Overview of INPRO SMR activities June 30, 2010

Transcription

1 Overview of INPRO SMR activities June 30, 2010 Randy Beatty INPRO Group Leader

2 Three Pillars of the IAEA

3 International Project on Innovative Reactors and Fuel Cycles (INPRO) Origins Established in 2000/2001 Authorized by IAEA General Conference resolutions Characteristics Membership based Funded mainly from extra-budgetary contributions 15 to 18 staff (mainly CFEs from Member States) at IAEA Headquarters International Project inside IAEA Cross-cutting with all relevant technical Departments involved 3

4 Objectives of INPRO Help assure that nuclear energy is available to contribute, in a sustainable manner, to meeting the energy needs of the 21 st century Provide a forum for discussion and cooperation of experts and policy makers from industrialized and developing countries on all aspects of sustainable nuclear energy planning, development and deployment Promote a mutually beneficial dialogue between technology holders and users Support national long range strategic planning and decision making on nuclear energy system development and deployment

5 Long-range NES Deployment Planning Concept of sustainable development Societal, Economical, Environmental, Institutional Aspects Energy system planning National, Regional, Global; covering all energy sources Nuclear Energy System Assessment (NESA) Covering all 7 areas of the INPRO methodology, for all components, cradle to grave Need for Sustainable Energy Supply Definition of the role of nuclear power in sustainable energy supply mix Follow up actions to achieve sustainable nuclear energy system

6 Number of INPRO Members INPRO Membership Members Algeria Italy Argentina Japan Armenia Kazakhstan Belarus Rep. Korea Belgium Morocco Brazil Pakistan Bulgaria Russia Canada Slovakia Chile South Africa China Spain Czech Republic Switzerland France Netherlands Germany Turkey India Ukraine Indonesia USA EC & Observers New in 2009

7 INPRO on the policy level IAEA General Conference Resolutions encouragement since 2000 Relevant statements in 20/20 report (2008) budget increase in NE by DG and GB G8 Summit (Global Energy Security, St. Petersburg, 2006) Complementary with GIF US Russia Strategic Framework Declaration (Presidents, US and Russia, 2008) support the IAEA Project INPRO that has brought together the states with developed nuclear technology, states running smallscale nuclear programmes and states just developing plans for peaceful use of nuclear energy. 7

8 2020 report by the Commission of Eminent Persons Recommendations that are relevant to INPRO (In the context of safety and sustainability) IAEA should support the trend towards standardized reactor design and the harmonization of a certification process IAEA should work more with states developing next-generation systems including through the INPRO programme

9 INPRO Program Areas Technical Program Areas A: Nuclear Energy Systems Assessments B: Global Vision C: Innovations in Nuclear Technology D: Innovations in Institutional Arrangements Cross-cutting E: INPRO Dialogue Forum INPRO Management F: Management, Coordination, Strategic Planning, Steering Committee, Outreach 9

10 Program Areas A: Nuclear Energy Systems Assessments (NESA) To support Member States in performing Nuclear Energy System Assessments (NESA) and to support long-term strategic planning and nuclear energy deployment decision making (including newcomer countries) using the INPRO methodology. B: Global Vision To develop global and regional nuclear energy scenarios using a scientific and technical basis that leads towards a shared world vision on sustainable nuclear energy development in the 21st century. C: Innovations in Nuclear Technology To foster collaboration among INPRO Member States on selected innovative nuclear technologies and related R&D that contribute to sustainable nuclear energy. D: Innovations in Institutional Arrangements To investigate and foster collaboration on innovative institutional and legal arrangements for the use of innovative nuclear systems in the 21st century and to support Member States in developing and implementing such innovative arrangements

11 Cooperation with International Orgs With the Generation IV International Forum (GIF) Participation in Policy Group as observer Participation in Working Groups Joint Action Plan in place 4 th coordination meeting March 2010 With the European Sustainable Nuclear Energy Technology Platform (SNE-TP) Interactions in planning and program development Other strategic partnerships and coordination with organizations like OECD/NEA and ISTC

12 Working with EC- SNETP IAEA/INPRO participates in SNETP Governing Board

13 INPRO and Sustainability Economic s Safety (Reactor) Proliferatio n Resistance Physical protection Sustainable NES Safety (Fuel Cycle) Infra structure Waste Management Environmen t

