the influence of policy changes in spent fuel … · 2019-01-25 · outline 17.07.2018 wolff, iaea...

THE INFLUENCE OF POLICY CHANGES IN SPENT FUEL MANAGEMENT IN GERMANY ON THE APPROACH OF STORING SPENT FUEL IN DUAL PURPOSE CASKS

Dietmar Wolff, Holger Völzke

17.07.2018

IAEA Technical Meeting on Integrated Approaches to the Back End of the Fuel CycleVienna, AustriaJuly 17-19, 2018

Outline

17.07.2018 Wolff, IAEA TM on Integrated Approaches to the Back End of the Fuel Cycle - Vienna, Austria

I. German Nuclear Waste Management Policy

II. Dry Interim Storage of Spent Fuel and HLW in Dual Purpose Casks

III. Perspectives on Extending Interim Storage Periods

IV. R&D regarding Extended Interim Storage of Dual Purpose Casks

V. German Nuclear Waste Management Policy towards Final Disposal of Spent Fuel and HLW

VI. Summary

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3

Heat generating waste (spent fuel, HLW from reprocessing)

Non-heat generating waste

(LLW/ILW)

Dry interim storage in dual purpose casks on site or at

former central facilities

Nuclear ApplicationsCommercial NPPs, Research reactors, medicine,

other technical and scientific applications, …

Waste conditioning and packaging

(drums, containers, etc.)

Dry interim storage

Final deep geological disposal

Asse until 1978, Morsleben until 1998,

Konrad starting 2027

Final deep geological disposal New site selection process

was started in 2017

Transportation !

Re-Packaging ?!


17.07.2018 Wolff, IAEA TM on Integrated Approaches to the Back End of the Fuel Cycle - Vienna, Austria 4

2011: Nuclear phase-out after Fukushima

immediate shut-down of 8 NPPs and the

remaining 9 until the end of 2022

Past policy changes

Concerning pre-disposal (dry interim storage)2002: Transport ban caused by minor contamination issues,

termination of reprocessing and transition from centralised to

on-site interim storage

Concerning final disposal

2000 – 2010 and after Nov. 2012: Gorleben moratorium and final exploration stop

2013: New „Repository Site Selection Act“ Final site selection until 2031


(Spent Fuel and HLW)


Phasing-out nuclear electricity production until the end of 2022

NPP Grafenrheinfeld

Dry interim storage of spent fuel and HLW in dual purpose casks will be necessary until final disposal

Transport and storage casks in the Gorleben storage facility (Photo: GNS)

Total fuel amount:10,500 Mg spent fuel 6,700 Mg reprocessed

Finally 1,900 loaded casks after 2025

▪ 2 former central storage facilities▪ 12 on-site interim storage facilities for

LWR fuel▪ Interim storage North (ZLN) for VVER fuel▪ Interim storage at the Jülich Research

Center for AVR fuel


(Spent Fuel and HLW)

New site selection process for final deep geological

disposal !!!


The initial storage concept from the 1980s

▪ Dry storage of spent fuel and high-level waste from reprocessing in accident safe transport and storage dual purpose casks (DPC)

▪ Centralized interim storage at two sites (Ahaus, Gorleben)

▪ Conditioning plant and repository at the same place (Gorleben)

▪ Repository available until 2035

▪ Sufficient interim storage period of max. 40 years

II. Dry Interim Storage of Spent Fuel and HLW

in Dual Purpose Casks


Permanently monitored

bolted double barrier lid

system with metal seals

Inert cask interior: vacuum dried and

helium filledGNS CASTOR® V/19

Corrosion protection

of outer surfaces

▪ Site specific safety evaluation of casks and specific inventories performed for 40 years

▪ Accident safe (robust) dual purpose cask designs for storage and transportation

▪ Valid Type B(U) package design approval required before loading and during storage to guarantee permanent transportability


in Dual Purpose Casks (major safety features)


Regulatory guidance documents issued by the

Nuclear Waste Management Commission (ESK):

Guidelines for dry cask storage of spent fuel and heat-generating waste Revised version of 10.06.2013

ESK guidelines for the performance of periodic safety reviews and on technical ageing management for storage facilities for spent fuel and heat-generating radioactive waste13.03.2014

Storage licenses issued by The Federal Office for the Safety of Nuclear Waste Management (BfE, the former BfS) under §6 AtG (German Atomic Energy Act)

http://www.entsorgungskommission.de/en/node/93


in Dual Purpose Casks (regulatory framework)


