Remote-Controlled Dismantling of the Thermal Isolation and Preparations for the Primary Shield Removal

Similar documents
Decommissioning and Dismantling of Prototype Reactors and Fuel Cycle Facilities at the German Karlsruhe Site Progress and new Challenges

RESEARCH REACTOR FRJ-1 (MERLIN) THE CORE STRUCTURES OF THE REACTOR BLOCK ARE DISMANTLED

Gerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany

DECOMISSIONING OF THE FORMER GERMAN REPROCESSING SITE WAK STATUS OF VITRIFICATION PLANT AND DISMANTLING OF THE HLLW STORAGE TANKS

Dismantling Techniques applied at MZFR

The WAK Decommissioning and Dismantling Project

Long Reach Tooling Solutions

Decommissioning of Dairyland Power s Lacrosse Boiling Water Reactor

SECURE LONG TERM STORAGE OF WASTE PRODUCTS AT THE KARLSRUHE RESEARCH CENTER

Progress Achieved in the Decommissioning of the Process Building of the Karlsruhe Reprocessing Plant

Waste Management of LLW / ILW at HDB

AREVA: Experience in Dismantling and Packing of Pressure Vessel and Core Internals

CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JÜLICH GMBH. H. Krumbach Forschungszentrum Jülich GmbH (FZJ) Jülich, Germany

Handling of Reactor Internals at Forsmark Nuclear Power Plant

Dirk Wegener*, Thomas Kluth** GNS Gesellschaft für Nuklear-Service mbh, Essen, Germany* Siempelkamp Nukleartechnik GmbH, Krefeld, Germany**

Dismantling of the Obrigheim NPP Reactor and Waste Management 14500

Disposal Of Spent Fuel In Salt Using Borehole Technology: BSK 3 Concept

Greifswald Project Introduction/Experience summary Axel Bäcker

Technology and Management for the Decommissioning of Nuclear Facilities

Miller Collective Safety at Height Solutions EPIC ULTRA Barrier System EPIC Post-N-Barrier System EPIC Basic Barrier System

Decommissioning of Nuclear Facilities. Dismantling Technologies

CHALLENGES FOR THE RADIATION PROTECTION DEPARTMENT IN THE SCIENTIFIC ENVIRONMENT OF A RESEARCH REACTOR LIKE FRM II

SNT location in Mülheim a breath of fresh air. Investments for the manufacturing center in Mülheim, Germany:

Characterization of Contaminated Stacks at Nuclear Facilities

K. Jayarajan Division of Remote Handling and Robotics Bhabha Atomic Research Centre

DISPOSAL OF THE CONTROL RODS OF THE EXPERIMENTAL AND RESEARCH REACTOR (FMRB) OF PTB, GERMANY

Installation Manual. Orion. TL-3 Steel Barrier. VHD (v2)

CONDITIONING OF OPERATIONAL AND DECOMMISSIONING WASTES AT THE KARLSRUHE RESEARCH CENTER

Lessons learned from ongoing decommissioning project of Fugen NPS

Design of Transport Container

Hans-Jürgen Blenski *, Steffen Oehmigen *, Frank Ambos **, Christian Gutland * GNS Gesellschaft für Nuklear-Service mbh ** sat.

lindab we simplify construction LindabSandwichPanels Installation instructions Mineral Wool Panels

RADIOACTIVE GRAPHITE MANAGEMENT AT UK MAGNOX NUCLEAR POWER STATIONS. G. HOLT British Nuclear Fuels plc, Berkeley, United Kingdom 1.

Minimizing Activation, Size and Costs and yet Maximizing Efficiency

WM2012 Conference, February 26 March 1, Phoenix, Arizona, USA

CEILING MOUNTED ARTICULATING JIB CRANE

Steam Generating Heavy Water Reactor SGHWR The final chapter

DISMANTLING THE WINDSCALE ADVANCED GAS COOLED REACTOR PRESSURE VESSEL AND INSULATION - DESIGN AND DEVELOPMENT

Mechatronics Courses by School Period

Automated Store Management For Drum Storage Facility

WM 03 Conference, February 23-27, 2003, Tucson AZ MLW, TRU, LLW, MIXED, HAZARDOUS WASTES AND ENVIRONMENTAL RESTORATION

The following considerations are taken into account for designing the NUHOMS MP197 packaging.

