Decommissioning of Dairyland Power s Lacrosse Boiling Water Reactor

Size: px
Start display at page:

Download "Decommissioning of Dairyland Power s Lacrosse Boiling Water Reactor"

Transcription

1 Decommissioning of Dairyland Power s Lacrosse Boiling Water Reactor

2 Dairyland Power Cooperative The plant achieved initial criticality in July, Full power was reached in August, 1969 and was declared for commercial use in February of The plant was permanently shut down in April of 1987 and placed in SAFSTOR for decommissioning at a later date. Due to the pending closure of the disposal site for the reactor vessel, decommissioning was started in 2005.

3 The Decommissioning Challenge An experienced decommissioning team was selected to provide design engineering and on-site decommissioning services to remove the reactor vessel and ship to the disposal site. Bluegrass Concrete Cutting, Inc was responsible for providing access for the vessel removal. Four major activities were required to provide the required access including: 1.Cutting an opening in the reactor containment building. 2.Segmentation and removal of the reactor shield plugs. 3.Cutting for removal a section of the biological shield wall surrounding the vessel. 4.Cutting free from the vessel the reactor nozzles, control rod drive tubes and all other vessel attachments. Of significant concern for the project was the spent reactor fuel that was still contained in the spent fuel pool located approximately 2 meters from where some of the work would take place.

4 Cut An Opening in the Reactor Containment Building The initial activity was to cut an opening in the containment building of sufficient size for the reactor vessel to pass through. The containment wall consisted of 9 (230 mm) of concrete, a small air gap and a 1 (25 mm) steel plate. The opening to be cut was 60 feet (18 meters) high and 16 feet (4,870 mm) wide.

5 Cutting An Opening in the Reactor Containment Building Diamond core drilling for diamond wire access. Diamond wire saw set up for cutting of containment opening. The use of diamond tools was critical to maintaining required tolerances and to smoothly cut through the steel plate liner and refractory bars.

6 Cutting An Opening in the Reactor Containment Building The access opening for removal of the reactor vessel was cut through the reactor containment building wall in eight separate sections.

7 Removal of Reactor Containment Building Wall Access Opening would eventually be 60 feet high by 16 feet wide.

8 Cutting and Removal of Reactor Shield Plugs The reactor shield plug consisted of three separate plugs approximately 1 3 (380 mm) thick and 15 (4,570 mm) in diameter made from high density concrete and lined with steel plate. Each of the three plugs was cut into six sections each with a diamond wire saw for sufficient size reduction to fit through the very small containment hatch opening.

9 Segmentation and Removal of Reactor Plugs The reactor shield plug consisted of three separate plugs made from high density concrete and lined with steel plate. The plugs were housed for cutting and sectioned into six sections each.

10 Removal of a Portion of the Bio Shield Wall Access to the reactor vessel meant removing a significant portion of the bio shield wall.

11 Removal of a Portion of Bio Shield Wall Access to the Bio Shield required removal of sections of the operating floor and support beams.

12 Removal of a Portion of Bio Shield Wall The biological shield wall had significant challenges due to very tight tolerances. Precise wire access and rigging holes had to be diamond core drilled at compound angles through up to 10 feet (3,650 mm) of concrete and steel plate in order to penetrate the circular edge of the shield wall without touching the vessel. With precision layout and specially designed angle brackets all holes were drilled in the proper orientation. Cutting then proceeded from the top down, cutting the shield wall into 20 ton sections. In all, 23 separate sections of biological shield wall were cut and removed to provide access for the vessel removal.

13 Removal of a Portion of Bio Shield Wall Drawing of the (23) sections of bio shield wall to be removed.

14 Removal of a Portion of Bio Shield Wall Access through Bio shield wall would require 23 individual sections to be cut and removed.

15 Removal of a Portion of Bio Shield Wall View of concrete core, with liner plate attached, illustrating the compound angles required to penetrate the circular shield wall, while not touching the reactor vessel.

16 Removal of a Portion of Bio Shield Wall Typical diamond wire saw setups required to reach cuts with limited access.

17 Removal of a Portion of Bio Shield Wall Diamond wire saw set-ups for sectioning bio shield wall into pieces small enough to fit through the small containment hatch opening.

18 Removal of a Portion of Bio Shield Wall Core drilling of biological shield wall. View of a section of biological shield wall after cutting with rigging attachments installed for lifting and removal.

19 Sectioning and Removal of the Bio Shield Wall The biological shield wall that had to be cut in unusual shapes in order to provide clearance for the reactor vessel.

20 Sectioning and Removal of the Bio Shield Wall

21 Sectioning and Removal of the Bio Shield Wall The tight tolerances and the curved inside edge of the biological shield wall required precision cuts.

22 Sectioning and Removal of the Bio Shield Wall Section of biological shield wall wrapped and ready to be removed from containment.

23 Cutting Reactor Nozzles, Control Rod Drive Tubes and All Other Vessel Attachments. The last item was to cut all nozzles pipes and other welded attachments from the vessel at precise tolerances so the vessel would fit in the transport package. In all, there were 10 steam and recirculation inlet and outlet nozzles, 29 stainless steel control rod drive tubes, 2 large support trunions and 25 other smaller nozzles of various size and materials. The recirculation inlet and outlet nozzles along with the control rod drive tubes were especially difficult due to very limited access and high radiation and contamination levels. Special brackets were fabricated to guide the diamond wire through the maze of pipes. Controls were located remotely to keep exposures to a minimum. The diamond wire successfully cut every nozzle and metal attachment eliminating any need for thermal cutting.

24 Cutting Reactor Nozzles, Control Rod Drive Tubes and All Other Vessel Attachments. Note the limited space available to access cutting of the control rod drive tubes. Additional challenges included the requirement to cut the control rod drive tubes flush to the bowl shaped bottom of the vessel so the vessel would fit into its specially designed transport package.

