Transcript

© 2015 Organisation for Economic Co-operation and Development

Decommissioning the Fukushima

Daiichi Site: A Global Challenge

William D. Magwood, IV Director-General

Nuclear Energy Agency

First International Forum on the Decommissioning of the Fukushima Daiichi NPS

April 10, 2016

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The NEA: A Forum for Cooperation

• Founded in 1958

• 31 member countries

• 7 standing technical committees

• 75 working parties and expert groups

• 21 international joint projects

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The NEA's committees bring together top governmental officials and technical specialists from NEA member countries and strategic partners to solve difficult problems, establish best practices and to promote international collaboration

NEA Committee Structure

3

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Fukushima Daiichi: Reviewing Post-Accident Recovery

Lessons Learned

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Key Message from Stakeholder Dialogues: “Decommission Quickly!”

NEA supported 12 dialogue sessions organised by ICRP between 2011 and 2015, with stakeholders from affected areas of Fukushima Prefecture

• Addressed many stakeholder concerns regarding radiological safety

• Reflected desire of residents to regain control of their lives and to return to normality

• Important message from those who evacuated and have not returned: “We might return, but only if the site is safe.”

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Lessons from the Stakeholder Dialogues

• Trust is a necessary and central component of successful stakeholder engagement.

• Successful stakeholder engagement provides information and support to enable stakeholders to make informed decisions and develop a positive vision of their future.

• It is essential to clearly acknowledge the validity of all individual decisions (i.e., whether to stay in an affected area or to relocate).

• Must plan for long-term technical support to stakeholders--not just short-term responses. Recognize that this can be very resource intensive.

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Post-Accident Food Management

• The Fukushima accident demonstrated the complexities and sensitivities of post-accident food consumption and trade.

• NEA developed a comprehensive approach to post-accident food management that provides consistent criteria for:

- Local consumption - Domestic markets - Export - Import

To build confidence, an international verification mechanism is needed.

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Post-Accident Food Management: Remaining Issues

• Vital to assure establishment of clear, verifiable criteria and processes to support export and import of food productions while protecting domestic markets.

• Effective verification would address:

- How are consumption criteria set? • Consumption assumptions

• Dose calculation process

- What is the process for food certification? • Measurement equipment

• Measurement processes

The NEA is exploring approaches for the international community to

provide greater assurance

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Lessons for Operating Plants Around the World

• As-built conditions may not match drawings

– Many plants have structures and features not fully reflected in drawings that might be referenced after an accident

• Important work areas, e.g. beneath reactor vessel, operating deck, etc., may be inaccessible due to dose rates

• Some equipment may require recertification (e.g. cranes, refuelling bridge, etc.)

– Access and operability needed to recover from significant on-site disaster

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Advances are Needed in Remote and Robotic Work

• Most work will be in “unique work environments” – conventional equipment tooling insufficient

– Dose rates will be very high in significant areas

– Often will require robotic characterisation

– Actual work best addressed via remotely operated tools rather than robotics

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Major Ongoing NEA Efforts: EGFWMD

• Purpose: Evaluating the management of post-accident waste

• Provides a strategic approach to the Japanese government to manage waste characterization process (sampling and analysis plan)

• Members: France, Korea, Norway, Russia, United Kingdom, Ukraine, United States, and Japan (NRA, JAEA, TEPCO)

• Report to be issued 2Q of 2016

Expert Group on Fukushima Waste

Management and Decommissioning R&D Structure of Work for EGFWMD

1. International Case Studies

2. Regulator / Implementer Interaction

3. Stakeholder Involvement

4. Physical and Chemical Nature of the Waste

5. Radiological Characterisation

6. Waste Classification and Categorization

7. Waste Conditioning, Decontamination, and Reduction

8. Destination (storage / disposal)

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Major Conclusions from EGFWMD

• A holistic waste management strategy must be established, based on a

sufficient number of material contamination measurements and meaningful

waste classification.

• Optimization is an important aspect of radiological protection and should

include not only radiological factors, but also social and economic factors.

• Radioactive waste exceeding the limits for near-surface or intermediate-

depth disposal is generated by post-accident decommissioning activities;

appropriate storage and stabilization is required until a final disposal

approach is developed.

EGFWMD Tokyo Workshop 6-7 July 2016

Iino Hall and Conference Center, Tokyo, Japan

Organized by the NEA and hosted by METI, IRID, others TBD

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Major Ongoing NEA Efforts: BSAF

• Purpose: Drawing from actual experience at Fukushima Daiichi to verify severe accident codes

• Members: France, Germany, Korea, Russia, Spain, Switzerland, United States, and Japan (JAEA, IAE, NRA, CRIEPI)

• Phase 1 completed 2015

• Phase 2 approved and soon to begin

Benchmark Study of the Accident at the

Fukushima Daiichi Nuclear Power Station

Phase 1: Codes show similar results in

predicting Unit 1 water levels and RPV pressure

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Major Results from BSAF and Next Steps

Phase 1 – Completed 2015

• A total of 13 different severe accident codes from around the world were

used to analyse the first six-days of thermal-hydraulics in 1F reactor vessels

• BSAF phase 1 results showed that when the boundary conditions are well

known and fixed, the codes provide comparable agreement of the

thermal-hydraulics phase, as well as the fuel temperature excursion

phase.

Phase 2 – Agreement Recently Adopted

• BSAF phase 2 will build upon the phase 1 results to assess severe accident

code comparisons out to three-weeks after accident initiation as well as

further information on fuel debris location. These results can be used to

support Japan’s planning efforts aimed at addressing the damaged

cores.

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Major Ongoing NEA Efforts: SAREF

• Purpose: Identifying research opportunities from Fukushima Daiichi to advance safety knowledge and to support safe decommissioning.

• Members: Canada, Czech Republic, Finland, France, Germany, Italy, Japan, Republic of Korea, Spain, Switzerland, United Kingdom and the United States

• Report expected to be issued 3Q of 2016

Senior Expert Group on Safety Research

Opportunities Post-Fukushima • Status of SAREF Effort To Date

• Many research areas of common interest were identified.

• Potential long-term and near-term projects will be included in final report to NEA’s CSNI in June 2016.

• Near term project recommendations include:

– Fuel debris characterisation and simulation

– Reactor and containment building examinations and water sampling

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Concluding Thoughts • A complete and sustainable waste management strategy is needed as

early as possible.

• Public confidence would benefit from additional transparency regarding progress toward stabilisation of damaged 1F units

• Robotic technologies are best-suited to surveys and characterisation, advanced remote tools are needed for most decommissioning tasks

• Post-accident food safety management remains an international issue—NEA has developed a food-safety framework and is now reviewing options for an international verification process

• While decommissioning must proceed, it is also vital for Japan and the International community to continue learning from the accident through advanced safety research such as being pursued through BSAF and SAREF

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Thank you for your attention

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