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1 KRB-A (Grundremmingen, Germany). 2 Type:Boiling Water Reactor Power: 250 MW(e) Started in 1966, shut down in 1977 First commercial power reactor in.

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Presentation on theme: "1 KRB-A (Grundremmingen, Germany). 2 Type:Boiling Water Reactor Power: 250 MW(e) Started in 1966, shut down in 1977 First commercial power reactor in."— Presentation transcript:

1 1 KRB-A (Grundremmingen, Germany)

2 2 Type:Boiling Water Reactor Power: 250 MW(e) Started in 1966, shut down in 1977 First commercial power reactor in the Federal Republic of Germany KRB-A General Description

3 3 KRB-A Layout

4 4 KRB-A Project Summary 1977: reactor shut down 1980: decommissioning planning 1983: phase I: removal of components and systems in the turbine house 1990: phase II: decommissioning of primary circuit 1992-date: phase III: dismantling of RPV, internals and biological shield 2005: complete reactor removal

5 5 KRB-A Operational lessons learned The use of chemical decontamination to minimise waste for disposal Ice sawing technique successfully used to stabilise and cut through tube bundles Thermal cutting is flexible and reliable Mechanical tools are simple to handle

6 6 KRB-A General learning points No single dismantling tool Avoidance of complicated techniques Clearly defined waste management process

7 7 KGR (Greifswald,Germany)

8 8 Type:8 Pressurised Water Reactors Power: 440MW(e) each Four reactors operational between 1973 and 1990 Reactor units based on Russian WWER design, three reactors never commissioned, one test operation KGR General Description

9 9 KGR Project Summary 1989-90: units 1-5 shut down and construction of units 6-8 halted 1995-2009: dismantling of equipment, units 1-5 1998: start of Interim Storage North (ISN) operations 1999-2002: demonstration remote dismantling, unit 5 2004-2007: dismantling of reactor and internals, units 1-4 2012: completion of reactor buildings demolition

10 10 KGR Site re-use Harbour construction works at the former cooling water outlet channel

11 11 KGR Progress Percent dismantling complete (by mass) as at May 2004 Unit 171% Unit 273% Unit 316% Unit 466% Unit 580% Turbine hall51% Removal of large components to the ISN for decay storage RPV (214Mg) Steam generator (166Mg)

12 12 KGR Waste management Total mass site decommissioning waste 1,800,000 Mg Radiologically unrestricted material 1,233,600 Mg Other radioactive residuals 566,400 Mg Remaining building structures 471,200 Mg Concrete for radioactive waste or decay storage 26,000 Mg Dismantling plant parts 69,200 Mg Unrestricted release 511,100 Mg Restricted re-use 2,500 Mg Conventional waste 3,750 Mg Decay storage 28,400 Mg Radioactive waste 16,500 Mg Controlled re-use in nuclear facilities 4,150 Mg Sorting, packaging and buffer storage

13 13 KGR Operational lessons learned No specific problems Development of a comprehensive inventory Use of simple, sturdy equipment Complete planning - shut down to disposal ALARA principle

14 14 KGR General learning points Challenge to project management and logistics Social aspects - strategy for site re-use Clear and realistic requirements from the licensing authority Open dialogue with the public

15 15 NPP-A1 (Jaslovske Bohunice, Slovakia) ReactorPrimary circ.Turbocompressors Turbines Steam generators Long term spent fuel store Refuelling machine in reactor hall

16 16 Type:Heavy Water Gas Cooled Reactor Power: 143 MW(e) Started in 1972, shut down in 1977 Experimental and power prototype reactor for the development of gas cooled, heavy water moderated reactors using natural uranium. NPP-A1 General Description

17 17 NPP-A1 Project Summary 1977: reactor shut down 1980-94: transition period 1999: all spent fuel transported to Russia 1999-2007: first decommissioning phase 2008-2033: final decommissioning

18 18 NPP-A1 Operational lessons learned Decommissioning greatly influenced by reactor history (accidents) and fuels and liquid waste storage issues Successful co-operation with European companies Use of operational staff knowledge Clear definition of waste management routes and process requirements Carrying out activities in small steps with small teams

19 19 NPP-A1 General learning points Maintaining fuel cladding integrity during operation Co-operation between project managers, technicians, health physicists and regulators

20 20 Summary of lessons learned(1) Initial characterisation Impacts cost, schedule, decontamination strategy, waste managaement

21 21 Summary of lessons learned(2) Tools and equipment Simple, appropriate, tested, commercially available where possible manual > remote develop contingency solutions and tooling consider effect of aging

22 22 Summary of lessons learned(3) Operational management remove debris promptly and in a controlled way consider effect of temporary systems on existing systems establish a fit for purpose working environment

23 23 Summary of lessons learned(4) Risk management prioritise take a total risk approach avoid creating new hazards consider non radiological and radiological hazards equally risk assessment/management must be an ongoing process

24 24 Summary of lessons learned(5) Waste management plan all operations minimise production of wastes e.g. segregate wastes at source do not generate a waste stream until a disposal strategy has been defined adequately consider effect of decontamination techniques on secondary waste generation, cost, worker health and safety

25 25 Summary of lessons learned(6) Staff experience make use of available expertise maintain team continuity where possible small experienced teams are generally more effective

26 26 Summary of lessons learned(7) International collaboration benchmarking exchange agreements - sharing technologies and experiences

27 27 Summary of lessons learned(8) Stakeholder involvement openness and transparency develop mechanisms for consulting and dissemination of information

28 28 Questions?

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