25 Cutting Reactor Nozzles, Control Rod Drive Tubes and All Other Vessel Attachments. Very limited access was available for installation of equipment and guide pulleys and to make cutting operations as remote as possible.

26 Cutting Reactor Nozzles, Control Rod Drive Tubes and All Other Vessel Attachments. Pulley set-ups used to access nozzle cuts with very limited access.

27 Cutting Reactor Nozzles, Control Rod Drive Tubes and All Other Vessel Attachments. Cutting the reactor nozzles, control rod drive tubes, and all other vessel attachments free from the vessel. In each case, the metal and/or concrete structures were cut at a precise location. Radiation dose was reduced significantly by operating the equipment from a remote location. The cuts were very smooth and completed on schedule.

28 Reactor Vessel Removal Reactor vessel being removed and placed in encapsulation and transport canister.

29 Reactor Vessel Removal Cut reactor nozzles after removal of vessel. Complete package being loaded onto trailer for transport to barge slip.

30 Reactor Vessel Removal Package loaded and ready for transport to burial site.

31 Reactor Vessel Removal Package at burial site. All phases of the project were successfully performed with no injuries or accidents. For all of the work, cooling water for the diamond wire was controlled, captured and in some instances recycled to reduce overall volume.

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

FIG. 1. Fort St. Vrain Nuclear Generation Station. Invited Paper XA9848067 FORT ST. VRAIN DECOMMISSIONING PROJECT M. FISHER Public Service Company of Colorado, Denver, Colorado, USA Abstract Public Service Company of Colorado (PSCo), owner of the Fort

More information

NEW TREATMENT CONCEPT FOR STEAM GENERATORS- TECHNICAL ASPECTS

NEW TREATMENT CONCEPT FOR STEAM GENERATORS- TECHNICAL ASPECTS NEW TREATMENT CONCEPT FOR STEAM GENERATORS- TECHNICAL ASPECTS Anders Lindström, Bo Wirendal and Maria Lindberg Studsvik Nuclear AB Department RadWaste SE 611 82 Nyköping Sweden ABSTRACT The project that

More information

Reactor Vessel Removal: Improving Performance Big Rock Point Lessons Learned

Reactor Vessel Removal: Improving Performance Big Rock Point Lessons Learned Reactor Vessel Removal: Improving Performance Big Rock Point Lessons Learned P.T. Daly BNG America, D&D Operations 804 South Illinois Avenue, Oak Ridge, TN 37830 USA ABSTRACT The Big Rock Point (BRP) reactor

More information

Radiation Control in the Core Shroud Replacement Project of Fukushima-Daiichi NPS Unit #2

Radiation Control in the Core Shroud Replacement Project of Fukushima-Daiichi NPS Unit #2 General Radiation Control in the Core Shroud Replacement Project of Fukushima-Daiichi NPS Unit #2 Yasunori Kokubun, Kazuyuki Haraguchi, Yuji Yoshizawa, Yasuo Yamada Tokyo Electric Power Co, 22 Kitahara

More information

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

PRR-1 Decommissioning: Preparing for Dismantling and Decontamination. R2D2 Project Meeting, Manila, Philippines September PRR-1 Decommissioning: Preparing for Dismantling and Decontamination R2D2 Project Meeting, Manila, Philippines 15-19 September 2008 1 Presented by Leonardo S. Leopando Philippine Nuclear Research Institute

More information

Lessons learned from ongoing decommissioning project of Fugen NPS

Lessons learned from ongoing decommissioning project of Fugen NPS Workshop on "Current and Emerging Methods for Optimizing Safety and Efficiency in Nuclear Decommissioning, Sarpsborg, Norway, 7th 9th February 2017 Lessons learned from ongoing decommissioning project

More information

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

AREVA: Experience in Dismantling and Packing of Pressure Vessel and Core Internals AREVA: Experience in Dismantling and Packing of Pressure Vessel and Core Internals Jan Hendrik Bruhn GmbH/ IBRZ-G Varna, June 10 th 2010 Content General Requirements for Dismantling Projects Stade NPP

More information

Best practices for preparing vessel internals segmentation projects

Best practices for preparing vessel internals segmentation projects Best practices for preparing vessel internals segmentation projects Joseph BOUCAU a*, Per SEGERUD b, Moisés SANCHEZ c a Westinghouse Electric Company, 43 rue de l Industrie, 1400 Nivelles, Belgium b Westinghouse

More information

Oregon State University s Small Modular Nuclear Reactor Experimental Program

Oregon State University s Small Modular Nuclear Reactor Experimental Program Oregon State University s Small Modular Nuclear Reactor Experimental Program IEEE Conference on Technologies for Sustainability August 1, 2013 Portland, Oregon Brian Woods Oregon State University brian.woods@oregonstate.edu,

More information

San Onofre Unit 1 Decommissioning

San Onofre Unit 1 Decommissioning San Onofre Unit 1 Decommissioning Eric M. Goldin, Ph.D., CHP Southern California Edison P. O. Box 128 San Clemente, CA 92674-0128 USA Introduction Nuclear plant decommissioning presents several challenges

More information

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

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

More information

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

The following considerations are taken into account for designing the NUHOMS MP197 packaging. 14th International Symposium on the Packaging and Paper # 164 Transportation of Radioactive Materials (PATRAM 2004), Berlin, Germany, September 20-24, 2004 NUHOMS - MP197 Transport Cask Peter Shih, TRANSNUCLEAR,

More information

1-(866)

1-(866) WELCOME TO SIOUX RUBBER. WE PROTECT IT WITH RUBBER & URETHANE Your Rubber & Urethane Partner Sioux Rubber & Urethane is proud of our ability to help design and manufacture custom solutions to your abrasion,

