The International Project on Irradiated Graphite

Processing Approaches (GRAPA)

Michael I. Ojovan, Patrick O’Sullivan

Waste Technology Section,

Department of Nuclear Energy, IAEA

International Atomic Energy Agency

IAEA

• The IAEA promotes safe and effective management of radioactive waste and has suitable programmes in place to serve the needs of Member States in this area.

• Technical assistance in predisposal area is delivered through publication of technical documents, coordinated research projects, technical cooperation projects, training, networks and peer review services.

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Many of the older reactors are now shut down, with more

approaching the end of their lives, and some

250000 tonnes of radioactive graphite (i-graphite) have now

accumulated world-wide.

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• 1984: Keynote EU analysis

• 1995: IAEA Technical Meeting “Graphite Moderator Lifecycle Technologies”, Bath UK

• 1999: IAEA Technical Meeting “Nuclear Graphite Waste Management”, Manchester, UK

• 2006 – 2012: EPRI “Graphite Decommissioning Initiative” – a six-volume study

• 2007: IAEA Technical Meeting “Progress in Radioactive Waste Management”, Manchester, UK

• 2008: EU CARBOWASTE project commences

• 2011 – 2014: IAEA Coordinated Research Project “Processing of Irradiated Graphite to meet Acceptance Criteria for Waste Disposal”

• 2016 - on: International Decommissioning Network establishes Project GRAPA

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The CRP has explored both innovative and conventional methods for graphite

characterisation, retrieval, treatment, and conditioning technologies and produced an

IAEA technical document which has identified a number of unresolved scientific and

technical issues such as the need to:

I. Improve the scientific understanding required on creation, chemical form ,

location and release behaviour (transport models) of radionuclides;

II. Improve predictive models of radioisotope behaviour;

III. Ensure that sampling programmes are statistically representative of the totality of

the graphite to be disposed of;

IV. Establish an accurate radionuclide inventory;

V. Consider novel alternative dismantling and treatment strategies.

The IAEA Coordinated Research Project (CRP) under the title

'Treatment of Irradiated Graphite to Meet Acceptance Criteria

for Waste Disposal' was conducted during 2010-2014 and has

involved 24 organisations from 10 Member States.

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The CRP promoted the exchange of technical information on R&D

activities to facilitate practical application for treatment and conditioning

of i-graphite waste. The collaboration continues under the IAEA

International Decommissioning and Predisposal Networks (IDN, IPN).

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TECDOC-1790 (includes update and wider commentary in each

section, not just activities of CRP participants)

1. Introduction

2. Graphite-Management Issues

3. Organisation of CRP Work Programme

4. Characterisation of Irradiated Graphite

5. Processing and Treatment of i-Graphite

6. Immobilisation of irradiated Graphite

7. Disposal of Irradiated Graphite

8. Summary and Conclusions

9. Cooperation Achieved / Country Work Summaries

10. CD-ROM containing detailed technical reports from participants

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Cementation of i-Graphite

Issues:

Objective: Immobilisation

Chemical formulation of cement

Optimum packing fraction – break up the graphite?

If LLW – can go straight to

near-surface disposal

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Disperse in Concrete

• Paul Scherrer Institute, Switzerland DIORIT, 45 t Graphite treated: 60 tonnes from PROTEUS to follow

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Graphite-Loaded Glass as Matrix for other

Radwaste (FNAG Proposal)

80% graphite, 20% glass

High density (2.23 g.cm-3) – regarded as ‘impermeable’

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Thermal: calcination

• GLEEP graphite (UK): (very low active) crumbled and calcined at ~1100°C: • Approx 60% of 14C and 80% of 3H removed in about 3

hours using an industrial ‘incinerator’ – not a ‘controlled’ experiment;

• AVR (Germany): Podruzhina pioneered similar results under lab conditions using a variety of different atmospheres (work continued under CARBOWASTE)

• Mechanisms not well understood, and debate continues about the location of the 14C within the graphite structure and porosity (dependant both upon the dominant production route and upon propensity for diffusion within the solid and the pore structure)

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• To further support Member States in resolving i-graphite

management up to industrial implementation of processing

technologies the IAEA has recently launched an International

Project on Irradiated Graphite Processing Approaches

(GRAPA).

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I-Graphite management - previous projects

EU 7th Framework

programme

CARRERA ?