14 Common User Considerations (CUC) Activity Issues Cost information Role of suppliers Desirable NPP sizes Technology transfer Proven technology Report issued in 2009 Led to Dialogue Forum

15 Incentives for SMRs Today, the progress of SMRs is largely defined by their capability to address the specific needs of users Countries with small or medium electricity grids < MW(e) peak load Energy intensive (industrial) sites in remote off-grid locations (permanent frost, islands, remote draught areas, etc.) Countries with limited investment capability (attractive investment profile through incremental capacity increase) Replacement of fossil plants of similar size and infrastructure

16 Incentives for SMRs (con t) In the future, utilities (worldwide) need both electrical and commercial plants for non-electric energy services (ie aircraft, car and other mature industries) Primary energy (in developed countries) is utilized in three roughly equal fractions [*]: A third is used to generate electricity; A third is used in the transportation sector; A third is used for domestic and industrial heating. [*] World Energy Book 2005, World Energy Council:

17 Incentives for SMRs (con t) A variety of flexible and effective non-electrical application options (i.e., co-generation) Potentially, smaller emergency planning zone and proximity to the users Flexible and just-in-time capacity addition For small reactors without on-site refuelling: long refuelling interval and all operations with fuel outsourced

18 SMRs Recently Deployed/ Under Construction PHWR/ 692 MW(e) (Siemens design 1980s) Under construction in Argentina (Atucha-2, Buenos Aires, 2010/10/01) CANDU-6/ 650 MW(e) (AECL, Canada) Chernavoda, Romania, 2008/08/07 CNP-600/ 610 MW(e) (PWR, China) Two units under construction (Quinshan 2-3 and 2-4, 2010/12/28 and 2011/09/28) PWR/ 300 MW(e) (China) Under construction (Punjab, Pakistan, 2011/05/31) PHWR-220/ 202 MW(e) (NPCIL, India) Two units commenced in (KAIGA-4, 2008/07/31 and RAJASTHAN-5, 2008/06/30), one unit under construction (RAJASTHAN-6, 2008/12/01) PFBR-500/ 470 MW(e) (IGCAR, India) Under construction in India (TAMIL NADU) Floating NPP with two KLT-40S reactors/ 2x35 MW(e) (Rosenergoatom, Russia) under construction in St. Petersburg (Russia)

19 INFRASTRUCTURE DEVELOPMENTS OF BENEFIT FOR INNOVATIVE SMRs To increase deployment opportunities for SMRs several infrastructure innovations might be helpful, such as: Reciprocity of design certification and licensing agreements between countries Legal frameworks for fuel and reactor unit leasing International regimes for trade in nuclear technology (national commitments to international norms on safety, operation, liability, etc.) Insurance of fuel supply and/or securing increased guarantees of sovereignty to those MS that would agree to forego the development of indigenous fuel cycle Multinational legal arrangements for fuel cycle centers (forego indigenous infrastructure in exchange for guaranteed access)

20 SMRs - Options for Immediate Deployment Options are available: CANDU-6/ EC-6 (AECL, Canada) CANDU Plants at Bruce, ON PHWR-220; PHWR-540 (NPCIL, India), attractive capital cost of US$/kW(e) Calandria at manufacturer (L&T) shop PWRs: ~300 MW(e) (China) built in Pakistan; CNP-600 (China) built in China

21 Control rod drive Barrel RPV Steam generator (a) Core (b) Pressurized Water Reactors/ Integral Design PWRs Steam generator (a) (b) (c) IRIS Westinghouse, USA CAREM CNEA, Argentina SCOR CEA, France Reactor coolant pumps Venturi Pressurizer Decay heat removal system with integrated heat exchangers Integrated control rods Core (c)

22 Pressurized Water Reactors/ Marine Reactor Derivatives 1 Reactor 6,7 Pressurizers 2 Steam generator 8 Steam lines 3 Main circulating pump 9 Localizing valves 4 CPS drives 5 ECCS accumulator 10 Heat exchanger of purification and cooldown system Modular layout of the KLT-40S reactor plant (OKBM, Russian Federation). 6

23 High Temperature Gas Cooled Reactors/ Direct gas turbine (Brayton) FIG. XIV-2. Conceptual layout of the PBMR primary system [XIV-3].