Discussion paper on the extended storage of spent fuel and other heat-generating radioactive waste” (Oct 2015)


Major topics

▪ Long-term aspects of cask suitability and future expectations based on the current experiences

▪ Potential lack of knowledge regarding spent fuel and other inventories (gap analysis)

▪ Issues on transportation after storage

▪ Citation: “For extended storage, the need for additional safety assessments in terms of long-term behaviour and potential changes in properties and condition of all above-mentioned inventories and additional cask internals (such as baskets and filter cartridges) is foreseeable”

▪ Alternative concepts for the extended interim storage:

1) Extended interim storage at current sites

2) Consolidated interim storage at a few regional sites

3) Centralized interim storage potentially at the future repository location

III. Perspectives on Extending Interim

Storage Periods


Discussion paper on the extended storage of spent fuel and other heat-generating radioactive waste” (Oct 2015)


Further topics

▪ Licensing issues

Any extension of storage periods whether for existing or new sites requires a new storage license

▪ A specific regulatory framework for the specific needs of future spent fuel management after shutting down all nuclear power plants should be beneficial

▪ Knowledge management to be provided by storage operators, cask manufacturers, authorities and technical expert organizations

▪ Economical and ethical aspects

▪ Discussion of the current regulatory system including responsible authorities and their interaction in the areas of storage, transportation, conditioning and disposal

▪ Consideration of the needs for subsequent final disposal

III. Perspectives on Extending Interim

Storage Periods


Horizon 2020

March 2017 !

National funding programs addressing nuclear waste management

BMBF BMWi BMU

BAM R&D Program

Research for the disposal of radioactive waste

Research for the decommissioning of nuclear installations

IV. R&D regarding Extended Interim Storage

of Dual Purpose Casks


R&D areas

Area 1: Impacts of extended interim storage periods on wastes and containers

1.1: Wastes (e.g. spent fuel behaviour)

1.2: Containers (e.g. integrity and leak-tightness, monitoring, handling, transportability)

1.3: Interim storage system (e.g. ageing management, monitoring techniques,

accident and safety analyses)

Area 2: Scientific basics for site selection

Area 3: Disposal concepts and techniques

Area 4: Safety case

Area 5: Knowledge management and socio-technical aspects

Area 6: Safeguards

Research for the disposal of radioactive waste (2015-2018)




Long-term performance is validated and confirmed for 40 years so far, but has to be demonstrated for extended periods of time. (For example, BAM is investigating long-term performance of bolted closure system components and neutron shielding polymeric materials.)

Various BWR, PWR, and VVER fuel types, canisters with vitrified HLW, THTR und AVR stainless steel cans, canisters for defect fuel rods and damaged fuel assemblies have to be considered.

Requirements may result from anticipated activity releases into the cask cavity during storage and subsequent transportation or requirements concerning handling abilities of fuel assemblies after storage for unloading and reconditioning.

Internationally, potential cladding failure is discussed as relevant safety issue:

▪ Major concern: Potential embrittlement by hydride reorientation at lower temperature levels during long term storage.

▪ Germany: After loading of all casks probably until around 2025 there is no chance anymore to determine initial fuel assembly properties prior to storage.

Long-term Performance of Cask Components and Inventory




▪ An interpretation of the term “highest possible safety level” and the procedure

towards a disposal site with the highest possible safety level

▪ Necessary interim storage prior to disposal (addressed in Part B chapter 5.7

and requirements for disposal canisters in Part B chapter 6.8)

▪ The restructuring of responsible authorities and organizations

„Repository Site Selection Act“ entering into force in July 2013

German Disposal Commission launched in April 20142 alternating chairs + 8 scientists + 8 representatives from social stakeholder organizations + 8 members of the German parliament (Bundestag) + 8 representatives of the states (“Länder”)

Publication of the comprehensive Final Report (ca. 600 pages) for public debate in July 2016 Final version published on Sept. 29, 2016

Recommendations include:

V. German Nuclear Waste Management Policy

towards Final Disposal of Spent Fuel and HLW

15

▪ Generic safety requirements for heat generating waste disposal published by the former Federal Ministry for the Environment (BMU) (2010)

▪ ESK “Recommendations on requirements for disposal packages for the

disposal of heat generating radioactive waste” (March 2016)

Generic safety requirements and the role of disposal packages in general and along with manufacturing, repository operation and the post-operational phase