More information

K. ASTM F436- Standard Specification for Hardened Steel Washers; 2011.

K. ASTM F436- Standard Specification for Hardened Steel Washers; 2011. DIVISION 05 METALS 05 12 00 STRUCTURAL STEEL FRAMING PART 1 GENERAL 1.1 SECTION INCLUDES A. Structural steel framing members, support members. 1.2 RELATED REQUIREMENTS A. Section 05 50 00 - Metal Fabrications:

More information

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

F. BODIN 1, Ph. FOURNIER 1, L. MARTIN 2 1 COGEMA La Hague BEAUMONT HAGUE Cedex - France 2 SALVAREM BEAUMONT HAGUE Cedex - France COGEMA EXPERIENCE ON DECONTAMINATION AND UNDERWATER AUTOMATICALLY REMOTE CUTTING USING ULTRA HIGH PRESSURE WATER DURING NUCLEAR DECOMMISSIONING OPERATIONS THE AQUARAD ROBOT F. BODIN 1, Ph. FOURNIER 1,

More information

Best practices for preparing vessel internals segmentation projects

Best practices for preparing vessel internals segmentation projects PREDEC 2016: Title of the communication, February 16 18, Lyon, France Best practices for preparing vessel internals segmentation projects Joseph BOUCAU a*, Per SEGERUD b, Moisés SANCHEZ c a Westinghouse

More information

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

WM2015 Conference, March 15 19, 2015, Phoenix, Arizona, USA Fukushima Inspection Manipulator 15485 Matt Cole, Kurion Takashi Mitsui, Yuji Morigaki * 1, Toshinori Dekura* 2, * 3 *1: IHI Corporation, Yokohama, Kanagawa, Japan *2: International Research Institute

More information

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

RESEARCH REACTOR FRJ-1 (MERLIN) THE CORE STRUCTURES OF THE REACTOR BLOCK ARE DISMANTLED RESEARCH REACTOR FRJ-1 (MERLIN) THE CORE STRUCTURES OF THE REACTOR BLOCK ARE DISMANTLED B. Stahn, R. Printz, K. Matela, C. Zehbe Forschungszentrum Jülich GmbH 52425 Jülich, Germany J. Pöppinghaus Gesellschaft

More information

Maintenance Technologies for SCC which Support Stable Operations of Pressurized Water Reactor Power Plants

Maintenance Technologies for SCC which Support Stable Operations of Pressurized Water Reactor Power Plants Maintenance Technologies for which Support Stable Operations of Pressurized Water Reactor Power Plants KOJI OKIMURA* 1 MASAYUKI MUKAI* 1 KAZUHIKO KAMO* 2 NOBUYUKI HORI* 1 KOICHIRO MASUMOTO* 1 MASAAKI KUROKAWA*

More information

Diffused Aeration Piping Equipment

Diffused Aeration Piping Equipment 1.0 General 1.1. The specifications in this section include all components of the Diffused Aeration System with the exception of the individual diffuser units. Refer to additional specification sections

More information

Innovative Approaches to Large Component Packaging. A. Freitag, M, Hooper, E, Posivak, J. Sullivan WMG, Inc. Peekskill, NY USA

Innovative Approaches to Large Component Packaging. A. Freitag, M, Hooper, E, Posivak, J. Sullivan WMG, Inc. Peekskill, NY USA Innovative Approaches to Large Component Packaging A. Freitag, M, Hooper, E, Posivak, J. Sullivan WMG, Inc. Peekskill, NY 10566 USA ABSTRACT Radioactive waste disposal often times requires creative approaches

More information

Reactor Internals Segmentation Experience in the Nordic Region

Reactor Internals Segmentation Experience in the Nordic Region Reactor Internals Segmentation Experience in the Nordic Region - 14267 Per Segerud, Stefan Fallström, and Lennart Nilsson Westinghouse Electric Sweden AB ABSTRACT The Nordic region has a long history of

More information

The ACR : Advanced Design Features for a Short Construction Schedule

The ACR : Advanced Design Features for a Short Construction Schedule Transactions of the 17 th International Conference on Structural Mechanics in Reactor Technology (SMiRT 17) Prague, Czech Republic, August 17 22, 2003 Paper # S01-3 The ACR : Advanced Design Features for

More information

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

Gerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany 861 REMOTELY-OPERATED DISMANTLING OF THE REACTOR INTERNALS AT NIEDERAICHBACH POWER PLANT USING MANIPULATORS Gerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany ABSTRACT The joint venture

More information

The paper includes design and licensing status of the MAGNASTOR system, and prototyping development that NAC has performed to date.

The paper includes design and licensing status of the MAGNASTOR system, and prototyping development that NAC has performed to date. 14th International Symposium on the Packaging and Paper # 108 Transportation of Radioactive Materials (PATRAM 2004), Berlin, Germany, September 20-24, 2004 NAC's Modular, Advanced Generation, Nuclear All-purpose

More information

SECTION ENTRANCE FLOOR GRILLES STAINLESS STEEL GRATING

SECTION ENTRANCE FLOOR GRILLES STAINLESS STEEL GRATING 7160 Krick Rd., Walton Hills, OH 44146 800-321-3827 - Tel 440-439-8650 - Fax 440-439-6889 SECTION 12 48 16 ENTRANCE FLOOR GRILLES STAINLESS STEEL GRATING PART 1. GENERAL 1.01 SUMMARY: This section includes

More information

RANCHO SECO TRANSITION TO FULL DECOMMISSIONING. Dennis E. Gardiner, Decommissioning Project Manager, SMUD John M. Newey, CHP, President, NewRad, Inc.