Experience from Fukushima 1F-3 Spent Fuel Removal System Project John Hubball Westinghouse Electric Company

TREATMENT AND STORAGE OF WASTE FROM THE DECOMMISSIONING OF THE WINDSCALE PILE REACTOR. D H Norton, Project Manager British Nuclear Fuels plc

F. BODIN 1, Ph. FOURNIER 1, L. MARTIN 2 1 COGEMA La Hague BEAUMONT HAGUE Cedex - France 2 SALVAREM BEAUMONT HAGUE Cedex - France

DISMANTLING OF A CONCRETE SHIELDED FACILITY

Brookhaven Graphite Research Reactor (BGRR)

Wälischmiller Engineering

An optimized cask technology for conditioning, transportation and long term interim storage of «End of Life» nuclear waste

Decommissioning Group Ketut Kamajaya

THE ROLE OF THE WORLD'S LARGEST INTERIM STORAGE FOR WASTE AND FUEL WITHIN THE DECOM PROJECT OF 6 WWER REACTORS IN GREIFSWALD AND RHEINSBERG (GERMANY)

SAMPLING AND RADIOLOGICAL ANALYSIS OF COMPONENTS OF THE TRIGA REACTOR AT THE MEDICAL UNIVERSITY OF HANNOVER

J. Kaulard B. Jünger-Gräf. Comparison of decommissioning options for the example of 2 research reactors of type TRIGA

Decommissioning three main strategies: Immediate dismantling, Safe enclosure (Deferred dismantling), Entombment

Installation and maintenance instructions for PLATIN and PLATIN XL Rainwater Underground Tank

The EnBW Strategyfor Decommissioningand DismantlingofNuclearPower Plants»

Combiforwarder Systems manual,rapid,regent,powerful

VMC Series Vertical Machining Centers PARTNER FOR YOUR METAL-CUTTING SOLUTION

FIG. 1. Fort St. Vrain Nuclear Generation Station.

WM2015 Conference, March 15-19, 2015, Phoenix, Arizona, USA

Installation Manual. DUO-GATE double. Containment level H2-W3-C in acc. with DIN EN

Schmidthammer. 06 High current carbon brushes. Elektrokohle GmbH. Transmission systems with linear adjustable telescope holders p.

DISMANTLING OF LARGE PLUTONIUM-CONTAMINATED GLOVE BOXES. H.-U. Arnold, DETEC (a NUKEM Company), Alzenau, Germany

PRR-1 Decommissioning: Preparing for Dismantling and Decontamination. R2D2 Project Meeting, Manila, Philippines September

A GERMAN RESEARCH PROJECT ABOUT APPLICABLE GRAPHITE CUTTING TECHNIQUES

TAKEN FROM A DOE TECHNOLOGY SUMMARY ON THE CONCRETE SHAVER DEMONSTRATED AT THE HANFORD SITE, RICHLAND, WA

Successful Hot Operation of the German Vitrification Plant VEK Results and Experiences Paper 11277

Economical paving of 4.0-m to 12.0-m wide concrete slabs Slipform Paver SP 1200

Metallurgy 101 (by popular request)

Restoration work for obstacle and upper core structure in reactor vessel of experimental fast reactor Joyo

Economic concrete distribution with stationary booms

Installation and maintenance instructions for GRAF rainwater storage tank, Carat-S series

RAPID Column Formwork For the highest requirements on concrete surfaces and edge formation. Product Brochure Issue 10/2017

Development Status of Dismantling Technology for Old Steam Generator & RV in Kori unit 1

3. Intermediate metal conduit (IMC). 4. Electric metallic tubing (EMT). 5. Flexible metal conduit (FLEX). 6. Polyvinyl chloride conduit (PVC).

