UR 1.1 – Robustness of fuel fabrication facility Increase of robustness can be achieved by a number of variables : Passive cooling systems for high temperature operation; Provision of sub-atmospheric pressure in process enclosures and operating areas; Use of safe geometry in equipment layout to prevent critical mass configurations; Minimization of hydrogenous materials in process and use of neutron absorbing materials are necessary for criticality control For every type of facility, events AL have to be identified and frequency & grace time specified, based on expert opinions and operating experience.

16. International Atomic Energy Agency 16 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO Safety Issues of Reprocessing Facilities Safety Issues of Reprocessing Facilities The large inventory of radioactive materials stored is a major cause of concern. The radioactive materials in process are in dispersible forms, and are subjected to vigorous chemical and physical reactions. Hence containment and off-gas cleanup ventilation systems play an important role. The major safety concerns: Criticality due to unsafe accumulation of fissile material inside the geometrically unsafe process equipment or cell Red oil explosion caused by violent TBP-nitric acid reaction and subsequent rapid pressurization (typical place of occurrence: HLW evaporator or Pu evaporator) Consequent radioactive contamination, internal and external radiation exposure

17. International Atomic Energy Agency 17 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO INPRO User Requirement UR1.1 on Safety of Reprocessing Facility Example: Indicator of UR1.1 Robustness of a reprocessing facility (simplicity, margins) Increase of robustness can be achieved by a number of variables such as : Lower frequencies of failures; Prevention against criticality; Plant availability factor; Grace time. For every type of facility, processes and events, ALs have to be identified and frequencies of failures and grace time specified, based on expert opinions and operating experience.

18. International Atomic Energy Agency 18 20 September, 2005Busurin /Kuczera, GIF-IAEA-INPRO Present Status in the Area of Safety The INPRO Manual Chapter on nuclear reactor safety, after an internal review, has been provided (as a stand alone version) to Member States that are performing an assessment studies. The INPRO Manual Chapter on safety of nuclear fuel cycle facilities is in an internal review process to be provided to those Member States.