24 SMR Projections From Recent Activities of IAEA s Planning and Economic Studies Section Summary: 22 countries in High Case and 10 countries in Low Case Installed Net Capacities (GWe) and number of the units Case by 2010 By 2020 by 2030 Units High Low

25 Legal and Institutional Issues of Transportable NPPs The objective of this activity: Study challenges for deployment of transportable SMRs with a focus on legal and institutional aspects but considering their economics and technical aspects and various deployment options related to ownership and contract Propose solutions and associated action plans to address the identified challenges

26 Transportable NPPs (TNPP) TNPP is defined as a transportable and/or re-locatable nuclear power plant, which is capable to produce final energy products like electricity or process heat on a regional basis A TNPP includes the nuclear reactor (with or without fuel) and the balance of the plant (e.g. steam generator, turbine) and fuel storage facilities if necessary A TNPP is physically transportable, but is not designed to produce energy during transportation nor provide energy for the transportation itself

27 TNPP Technical Options Ways of Transportation Water, railway, road/highway Siting Barge-mounted or ground-based Refueling scheme Conventional or without on-site refueling Factory assembly Reactor units to be delivered already assembled to the site but could be fueled onsite

28 Reference approaches Floating NPP Russian Federation Other concepts for small reactors are being developed within national and international programmes Brazil, India, Indonesia, Japan, Morocco, Republic of Korea, Russian Federation, Turkey, USA and others IAEA TecDocs 1451, 1485 and 1536 Present most available technological options for such reactors and also address issues for deployment

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30 TNPP Study / Options Study undertaken in INPRO, considering two options and three scenarios Option 1 (innovative) TNPP factory assembled, supplier factory fueled and tested, supplier factory maintained and refuelled or decommissioned, no on-site refueling, supplier takes back the spent fuel in reactor vessel Option 2 (existing legislative basis) TNPP factory assembled, factory pre-tested (nonnuclear tested), maintained, fueled and refueled onsite

31 TNPP Study / Scenarios Scenario 1 Supplier is operator, host state is regulator The supplier provides, operates and takes back the whole TNPP, including the spent fuel. The TNPP is operated by the supplier. The TNPP is regulated and licensed by the host state Scenario 2 Host country entity is operator, host state is regulator The supplier provides and takes back the whole TNPP, including the spent fuel. The TNPP is operated by an entity established by the host state. The TNPP is regulated and licensed by the host state Scenario 3 Supplier is operator, host state is regulator with technical assistance The supplier provides, operates and takes back the whole TNPP, including the spent fuel. The supplier provides technical assistance for regulation and licensing by the host state

32 Possible Benefits of TNPPs Reduced requirements for infrastructure, reduced associated costs The host state may require only limited facilities for the storage and management of fresh and spent nuclear fuel The TNPP site might be easily restored to a non-nuclear condition Production, delivery and commissioning faster than custom construction on site The investment cycle length and construction costs could be lower than for a land based NPP of the same capacity Regional service centres may help with maintenance (and refueling) National or regional centres may provide training to host state staff Decommissioning of TNPPs is provided by the supplier Availability of a TNPP could influence some countries making a decision to introduce nuclear power

33 Legal and Regulatory Issues acceptability of each of the proposed options and scenarios national nuclear legislation of vendor and recipient countries legal implications in case the plant is not solely transported through national territories waters sharing responsibility for liability and security compatibility of regulations in the supplier and host states new regulatory and licensing approaches responsibility for operation and supervision potential transport of a fuelled reactor emergency planning waste management applicability and adequacy of existing IAEA Safety Standards

34 Applicability of the existing safety standards It appears that the current IAEA Safety Standards are fully applicable. However this should be confirmed by a general detailed review of the standards in all areas It is necessary to determine if the existing requirements are sufficient and if additional dedicated safety guides are necessary. The existing experience on design, licensing and operation of reactors mounted on ships (ice breakers) and submarine can certainly provide useful information and should be collected.

35 Issues To Be Addressed Nuclear liability with specific reference to the transfer of liability during transport, and when a TNPP with fuel in the core needs to have international liability cover How the host state can meet its safeguards commitments if it is unable to access the fuel in the supplied TNPP. Security and physical protection of a fueled reactor and a reactor with used fuel during transport Regulatory responsibility of the host state for design, manufacture, construction and commissioning in the supplier state

36 Challenges of TNPPs Factory fuelling and zero-power testing with subsequent delivery of the assembled reactor to the user Shipment of the whole reactor with used fuel back to the factory for refurbishment, repair and/or refuelling Return of stabilized radioactive waste to the host country for long-term (final) disposal (not only for TNPPs)

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