Replacement Works for the Steam Generator and the Reactor Pressure Vessel Upper Head

Section 906. STRUCTURAL STEEL

Spherical Turbine with Skewed Axis of Rotation. Design Team

Electrochemical Die-Sinking (ECM) in Practice

SVAFO R2 Decommissioning Phase 1

MODEL 1051 TEM Mill ION MILLING. Ion milling is used on physical science. specimens to reduce thickness to electron

HIGH COST SAVINGS DUE TO THE SEPARATION OF CLEAN FROM CONTAMINATED CONCRETE AND CABLES

DURMAT PTA Welding Equipment: PTA Power Sources PTA Manual Torches, Robot Torches, Special Torches PTA Accessories

H neycomb TECHNOLOGY. Floor plates Innovation and Expertise

Benefits from R&D for D&D Projects 15089

RECYCLING OF URANIUM- AND PLUTONIUM-CONTAMINATED METALS FROM DECOMMISSIONING OF THE HANAU FUEL FABRICATION PLANT

Technical specification Slipform Paver SP 1600

Technical specification Slipform Paver SP 1500 / SP 1500 L

AP5K-C Precision AC Double-Pulse Spot Welding Machine User s Manual Shenzhen Will-Best Electronics Co., Ltd

TREPANING PROCEDURE APPLIED AT THE RPV OF THE FORMER GREIFSWALD NUCLEAR POWER PLANT

LIFT-AND-SLIDE DOOR 85 MM INSTALLATION GUIDELINES

MODELLING OF NUCLEAR POWER PLANTS DECOMMISSIONING TASKS ISSUES AND THEIR SOLUTION. Martin Hornáček, Vladimír Nečas 1

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA

Laser applications in nuclear power plants

Site Preparation... 2

1.6S PP SPUNBOND NONWOVEN PRODUCTION LINE. Ⅰ. Application

S.No Description Unit Quantity Rate (Rs) Amount (Rs)

PLASTIC FABRICATION. OUTPUT: Kg / h lb / h K-SB 20 K-SB 30 K-SB 40 R-SB Kg / h 11.2 lb / h. 3 Kg / h 6.6 lb / h. 4 Kg / h 8.

Additive Manufacturing

DPTE Transfer System Transfer materials without breaking containment

Transcription:

Remote-Controlled Dismantling of the Thermal Isolation and Preparations for the Primary Shield Removal A. Graf, J. Fleisch, S. Neff, WAK GmbH, Eggenstein-Leopoldshafen, Germany S. Klute, E. Koselowski, Siempelkamp Nukleartechnik, Heidelberg, Germany Introduction The compact sodium-cooled reactor facility KNK was an experimental nuclear power plant with 20 MW of electrical power output. Initially, between 1971 and 1974, the plant was operated with a thermal core and referred to as KNKI. Between 1977 and 1991, it was run with a fast core as KNKII. The reactor is currently being completely decommissioned down to green field conditions in ten permission steps according to the German Atomic Law. The current permission step nine includes dismantling the thermal isolation, removal and cutting of the primary shield and dismantling the activated parts of the biological shield. Afterwards, the remaining auxiliary installations such as ventilation systems or electrical components can be removed. This removal is necessary for the subsequent free measurement and release from the Atomic Act at the end of the dismantling project. After the release, the demolition of the building with its remaining built-in structures will be carried out. Dismantling of the thermal isolation At the current state of the KNK decommissioning project, all sodium has been removed from the reactor. Therefore the follow-on works can be done under normal dismantling conditions within a nuclear power plant. This means that only the activity and the corresponding dose rates as well as the building conditions need to be taken into consideration for the dismantling. Due to the activation during operations the existing dose rate demands a remote-controlled dismantling of the core internals and the activated part of the biological shield. The Co-60 activity of the thermal isolation is approximately 6 E11 Bq and that of the primary shielding is approximately 1.3 E13 Bq. In addition to the dose rate, the lack of space further complicates the decommissioning process. Figure 1 shows the setup of the remaining parts within the reactor core. Above the reactor core, an enclosure was constructed containing all the necessary tools such as cranes, manipulators and locking systems for the dismantling work. This enclosure was built for shielding and inerting. The inerting is no longer necessary since all sodium has been removed, but the necessity for shielding and avoidance of contamination spread still exists. Thus the enclosure needs to remain in place.