Basic R & D R & D on Application

Release of C-14

Recycling and Reuse of C-14

Closing the C-14 cycle

C-14 Source Term

(partly i-Graphite)

Carbon

ForeST

Disposal of C-14- Waste

from HTR & MTR Reactors

2010 2009 2008 2012 2013 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 2011

Germany

Comprehensive Study Modular & Holistic View

(application-oriented)

Rosatom/BMWi-Project (Disposal)

CarboDisp

EU CarboWaste

EU CAST

IAEA CRP IAEA GRAPA

Russia

Options & Solutions

EU „Carbo Solutions“

Thematic area of the

Russian/German expert group

IAEA

Finding Solutions

Science

Practice

Resources

Permits

Logistics

Legal

Framework

Deadlines

Targets

Budgets

Infrastructure

Safety

Experience

Politics

Regulations

Organisation

Strategy

Technology

Technology

Equipment

The Challenge: Common application-

oriented approach

IAEA

GRAPA Project Management

Structure

Scientific-Technical Gaps A

Industrial Applications B

Chairman: Anthony J. Wickham

Scientific Officers: Michael I. Ojovan & Patrick J. O‘Sullivan

Topics: Co-Chairs

Subprojects: Teams

Umbrella Studies

Projects

Synergie & Achievement Evaluations

Operators / Site Managers

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Waste Technology Section

Co-Chairs

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GRAPA Umbrella Studies (Cluster 1)

1.1 Radiological Characterisation

1.2 Leachíng Informationj

1.3 Modelling

1.4 Isotope Distribution (Samples) & Correlation

1.5 Wigner Energy

2.1 Nibble & Vaccum

2.2 Whole Block Retrieval

2.3 Underwater Dismantling

2.4 Water Jet Cutting / Fluid Transport

3.1 Incineration (incl. Plasma)

3.2 Hot Isostatic Pressing

3.3 Microwave

3.4 Thermal Decontamination

3.5 Chemical (incl. Molten Salt)

4.1 Isotope Ratios of Bulks

4.2 Large Scale Classification

5.1 Conditioning

5.2 System Container/Waste Product

6.1 On-site Decommissioning / Entombment

6.2 Shallow Disposal

6.3 Deep Disposal

6.4 Potential Exposure Reduction (PER)

⑤ Packaging

① Characterisation

② Removal /

Retrieval

③ Treatment

④ Measurement

⑥ Storage /

Disposal

IAEA

Entscheidungskriterien

Bugey I

Synergies & Achievements Site Studies ❸

Ignalina Chernobyl Latina

ISPRA I

Tomsk

Others

Others

Steps towards application

Holistic Views State-of-Art Studies

Details Subprojects on Specific Items

Industrial Applications

Res ults

Inp

ut

Data Pool

Techniques

Methods

❷

Physical / Chemical

3 Clusters

❶ A Scientific-Technical

Gaps

Technology Readiness Level (TRL) – Assessing status of

developments

Sources: wikipedia

IAEA

From Laboratory to Application Scenario Diagramm (TRL vs Applicability)

Technically developed, 100%

Universal

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3.3

1.1

2.2

6.2

4.2

2.1

1.3

1.2

1.5

4.1

individual

Basic R&D

Packaging

(Surface Chemistry & )

Modelling Classification

(Samples)

Classification

(Large Scale)

Bulk Isotope Ratios

Microwave Heating

Nibble & Vacuum

Removal of Blocks

Shallow Disposal

Leaching

Information

Wigner Energy

GR

AP

A

all sites one site

TRL

5

TRL

9

TRL

1

TRL

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Technically developed, 100%

Universal (all sites)

3.3

1.1

4.

2

1.3

4.1

From Laboratory to Application Dependences of GRAPA subjects

individual

Basic R&D

4.

2

1.2

1.1 Classification (Laboratory)

1.2 Leaching Information

1.3 (Surface Chemistry &)

Modelling

3.3 Microwave Heating

4.1 Isotope Ratios

4.2 Classification (Large-Scale)

Bulk Classification

IAEA

Technical Meeting on the International Project on Irradiated

Graphite Processing Approaches (GRAPA)

9 – 12 February 2016, IAEA, Vienna, Austria 22

IAEA Consultants Meeting on the “International Project on Irradiated

Graphite Processing Approaches (GRAPA)”, 8 – 11 November 2016, Vienna, Austria, IAEA

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The ‘GRAPA’ programme commenced in February 2016 and will

continue until 2018 at which point the entire programme

will be reviewed in the context of the ongoing requirements for

radioactive waste disposal within the individual Member States of

the IAEA. Sub-topic results will be reported individually, and there

will be a comprehensive final report.

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IAEA Thank you!

Event Meeting Scheduled for

EVT1703162 Technical Meeting on the International

Project on Irradiated Graphite Processing

Approaches (GRAPA)

10-14 September 2018

Visaginas, Ignalina NPP,

Lithuania

EVT1702905 Consultancy Meeting on the International

Project on Irradiated Graphite Processing

Approaches (GRAPA)

13-16 February 2018

IAEA, Vienna, Austria