RANCHO SECO TRANSITION TO FULL DECOMMISSIONING. Dennis E. Gardiner, Decommissioning Project Manager, SMUD John M. Newey, CHP, President, NewRad, Inc. ABSTRACT RANCHO SECO TRANSITION TO FULL DECOMMISSIONING Dennis E. Gardiner, Decommissioning Project Manager, SMUD John M. Newey, CHP, President, NewRad, Inc. The Rancho Seco Nuclear Generating Station

More information

Trex Commercial Products page Metal Railing

Trex Commercial Products page Metal Railing SECTION 05520 HANDRAILS AND RAILINGS PART 1 GENERAL 1.1 SECTION INCLUDES A. Classic Railings (Picket). B. GridGuard Railings (Mesh). C. Post Rail (Glass). D. Tensiline Railings (Cable). E. Track Rail (Glass).

More information

SECTION ENTRANCE FLOOR GRILLES STAINLESS STEEL GRATING

SECTION ENTRANCE FLOOR GRILLES STAINLESS STEEL GRATING 7160 Krick Rd., Walton Hills, OH 44146 800-321-3827 - Tel 440-439-8650 - Fax 440-439-6889 SECTION 12 48 16 ENTRANCE FLOOR GRILLES STAINLESS STEEL GRATING PART 1. GENERAL 1.01 SUMMARY: This section includes

More information

PROCESS GAS WASTE HEAT BOILERS WITH THIN FLEXIBLE TUBESHEET DESIGN

PROCESS GAS WASTE HEAT BOILERS WITH THIN FLEXIBLE TUBESHEET DESIGN PROCESS GAS WASTE HEAT BOILERS WITH THIN FLEXIBLE TUBESHEET DESIGN BORSIG The Company BORSIG Process Heat Exchanger GmbH, a member of the BORSIG Group, is the international leading manufacturer of pressure

More information

Developing a Low Power/Shutdown PRA for a Small Modular Reactor. Nathan Wahlgren

Developing a Low Power/Shutdown PRA for a Small Modular Reactor. Nathan Wahlgren Developing a Low Power/Shutdown PRA for a Small Modular Reactor Nathan Wahlgren NuScale Power, LLC June 23, 2014 1 Non-Proprietary Overview Probabilistic risk assessment (PRA) has traditionally focused

More information

Large Cask, Small Building, AREVA s Safe MLLW Disposal Solution Despite Facility Limitations 16295

Large Cask, Small Building, AREVA s Safe MLLW Disposal Solution Despite Facility Limitations 16295 Large Cask, Small Building, AREVA s Safe MLLW Disposal Solution Despite Facility Limitations 16295 Ronnie T. Broughton*, PE, PMP, Adam Jones*, PE, Paul Scott** *AREVA Federal Services, LLC Ronnie.Broughton@areva.com

More information

JOSEPH OAT CORPORATION. We Make Metal Work FABRICATION, DESIGN, AND CONSULTING SERVICES FOR THE NUCLEAR INDUSTRY.

JOSEPH OAT CORPORATION. We Make Metal Work FABRICATION, DESIGN, AND CONSULTING SERVICES FOR THE NUCLEAR INDUSTRY. JOSEPH OAT CORPORATION We Make Metal Work FABRICATION, DESIGN, AND CONSULTING SERVICES FOR THE NUCLEAR INDUSTRY. JOSEPH OAT CORPORATION Joseph Oat Corporation, a family owned and operated business for

More information

WM 00 conference, February 27 March 2, 2000, Tucson, AZ

WM 00 conference, February 27 March 2, 2000, Tucson, AZ WM 00 conference, February 27 March 2, 2000, Tucson, AZ REACTOR PRESSURE VESSEL REMOVAL AT A BOILING WATER REACTOR WITH SPENT FUEL IN THE ADJACENT FUEL POOL By Albert A. Freitag, WMG, Inc Greg Harttraft,

More information

Reactor Core Internals Replacement of Ikata Units 1 and 2

Reactor Core Internals Replacement of Ikata Units 1 and 2 IAEA-CN-194-1P51 Reactor Core Internals Replacement of Ikata Units 1 and 2 K. Ikeda,T. Ishikawa,T. Miyoshi,T. Takagi Shikoku Electric Power Co., Inc., Takamatsu City, Japan Abstract. This paper presents

More information

SECTION ALUMINUM HANDRAIL SYSTEMS

SECTION ALUMINUM HANDRAIL SYSTEMS SECTION 05520 ALUMINUM HANDRAIL SYSTEMS PART 1 - GENERAL 1.01 SUMMARY A. Section includes aluminum handrails and railings. B. Related Work: 1. Section 03300 - Cast-in-Place Concrete C. References: 1. American

More information

Push a Button and the Work Gets Done

Push a Button and the Work Gets Done EPRI JOURNAL July/August 2018 No. 4 1 Push a Button and the Work Gets Done EPRI Examines Robotics and Automation for Nuclear Plant Decommissioning By Brent Barker The Resident Farmer Scenario describes

More information

ESS Target Facility Design. John Haines for the ESS Target Project Team

ESS Target Facility Design. John Haines for the ESS Target Project Team ESS Target Facility Design John Haines for the ESS Target Project Team www.europeanspallationsource.se May 7, 2015 Outline Background Status of technical systems Project status and plans 2 ESS will be

More information

SECTION ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Casino Modular Railing System

SECTION ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Casino Modular Railing System SECTION 05 5200 ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Casino Modular Railing System PART 1 GENERAL 1.01 WORK INCLUDED A. Furnish and/or install stainless steel railings and components. 1.02 REFERENCE

More information

CITY OF MOUNT DORA LIFT STATION CHAINLINK FENCE AND GATE SPECIFICATIONS

CITY OF MOUNT DORA LIFT STATION CHAINLINK FENCE AND GATE SPECIFICATIONS CITY OF MOUNT DORA LIFT STATION CHAINLINK FENCE AND GATE SPECIFICATIONS PART 1 - GENERAL 1.01 SUMMARY A. Section Includes furnishing and installing chain-link fabric fence, gate, and appurtenances. 1.02

