Role of GNS in the German Treatment of Radioactive ... Polytechnic_Mailand_0… · Role of GNS in the German Treatment of Radioactive Operational & Decommissioning Waste ... specialised

Meeting Polytechnic University of Milan 03.05.2013, Dr.G/1

Role of GNS in the German Treatment of

Radioactive Operational & Decommissioning Waste

Dr.-Ing. Heinz Geiser

GNS Gesellschaft für Nuklear-Service mbH

Meeting at Polytechnic University of Milan on May 3rd, 2013

Vita Dr.‐Ing. Heinz Geiser born 1946, married, one daughter

Education / Working History1963/67 Trainee in different nuclear research laboratories

1967/70 Study in Mechanical Engineering (Dipl.‐Ing.)1970/75 Study in Physics at Aachen University (Dipl.‐Phys.)1975/79 Position in Nuclear Industry, German Nuclear Program1977 PhD‐Degree in Nuclear Technology University Aachen1979/2011 Founder and Managing Director of the Engineering Company WTI,

specialised in nuclear Back End Operation2005/2011 Managing Director of GNS, responsible for Waste Treatment, Storage

of Spent Fuel and all related Engineering work.

Current PositionSenior Advisor for GNS,Teaching positions at Universities in Aachen and Munich in Nuclear Engineering,Member of various committees, consulting the German government, Solution of nuclear waste storage and treatment (Ministry of Environmental Affaire)

Content of the Presentation

Information on the company GNS

Waste treatment

Waste Packaging, Storage and Transportation

Final disposal



The Company

GNS Gesellschaft für Nuklear-Service mbHA medium-sized company founded in 1974,based in Essen/Germany

Gewissenhaft. Nachhaltig. Sicher.

Main Task:

Competence Centre for the German utilities for the management of spent fuel and nuclear waste from German power plants

Worldwide operations:

as one of the leading manufacturers of casks for spent fuel/HAW (CASTOR®, CONSTOR®) and MAW (MOSAIK®)

for processing of every kind of radioactive waste, decommissioning and related engineering services


Structure of GNS Group

28 %

GNS Gesellschaft für Nuklear-Service mbH

18,5 %*5,5 %

* Südwestdeutsche Nuklear-Entsorgungs-Gesellschaft mbH, Stuttgart (EnBW Kraftwerke AG, E.ON Kernkraft GmbH)

48%

* Südwestdeutsche Nuklear-Entsorgungs-Gesellschaft mbH, Stuttgart (EnBW Kraftwerke AG, E.ON Kernkraft GmbH)

100 % 100 % 100 % 75 %

Brennelement-Zwischenlager Ahaus GmbH

Brennelementlager Gorleben GmbH

Deutsche Gesellschaft zum Bauund Betrieb von Endlagern für

Abfallstoffe mbH (DBE)

WTIWissenschaftlich-Technische

Ingenieurberatung GmbH

100 %

ActaTechnologien

GmbH


Role of GNS in Germany

We take care of …(i.e. Competence and Responsibility of GNS)

Spent Fuel and HLW from Reprocessing

Management of Operational and Decommissioning waste(LLW/ILW)

Packaging, Transport, Interim Storage,Treatment, Preparation for Final Disposal

Treatment, Packaging, Transport,Interim Storage, Preparation for Final Disposal

Final Repository„Konrad“LLW/ILW

(construction phase)

Final RepositoryHLW

(exploration phase)

All GermanNPPs

Responsibility forexploration, construction

and operation:

Federal Republicof Germany


Sites of GNS Group

Abroad:Pilsen / CZMaubeuge / FBristol / UK

Gorleben

Jülich

Gorleben

Peine

DuisburgMülheim

Essen

Ahaus

Karlsruhe

Alzenau

General Information

Blue CollarWorkers

Administration

Service

GNS

plus subsidiaryDBE/DBE TECemployees 800

GNS-Group:Employees 650Turnover 200 Mio. Euro

ScientistsEngineers

Technicians

= total 1.350


WasteManagement

DecommissioningProjects

Waste Management


General Aim

Measuring forFree Release

Recycling

Packaging for Final Disposal

- Volume Reduction- Drying/Solidification

• Meeting Polytechnic University of Milan 03.05.2013, Dr.G/10

Contents Part 1:

Classification of waste categoriesTreatment of low/medium level wasteDecommissioning Treatment of large components