Thermal Isolation (ca.. 11 Mg) Primary Shielding (ca. 90 Mg) Activated parts of the biological shield (ca. 330 Mg heavy concrete, ca. 45 Mg steel) Fig. 1: Setup of the core internals such as thermal isolation, primary shield and the activated parts of the biological shield The reactor shaft of KNK is lined with a thermal insulation consisting of brickwork with a thickness of 160 mm (upper parts) and of 250 mm (lower parts), a 90 mm thick layer of mineral wool and a 0.5 mm thick steel liner fixed by steel bolts. The total mass of the thermal shield is approximately 11 Mg. The dismantling of these components is currently performed with a remote-controlled multi-purpose tool called WTS, provided by Siempelkamp Nukleartechnik GmbH. The WTS is attached to an existing crane above the reactor shaft. The electric and hydraulic lines use special multi-plug connectors on top of the machine which allow remote controlled couplings. In order to fasten the device securely within the reactor shaft, the WTS is equipped with two outriggers which can be pressed against the surrounding walls. The dismantling work is performed using a hydraulic manipulator system, positioned at the lower half of the machine. Several electric and hydraulic tools like a chipping hammer and an angle grinder are available which had to be adopted with handles and plug-in coupling suitable for remote controlled use. Two drums, positioned on a telescopic drum handling unit underneath the manipulator working zone are used to collect the dismantled material. Pivoted guiding plates above the drums ensure that more than 90% of the dismantled material is directly collected. In order to replace full casks with empty ones, the drum carrier unit can be uncoupled and docked automatically without manual interference. All security relevant actions are designed to be redundant, the main functions of this machine can be performed by two completely independent systems. For instance, in case of breakdown of an electric drive, the affected function can be taken over temporarily by a hydraulic motor.

The WTS is currently operated about 12 hours per day in two shifts and a large part of the thermal insulation has already been successfully dismantled. Fig. 2 Remote-controlled dismantling of chamotte brickwork and steel lining Preparation of the primary shield removal The primary shield of KNK consists of 12 cast iron segments, which are placed in a niche of the biological shield and surround the former reactor core. Their total mass is 90 Mg with a Co-60-activity of 1.3 E13 Bq with the heaviest segment having a mass of 15.5 Mg. The estimated dose rate is approximately 330 msv/h. This conditions demand a remote-controlled removal of the primary shield. Due to the restrictions caused by the enclosure and the compactness of the plant no standard tool could be used for the removal. Additionally, the distance between single segments is only about 5 mm and the maximum lifting height is about 3 cm. The dismantling of these elements will be performed by a remote-controlled multi-purpose tool called HWZ, provided by Siempelkamp Nukleartechnik GmbH. The HWZ is attached to the existing reactor crane, which has a maximum load capacity of 25Mg, thus limiting the admissible net operating weight of the HWZ. Also, the overall tool size is limited by the 2100mm diameter of the circular opening at the upper end of the reactor shaft. Due to these load and size restrictions, most parts of the machine had to be purpose-built. In order to attach the device to the reactor shaft, the HWZ is equipped with four outriggers which can be pressed against the surrounding walls. A custom-built machining device, positioned at the lower half of the HWZ, is used to drill two holes into each of the shield elements for further handling. As the surface of the shielding elements is curved, the elements initially have to be milled in order to produce a plane surface. Subsequently the two holes with a diameter of 110mm and a depth of 335mm are drilled

simultaneously. The semi-automatic machining device moves along three linear and two rotation axes to realize the complex movements required. All security relevant actions are designed to be redundant, the main functions of this machine can be performed by two completely independent systems. For instance, in case of breakdown of an electric drive, the affected function can be taken over temporarily by a hydraulic motor. To hoist the elements out of the reactor shaft, the HWZ is equipped with clamping mandrels. These tools can be inserted into the drilled holes and then tightened inside, thus achieving a firm connection with the cast iron components. The dismantling process described above is currently tested in a mock-up of the reactor shaft. During this trial operation a replication of the heaviest element (16.6Mg) has already been successfully machined and hoisted out of the mock-up. Fig. 3: Drilling and lifting up of the primary shielding segment in the mock-up

Summary The remote-controlled dismantling of the thermal isolation and the removal of the primary shield within a compact nuclear research reactor cannot be done with standard tools. Special custom-built tools and systems are required, prototypes have to be designed, constructed and tested before their final adoption. The smooth progress of the remote-controlled dismantling of the thermal isolation proves that the advance testing of the prototype tools is both necessary and efficient. Even with the existing restrictions due to dose rate, compactness and additional enclosure, a secure and fast dismantling process could be realized with very low down times. The dismantling of the primary shield is the next challenge on the way to green field status. The first test results of the HWZ tool in the reactor mock-up show that the current plan for removing the segments is feasible.