More information

NORTH HARRIS COUNTY REGIONAL WATER AUTHORITY PIPE HANGERS, Section PIPE HANGERS, SUPPORTS, AND RESTRAINTS

NORTH HARRIS COUNTY REGIONAL WATER AUTHORITY PIPE HANGERS, Section PIPE HANGERS, SUPPORTS, AND RESTRAINTS PART 1 GENERAL 1.01 SUMMARY Section 15140 PIPE HANGERS, This Section includes the furnishing and subsequent installation of: A. Pipe and equipment hangers, supports, and associated anchors B. Equipment

More information

Demonstrative Drop Tests of Transport and Storage Full-Scale Canisters with High Corrosion-resistant

Demonstrative Drop Tests of Transport and Storage Full-Scale Canisters with High Corrosion-resistant 14th International Symposium on the Packaging and Paper # 149 Transportation of Radioactive Materials (PATRAM 24), Berlin, Germany, September 2-24, 24 Demonstrative Drop Tests of Transport and Storage

More information

Collectors. Water Treatment & Chemical Processing

Collectors. Water Treatment & Chemical Processing Water Treatment & Chemical Processing Collectors Screen Services Specialty screens and equipment for industrial, petrochemical, mining, and water treatment applications Page 2 Collector/Distributors fabricated

More information

SECTION HANDRAILS AND RAILINGS. Display hidden notes to specifier. (Don't know how? Click Here)

SECTION HANDRAILS AND RAILINGS. Display hidden notes to specifier. (Don't know how? Click Here) SECTION 05520 HANDRAILS AND RAILINGS PART 1 GENERAL 1.1 SECTION INCLUDES Display hidden notes to specifier. (Don't know how? Click Here) A. Classic Railings (Picket). B. GridGuard Railings (Mesh). C. Post

More information

MODEL SPECIFICATIONS: Hydraulically Driven Steel Underpinning Pile Specifications

MODEL SPECIFICATIONS: Hydraulically Driven Steel Underpinning Pile Specifications MODEL SPECIFICATIONS: Hydraulically Driven Steel Underpinning Pile Specifications Mar/2008 v1.0 SECTION 02255 HYDRAULICLY DRIVEN STEEL UNDERPINNING PILES PART 1 GENERAL 1.01 SCOPE OF WORK The work shall

More information

CEILING MOUNTED ARTICULATING JIB CRANE

CEILING MOUNTED ARTICULATING JIB CRANE SECTION 14657 CEILING MOUNTED ARTICULATING JIB CRANE ***** Gorbel, Inc. manufacturers a broad range of material handling cranes including monorail, bridge, gantry, and jib cranes. Numerous work station

More information

FOOD AND BEVERAGE PROCESSING

FOOD AND BEVERAGE PROCESSING BILFINGER WATER TECHNOLOGIES FOOD AND BEVERAGE PROCESSING COMPREHENSIVE SOLUTIONS FOR BIO-FUELS, BREWING, CORN WET MILLING, ETHANOL, MALTING, STARCH, SUGAR TREATMENT AND WINE PRODUCTION 2 FOOD AND BEVERAGE

More information

Chapter 12. Flux Cored Arc Welding Equipment, Setup, and Operation Delmar, Cengage Learning

Chapter 12. Flux Cored Arc Welding Equipment, Setup, and Operation Delmar, Cengage Learning Chapter 12 Flux Cored Arc Welding Equipment, Setup, and Operation Objectives Explain the FCA welding process Describe what equipment is needed for FCA welding List the advantages of FCA welding, and explain

More information

Stairpans Stair Treads Landing Pans Carrier Angles Nosings Infill Panels U-Edging Hems

Stairpans Stair Treads Landing Pans Carrier Angles Nosings Infill Panels U-Edging Hems Stairpans Stair Treads Landing Pans Carrier Angles Nosings Infill Panels U-Edging Hems STAIR SYSTEMS CATALOG stairpans.com 2 Serving the Needs of Our Customers Since 1923 Eberl Iron Works, Inc. Founded

More information

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

Replacement Works for the Steam Generator and the Reactor Pressure Vessel Upper Head Unit 2, Genkai Nuclear Power Plant Replacement Works for the Steam Generator and the Reactor Pressure Vessel Upper Head Replacement works for the above components were conducted at Unit 2 of the Genkai

More information

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

RADIOACTIVE GRAPHITE MANAGEMENT AT UK MAGNOX NUCLEAR POWER STATIONS. G. HOLT British Nuclear Fuels plc, Berkeley, United Kingdom 1. RADIOACTIVE GRAPHITE MANAGEMENT AT UK MAGNOX NUCLEAR POWER STATIONS G. HOLT British Nuclear Fuels plc, Berkeley, United Kingdom Abstract. The UK nuclear power industry is predominantly based on gas-cooled,

More information

Chapter 7. Drains and cleanouts. Drains and cleanouts 34. Topics. Notes. 7.1 Existing rectangular or square drains and floor sinks 35

Chapter 7. Drains and cleanouts. Drains and cleanouts 34. Topics. Notes. 7.1 Existing rectangular or square drains and floor sinks 35 Drains and cleanouts 34 Chapter 7 Drains and cleanouts Topics 7.1 Existing rectangular or square drains and floor sinks 35 7.2 Altro Gulley Angle/Edge strips with Altro safety flooring 35 7.3 Visedge VR

More information

SECTION VIBRATION CONTROLS FOR HVAC PIPING AND EQUIPMENT

SECTION VIBRATION CONTROLS FOR HVAC PIPING AND EQUIPMENT SECTION 230548 - PART 1 - GENERAL 1.1 SUMMARY A. This Section includes the following: 1. Elastomeric Isolation pads. 2. Elastomeric Isolation mounts. 3. [Freestanding] [Restrained] [Freestanding and restrained]

More information

De Montfort Mark 7 Incinerator (Flatpack)