▪ Final report of the Disposal Commission (Sept 2016)

▪ Final Report of the KFK (Commission to ensure the financing of the nuclear energy exit) (April 2016)

Federal responsibility for interim storage and final disposal of spent fuel and radioactive waste (siting, construction, operation, closure/decommissioning)

Financial compensation to be paid by utilities ≈ 24.1 billion Euros in total (federal funds)

Utilities remain responsible for NPP decommissioning and waste packaging

Way forward to final HLW and spent fuel disposal

New legislation (2016/2017)

Restructuring of responsible

organisations (completed by the end of 2017)

Reorganization of responsibility in nuclear waste management

(completed by the end of 2019)




Restructuring of responsible authorities and organizations in nuclear waste management (as ruled by law in July 2016)

BMUFederal Ministry for the

Environment, Nature Conversation and Nuclear Safety

BGEThe Federal Company for

Radioactive Waste Disposal

Project lead of the SF/HLW repository siting procedure

Konrad repository (LLW/ILW)

ASSE II

Morsleben repository (LLW/ILW)

Project Management and Operation

Nuclear RegulationNuclear licensing and

supervision

BfE

Regulation of the SF/HLW repository siting

procedure

Licensing of SF/HLW interim storage and

transportation

Nuclear licensing and supervision of

LLW/ILW repositories

Legal and Technical Supervision

(Company for Interim Storage)




Actors in the repository siting process

Federal Parliament / States (Länder) Parliament

Federal Office for the Safety of Nuclear

Waste Management (BfE)

Federal Company for Radioactive Waste

Disposal (BGE)

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Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU)

National Monitoring Panel

Citizens

Expert conferences subareas

Regionally affected population

Public support

Technical support

Technical supervision Participating administration

Regulation




Repository siting procedure: Status and outlook

05 Sept. 2017: Opening event of the site selection procedure hosted by BGE

StandAG (Repository Site Selection Act).

Aim: To find the best possible repository site for mainly heat-generating

radioactive waste.

Phase 1 Phase 2 Phase 3

Identification of potential regions for near surface exploration

(geological data base; exclusion criteria, minimum requirements)

Identification of areas with most favourable conditions for all

three host rock types (salt, crystalline, clay)

Determination of at least three locations for near surface

exploration

Near surface exploration and proposal for underground

exploration

Final decision about underground exploration

Definition of site specific exploration programs and

evaluation criteria

In depth geological exploration

Final site comparison and repository site proposal

Final site selectionuntil

2031





Timeline towards disposal

▪ 2017 Launching the new repository siting procedure

▪ 2031: Final HLW repository site selection

▪ Repository licensing and construction

▪ > 2050: Earliest start of repository operations

▪ Spent fuel and HLW disposal ending between > 2080 and 2130 or even later

▪ Repository closure between > 2090 and 2160 or even later

Interim spent fuel and HLW storage since 1992

Final cask loading and closure 2025/27

First cask towards disposal after 2050

Last casks towards disposal 2080/2130 or even later

Foreseeable extension of interim storage between 30 and >80 (100) years for at least a relevant number of casks

CASTOR® THTR/AVR casks in the Jülich Research Center interim storage (license expired)



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Timeline

1992 2025/27

Cask loading for interim storage

2017

Repository site selection

procedure

2031 > 2055

Repository licensing and construction

Repository closure

> 2090

Expiration of interim storage licenses after

40 years

HLW and spent fuel disposal

Extended interim storage





▪ The initial German spent fuel and HLW management concept has been adapted to the needs of the nuclear phase-out decision.

▪ Restructuring of the responsible authorities and organizations is under way and the HLW repository siting process has been restarted with the goal to decide about the location by 2031.

▪ The concept of dry interim storage in dual purpose casks has proven to be a safe and secure spent fuel management strategy for almost 25 years in operation, but for the future storage needs, it has to be extended beyond the initial license period of currently 40 years.

▪ For future extended storage licenses data gaps concerning the long-term performance of cask materials and components and also the internals need to be identified and addressed in due time.

▪ BAM has been performing safety evaluation of nuclear packages for more than 30 years, is comprehensively engaged in international collaboration and performs scientific investigations to understand ageing effects with regard to the long-term performance of cask materials and components.

VI. Summary

the influence of policy changes in spent fuel … · 2019-01-25 · outline 17.07.2018 wolff, iaea...

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