Part 2:Waste packagingStorageTransportation

Part 3:Final disposal and requirementsKONRAD Repository


Waste Classification by Radioactivity

High level radioactive Waste Intermediate level radioactive waste Low level radioactive waste

Short lived waste Long lived waste

Heat generating waste Waste with negligible heat generation

Natural occurring radioactive material

GER


Classification of Waste Categories

MediumLevel

Low

Level

HighLevel

previous today

heat-generatingWaste

Waste

without heat-generation

Waste Type

Fission Products from ReprocessingSpent Fuel

Core Components

Waste from Reprocessing

Waste from NPP Operation

Decommissioning Waste


Operational Waste


Schematic of Waste Treatment

Solid Waste Liquid Waste

Metal,Concrete

IsolationsPaper,Plastic,Cloths

Oil Sludge Concen-trate

Filter Aid Resins

Incineration Drying, Dewatering

Compaction

CompactSolid Waste

Container Shielded Container

Powder,Salt Crystal block


Requirements for Waste Treatment

Acceptance criteria for the final repository KONRAD mine define the necessary quality of the waste products and packages:

Only solid waste products No movable liquid inside the

waste packages Stable products, no

chemical reactions Limits for activity content

and hazardous material


GNS Waste Treatment Facilities


Compaction of Solid Waste (FAKIR)

Mobile super-compactors: Force of pressure 15 MN Operational capacity 10-20

drums/h Volume reduction factor 3-10


Cementation of KONRAD-Containers (1)






Insulation Material

Copper

Recycling of Cables by Shredding

Contaminated Cables


Incineration of Combustible Waste

Suitable for incineration of Combustible solid waste Oil, solvents Charcoal

Studsvik Nuclear (S)

Research Centre Jülich (D)

Research Centre Karlsruhe (D)

Socodei (F)

Belgonucléaire (B)


Treatment of Liquid Waste and Resins

Mobile and stationary drying facilities for treatment of evaporator concentrates, sludges as well as filter resins


PETRA-Facility for Drying of Drums


Treatment of Core Components Mobile underwater cutting equipment

84 control rods, 51 fuel assembly fasteners, incore lances, neutron sources etc. cutted, compacted and packed into MOSAIK® casks


Underwater Loading of Core Components


Hot Cell Facilities

Hot cell facilities are used for treatment of highly activated material arising from NPP. (Cutting, compaction and packaging)


Decommissioning Waste (PWR 1300 MW)

PWR: Total 4.100 Mg

Concrete, Reinforcing

Rad Waste

Components

Radioactive Waste, ConcreteRecycl. Material

Waste for konv. Disposal

Rad Waste, Components

Rad Waste secondary Waste

Recycling

Konv. Disposal

Material

Rad Waste

Rad Waste

non-radioactiveWaste

PWR Total MassMg


Dismantling Work under Performance


Decommissioning of a TRIGA-Reactor


Container Lock


Treatment of Large Components

Complete Mass approx. 1635 Mg

This is the waste stream with the biggest financial relevance within the deconstruction phase.

approx. 140 Mg

Reactor Pressure Vessel approx. 500 Mg

4 pc. Steam Generator approx. 660 Mg

Pressure Accumulator approx. 85 Mg

4 pc. Main CoolingPumps

Various Canisters, Tubes etc. approx. 250 Mg

Reactor Pressure Vessel

Main Cooling Pumps

Steam Generator

Pressure Accumulator


Dismantling of Steam Generators


Cutting of Steam Generator Bundles


Treatment of Steam Generators

Segmentation of the Steam Generator

Melting process and final ingots


Decontamination of Surfaces

Different types of blasting techniques


Equipment for Free Release


EWN Facility for Free Release Measurement


Contents

Part 1:Classification of waste categoriesTreatment of low/medium level wasteDecommissioning Treatment of large components


Part 3:Final disposal and requirementsKONRAD Repository


2 mm Steel sheet wall

Type IV

Waste Container (Box-type)


200 l-Drum / 400 l-Drum

200-l-Drum


Content 200 l Content 400 l

Cylindrical Concrete Container


Shielded Waste Container (MOSAIK®)

150 mm cast iron wall

40 mm … 140 mm inner lead shielding


Shielded Waste Container (Box-type)

2,0 … 3,5 m³ waste volume for spent resins, dried concentrates or activated materials; 150 mm cast iron wall