De Montfort Mark 7 Incinerator (Flatpack) De Montfort Mark 7 Incinerator (Flatpack) Introduction This design is specially for those occasions when a large number of incinerators are to be built at one location and transported to the places where

More information

SECTION ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Summit tm Modular Railing System

SECTION ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Summit tm Modular Railing System SECTION 05720 ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Summit tm Modular Railing System PART 1 GENERAL 1.01 WORK INCLUDED A. Furnish and/or install supported glass stainless steel railings, glass

More information

SECTION STRUCTURAL METAL FRAMING

SECTION STRUCTURAL METAL FRAMING SECTION 05100 STRUCTURAL METAL FRAMING PART 1 GENERAL 1.01 SUMMARY A. Section Includes: Structural steel framing including lintels, shelf angles, bearing plates, anchor bolts and other items as shown on

More information

WALL CANTILEVER WORK STATION JIB CRANE

WALL CANTILEVER WORK STATION JIB CRANE SECTION 14662 WALL CANTILEVER WORK STATION JIB CRANE ***** Gorbel, Inc. manufactures a broad range of material handling cranes including monorail, bridge, gantry, and jib cranes. Numerous work station

More information

Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life

Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life Nuclear Fuels Storage & Transportation Planning Project Office of Fuel Cycle Technologies Nuclear Energy

More information

1. Base plates, setting plates and anchor rods for columns. 8. Lintels if connected to structural steel columns.

1. Base plates, setting plates and anchor rods for columns. 8. Lintels if connected to structural steel columns. PAGE 051200-1 SECTION 051200 PART 1 - GENERAL 1.1 RELATED DOCUMENTS A. Drawings and general provisions of the Contract, including General and Supplementary Conditions and Division 01 Specification sections,

More information

nalcofabtech.com A Nalco Champion Company

nalcofabtech.com A Nalco Champion Company nalcofabtech.com A Nalco Champion Company 2 CONTENTS Goal Zero - Safety Culture...4 About Us...6 Capabilities...8 Services...24 Equipment and Facilities... 36 3 4 At Nalco FabTech, our programs ensure

More information

.1 American Institute of Steel Construction (AISC) Specifications for Steel Buildings AISC

.1 American Institute of Steel Construction (AISC) Specifications for Steel Buildings AISC 05 12 00 STRUCTURAL STEEL FRAMING Page 1 of 3 1 General 1.1 SECTION INCLUDES.1 Structural steel framing and support members 1.2 RELATED SECTIONS.1 Section 05 50 00 Metal Fabrications 1.3 REFERENCES.1 American

More information

A-Series Aluminum Gantry Crane

A-Series Aluminum Gantry Crane SPANCO PRODUCT SPECIFICATIONS 1 A-Series Aluminum Gantry Crane This guide can be used to prepare a bid specification for the incorporation of an A-Series Gantry Crane into a competitive bid project or

More information

Handling of Reactor Internals at Forsmark Nuclear Power Plant

Handling of Reactor Internals at Forsmark Nuclear Power Plant Handling of Reactor Internals at Forsmark Nuclear Power Plant Presented at the Studsvik seminar on Decommissioning of Nuclear Facilities 14-16 September 2010, Nyköping, Sweden Jennifer Möller Henrik Algotsson

More information

METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF

METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF THE AP1000 TM REACTOR Erik Slobe slobeed@westinghouse.com Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township,

More information

Minimizing Activation, Size and Costs and yet Maximizing Efficiency

Minimizing Activation, Size and Costs and yet Maximizing Efficiency Minimizing Activation, Size and Costs and yet Maximizing Efficiency An Engineering Challenge for Neutron Research Instruments Elbio Calzada MLZ is a cooperation between: Outline Introduction: Neutron Source

More information

How To Construct a Ferro Cement Tank

How To Construct a Ferro Cement Tank How To Construct a Ferro Cement Tank Be Advised The following power point presentation assumes that individuals using it to construct ferro-cement tanks have a basic knowledge of geometry and calculating

More information

SECTION DECORATIVE METAL AND GLASS RAILING

SECTION DECORATIVE METAL AND GLASS RAILING SECTION 05 73 00 DECORATIVE METAL AND GLASS RAILING PART 1 GENERAL 1.1 SUMMARY A) This section includes both standard and custom handrails as shown in the contract drawings. B) These include aluminum,

More information

Sampling of Reactor Pressure Vessel and Core Internals Ralf Oberhäuser

Sampling of Reactor Pressure Vessel and Core Internals Ralf Oberhäuser Sampling of Reactor Pressure Vessel and Core Internals Ralf Oberhäuser Decommissioning & Dismantling Projects GmbH, Erlangen, Germany Content Introduction and Motivation Main Aspects Sampling Techniques

More information

Valmont Newmark is your single source for steel, concrete or hybrid structures for power delivery

Valmont Newmark is your single source for steel, concrete or hybrid structures for power delivery Valmont Newmark is your single source for steel, concrete or hybrid structures for power delivery Valmont Newmark is your single source for steel, A Tradition of Meeting Needs. Building on its steel pole

More information

SECTION VIBRATION CONTROLS FOR PLUMBING PIPING AND EQUIPMENT

SECTION VIBRATION CONTROLS FOR PLUMBING PIPING AND EQUIPMENT Page 220548-1 SECTION 220548 - PART 1 - GENERAL 1.1 RELATED DOCUMENTS A. Drawings and general provisions of the Contract, including General and Supplementary Conditions and Division 01 Specification Sections,

More information

This guide can be used to prepare a specification for incorporating wall bracket jib cranes into a competitively bid construction project.

This guide can be used to prepare a specification for incorporating wall bracket jib cranes into a competitively bid construction project. SECTION 14654 WALL BRACKET JIB CRANE ***** Gorbel, Inc. manufacturers a broad range of material handling cranes including monorail, bridge, gantry, and jib cranes. Numerous work station and industrial

More information

Designing, Commissioning and Monitoring of 40% Scale Bentonite Buffer Test 14260

Designing, Commissioning and Monitoring of 40% Scale Bentonite Buffer Test 14260 Designing, Commissioning and Monitoring of 40% Scale Bentonite Buffer Test 14260 Harri Kivikoski*, Pieti Marjavaara* and Pasi Rantamäki** * VTT Technical Research Centre of Finland, Espoo, Finland ** Posiva

More information

Nuclear Fuel Cycle Transport

Nuclear Fuel Cycle Transport WNTI W O R L D N U C L E A R T R A N S P O RT I N S T I T U T E FACT SHEET Nuclear Fuel Cycle Transport Back End Materials Dedicated to the safe, efficient and reliable transport of radioactive materials

More information

Structural Steel. Production and Applications. GWP Engineering Limited

Structural Steel. Production and Applications. GWP Engineering Limited Structural Steel Production and Applications GWP Engineering Limited Contents About Us...3 Steel Material...4 Production...6 Structural Steel Fabrication...8 Applications...10 2 About Us From offices in

More information

4418 Pesson Road New Iberia, LA 70560

4418 Pesson Road New Iberia, LA 70560 ASRC Energy Services Omega, LLC is a full service provider for oil and gas production, mid-stream chemical processing, drilling, refining, utility, government and manufacturing industries. Omega has construction

More information

METAL LADDERS (LADDER SAFETY GATE FALL PROTECTION)

METAL LADDERS (LADDER SAFETY GATE FALL PROTECTION) Page 1 of 6 SECTION 05515 METAL LADDERS (LADDER SAFETY GATE FALL PROTECTION) PART 1 - GENERAL 1.1 SECTION INCLUDES A. Specialty custom designed, spring assisted, self-closing LADDER SAFETY GATE (LSG) for

More information

SPECIFICATIONS SECTION FLOOD CONTROL GATES. A. ASTM C 39 - Standard Test Method for Compressive Strength of Cylindrical Concrete Specimens.

SPECIFICATIONS SECTION FLOOD CONTROL GATES. A. ASTM C 39 - Standard Test Method for Compressive Strength of Cylindrical Concrete Specimens. SPECIFICATIONS SECTION FLOOD CONTROL GATES PART 1 GENERAL 1.1 SECTION INCLUDES A. Flood Gates. 1.2 RELATED SECTIONS A. N/A. 1.3 REFERENCES A. ASTM C 39 - Standard Test Method for Compressive Strength of

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C SAFETY EVALUATION REPORT

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C SAFETY EVALUATION REPORT UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 72-1040 HI-STORM UMAX Canister Storage System Holtec International, Inc. Certificate of Compliance

More information

VVER-440/213 - The reactor core

VVER-440/213 - The reactor core VVER-440/213 - The reactor core The fuel of the reactor is uranium dioxide (UO2), which is compacted to cylindrical pellets of about 9 height and 7.6 mm diameter. In the centreline of the pellets there

More information

INSTALLATION GUIDE PLEASE READ ENTIRE INSTRUCTION MANUAL BEFORE PROCEEDING!

INSTALLATION GUIDE PLEASE READ ENTIRE INSTRUCTION MANUAL BEFORE PROCEEDING! DURA - TRENCH INSTALLATION GUIDE This guide is intended to aide in the installation of Dura-Trench systems. There are many different applications and situations for the use of this product and the installation

More information

SPECIFICATION SECTION 05515: LADDERS O Keeffe s Aluminum Ladders

SPECIFICATION SECTION 05515: LADDERS O Keeffe s Aluminum Ladders Welcome to the O Keeffe s Guide Specification System prepared as an aid to specify in preparing written construction documents. For specification assistance with specific product applications, please contact

More information

SECTION ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Monaco tm Modular Railing System

SECTION ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Monaco tm Modular Railing System SECTION 05720 ARCHITECTURAL ORNAMENTAL HANDRAILS AND RAILINGS Monaco tm Modular Railing System PART 1 GENERAL 1.01 WORK INCLUDED A. Furnish and/or install supported glass stainless steel railings, glass

More information

40'-0" PIPE SUPPORT (TYP.) (SEE DWG. NO. SK-2 OR DWG. NO. SK-4)

40'-0 PIPE SUPPORT (TYP.) (SEE DWG. NO. SK-2 OR DWG. NO. SK-4) SK-1 STANDARD LENGTH 4.301 40'-0" A 6" 2'-0" 9'-0" 9'-0" 9'-0" 9'-0" 2'-0" A 3" OF EXPOSED AT EACH END OF PIPE. PIPE SUPPORT (TYP.) (SEE DWG. NO. SK-2 OR DWG. NO. SK-4) EXPOSED PIPE MINIMUM GAUGE AND THICKNESS

More information

Decommissioning the Philippine Research Reactor (Under R2D2P): Updates and Challenges

Decommissioning the Philippine Research Reactor (Under R2D2P): Updates and Challenges Decommissioning the Philippine Research Reactor (Under R2D2P): Updates and Challenges C.C. Bernido,, F.L. Santos, L.S. Leopando Philippine Nuclear Research Institute Philippine Research Reactor (PRR-1)

More information

WM 2013 Conference, February 24 February 28, 2013, Phoenix, AZ, USA. Removal of the Plutonium Recycle Test Reactor 13031

WM 2013 Conference, February 24 February 28, 2013, Phoenix, AZ, USA. Removal of the Plutonium Recycle Test Reactor 13031 ABSTRACT Removal of the Plutonium Recycle Test Reactor 13031 C. Brad Herzog, CH2M HILL, Inc., cherzog@ch2m.com Rudolph Guercia, DOE, rudolph.guercia@rl.doe.gov Matt LaCome, Meier Engineering Inc., mllacome@meierinc.com