Waste Container (Box-type)


Storage Facility for MOSAIK® Container


Waste Storage Facility Ahaus


Waste Storage Facility at Karlsruhe


Greifswald Storage and Treatment Facility


Waste Storage at Greifswald (EWN)


Positioning of MOSAIK Casks



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Transportation of Waste (1)

Transport of 20´-Containers



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Transportation of Waste (3)


Transportation of Steam Generators (1)


Transportation of Steam Generators (2)


Contents

Part 1:Classification of waste categoriesTreatment of low/medium level wasteDecommissioning Treatment of large components


Part 3:Final disposal and requirementsKONRAD repository


German Final Disposal ProjectsOnly deep geological formations for final disposal of radioactive waste can be used in Germany.

Non-heat generating wasteKONRAD mineStarting 2019?

Heat generating wasteGorleben mineStarting 2045 (?)


Final Disposal at Morsleben (closed in 1998)


Development of German Final Repository

1967-1978 Operation of Research Disposal Facility Asse(Disposal of 126.000 m³)

1982 Start of KONRAD Licensing Process

1990 Responsibility of BfS for ERAM

1994-1998 Disposal of 13.700 m³ NPP-Waste in ERAM

1998 Closure of ERAM

2007 KONRAD Operation License

2019 ?? Operation of KONRAD


KONRAD Repository (1)


KONRAD Repositiory (2)


Planned Emplacement


Waste Package Emplacement


KONRAD Waste Acceptance Requirements (1)

… as of December 1995


KONRAD Waste Acceptance Requirements (2)


Additional Requirements: Nuclear Law


Requirements for Package Integrity


ABK I

- drop test: 0.8 m

- mechanical integrity of the cask

- non combustibility of the content up to 300 °C

ABK II

- drop test: 5.0 m

- mechanical integrity of the cask

- Thermal resistivity >0.1m2 K/W after drop test 0.8 m

- maximum temperature of the content < 80°C in the

case of fire (800°C/1 h)

Waste Package Qualification Tests

BAM Test Facility


Box-Type Container, Drop Test: 5.0 mContent: 26 pieces of 200-l-drums with sand Result

Integrity (top coverplate was still inposition)

positive drop test


MOSAIK®-Cask, Drop Test: 5 m


Nuclear CasksSpent FuelManagement

Spent Fuel Management



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Management of Reprocessing Contracts

Transport of CASTOR® HLW-Casksfrom La Hague to Gorleben


Interim Storage Facilities

Pilot Conditioning Plant (PKA)

Spent Fuel and HLW

LLW and ILW

Gorleben Site


Ahaus Site

Interim Storage Facilities

Spent Fuel, ILW/LLW(in the future: CSD-C)

Ahaus Site

GNS has developed and manufactured a variety of casks for High Active Waste and Spent Fuel:

Nuclear Casks

More than 1200 already loaded and ininterim storage

Germany 976

Lithuania (Ignalina) 118

Czech Republic (Dukovany, Temelin) 90

USA 35

Belgium 7

Switzerland 6

South Africa 4

Bulgaria (Kozloduy) 1as of December 2012


CASTOR® HAW20/28CG

CASTOR® V/52 CASTOR® 440/84CASTOR® THTR/AVR

CASTOR®-Casks


Assembly of Casks

Assembly and Preparation for Delivery in the GNS-Cask-Manufacturing Mülheim



Work and Testing in the Salt Dome

Preparation for Final Disposal



Pilot Conditioning Plant (PKA)

Gorleben Site



Pilot Conditioning Plant in Gorleben

Staff recreation

area

Cell area

Cask area

Pilot Conditioning Plant (PKA), Gorleben

Cooperation with ITALCERT

Cooperation agreement since 1987

Memorandum of Understanding 2009

Common Projects: Caorso NPP, treatment of Resins (contract 1986-1997) Trisaia ENEA, treatment of contaminated drums Incineration of medical wastes SOGIN CASTOR® casks (contract management)

Various Tenders for Italian Clients CORA Project CEMEX, Plant for Saluggia


ITALCERT


Many thanks for

your attention!

Light at the End of the Tunnel?

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Role of GNS in the German Treatment of Radioactive ... Polytechnic_Mailand_0… · Role of GNS in the German Treatment of Radioactive Operational & Decommissioning Waste ... specialised