More information

UK ABWR - NEW NPP DESIGN FOR UK

UK ABWR - NEW NPP DESIGN FOR UK IAEA PLiM2017 [IAEA-CN-246-085] UK ABWR - NEW NPP DESIGN FOR UK 25-October-2017 Kazuhiro YOSHIKAWA Masaaki HAYASHI Yasuhiro MABUCHI Daisuke TANIGUCHI Hitachi-GE Nuclear Energy, Ltd. Contents 1. Introduction

More information

female pipe. A Wall Support must be installed just above the tee and at least every 8 feet thereafter. If the pipe is to be run through a roof overhang then a Flashing, Storm Collar and Vertical Rain Cap

More information

SECTION ORCHESTRA PIT FILLER

SECTION ORCHESTRA PIT FILLER PART 1 - GENERAL 1.1 SECTION INCLUDES A. Orchestra pit filler. 1.2 REFERENCES SECTION 11 61 00 ORCHESTRA PIT FILLER A. American Hardboard Association (AHA): 1. AHA A135.4-95: Basic Hardboard. B. American

More information

STEAM GENERATOR LEAKAGE AT THE BN-350 DESALINATION PLANT

STEAM GENERATOR LEAKAGE AT THE BN-350 DESALINATION PLANT STEAM GENERATOR LEAKAGE AT THE BN-350 DESALINATION PLANT M. Ragheb 12/13/2010 INTRODUCTION The BN-350 sodium cooled fast reactor was constructed near the city of Aktau, formerly Shevchenko on the Caspian

More information

2.0 Normal and customary equipment used on a core drill job include:

2.0 Normal and customary equipment used on a core drill job include: CSDA Specification Title: Core Drilling Specification No: CSDA-C-101 Effective Date: June 1, 1998 Revised: Mar 30, 2004 1. Codes, Standards & Definitions 1.1 Occupational Safety and Health Administration

More information

Long Reach Tooling Solutions

Long Reach Tooling Solutions Long Reach Tooling Solutions Supporting Decommissioning of the PFSP at Sellafield A framework contract, with JFN as the primary interface, was established in July 2013, with the aim of developing a long

More information

Maria Taranger Foto: Kävlinge Municipality

Maria Taranger Foto: Kävlinge Municipality Maria Taranger Foto: Kävlinge Municipality The icon of nuclear power in Sweden The beginning and the end Type: BWR Capacity: 1800 MWt / 615MWe First connection to the grid: May 15, 1975 / March 21, 1977

More information

Structural Design of Dam Sluice Gate Walkway Slabs: Retrofit and Replacement Options

Structural Design of Dam Sluice Gate Walkway Slabs: Retrofit and Replacement Options Structural Design of Dam Sluice Gate Walkway Slabs: Retrofit and Replacement Options A local utility company issued a Request for Proposal to our university s capstone design class for structural improvements

More information

International Journal of Advance Engineering and Research Development

International Journal of Advance Engineering and Research Development Scientific Journal of Impact Factor (SJIF): 5.71 International Journal of Advance Engineering and Research Development Volume 5, Issue 03, March -2018 e-issn (O): 2348-4470 p-issn (P): 2348-6406 Study

More information

BORSIG Process Heat Exchanger GmbH. Egellsstr. 21 Phone: +49 (0) 30 / Berlin/Germany Fax: +49 (0) 30 /

BORSIG Process Heat Exchanger GmbH. Egellsstr. 21 Phone: +49 (0) 30 / Berlin/Germany Fax: +49 (0) 30 / BORSIG Process Heat Exchanger GmbH www.borsig.de/pro E-mail: info@pro.borsig.de Egellsstr. 21 Phone: +49 (0) 30 / 4301-01 13507 Berlin/Germany Fax: +49 (0) 30 / 4301-2447 BORSIG Process Heat Exchanger

More information

Rapid Axial Load Testing of Drilled Shafts

Rapid Axial Load Testing of Drilled Shafts Supplemental Technical Specification for Rapid Axial Load Testing of Drilled Shafts SCDOT Designation: SC-M-712 (9/15) September 4, 2015 1.0 GENERAL This work shall consist of performing a rapid axial

More information

Best Practice Form. Open Air Demolition of Asbestos Gunite by Using Track Mounted Wet Cutting Saw DOE Site:

Best Practice Form. Open Air Demolition of Asbestos Gunite by Using Track Mounted Wet Cutting Saw DOE Site: Best Practice Form Best Practice Title: Open Air Demolition of Asbestos Gunite by Using Track Mounted Wet Cutting Saw DOE Site: Lawrence Livermore National Laboratory (LLNL) Facility Name: B328 Demolition

More information

Installation Manual For Conical Tanks. INSTALLATION and MAINTENANCE INSTRUCTIONS FOR CONICAL TANKS

Installation Manual For Conical Tanks. INSTALLATION and MAINTENANCE INSTRUCTIONS FOR CONICAL TANKS INSTALLATION and MAINTENANCE INSTRUCTIONS FOR CONICAL TANKS Page 1 of 10 INDEX 1. Health & Safety 3 2. Introduction 3 3. Requirements 3 4. Working Area 3 5. Equipment 3 6. 2 and 3 metre tank above ground

More information

Greifswald Project Introduction/Experience summary Axel Bäcker

Greifswald Project Introduction/Experience summary Axel Bäcker Decommissioning operation of large decommissioning projects 20 years experience Decommissioning management of five power reactors on the Greifswald site Greifswald Project Introduction/Experience summary

More information

Irradiation Facilities at the Advanced Test Reactor International Topical Meeting on Research Reactor Fuel Management Lyon, France

Irradiation Facilities at the Advanced Test Reactor International Topical Meeting on Research Reactor Fuel Management Lyon, France Irradiation Facilities at the Advanced Test Reactor International Topical Meeting on Research Reactor Fuel Management Lyon, France S. Blaine Grover Idaho National Laboratory March 12, 2007 Agenda Advanced

More information