Pastina[1].pdf

8/9/2019 Pastina[1].pdf

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Safe radioactive waste disposal:

from vision to practice

11/5/2013 1

Barbara Pastina

Saanio & Riekkola Oy

ATOMECO 2013 Moscow, 30-31.10.2013


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Spent fuel management

organisation AUTHORISATIONS

OVERSIGHT

RAD WASTE

MANAGEMENT FUNDING

Nuclear waste fund

managed by TEM

Ministry of Employement

and Economy (TEM)

Säteilyturvakeskus (STUK)

Consulting firms, research

institutes (e.g. VTT), universities


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Status of spent nuclear fuel

management in Finland

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Total: 9000tU of SNF

4 500 canisters

800-900 W/tU after 30y


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Olkiluoto spent nuclear fuel repository


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The KBS-3 method

• Sites: Olkiluoto

(Finland), Forsmark

(Sweden)• Granitic host rock

• Depth 400-500 m

• Reducing conditions

28.06.2010 5

KBS-3V KBS-3H


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Legal requirements

& other constraints

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System understanding

•Site

•Waste streams

•FEPs

Disposal

method

Design &

technical development

Safety case

Next stage

Site characterisation,design & technicaldevelopment

S a f e t y a s s e s s m e

n t


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Finnish safety case

• Safety case for KBS-3V design (main)

– Safety case for KBS-3H design

(alternative) joint project with SKB• Both developed according to the

Nuclear Energy Agency and IAEA

guidelines• Structured as a report ”portfolio”

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8

Complementary Considerations

Assessment of

RadionuclideRelease Scenarios

for the Repository

System

Biosphere Assessment

Models and Data for

the Repository

System

Biosphere Assessment

Data Basis

Biosphere Assessment: Modelling reports

Formulation of Radionuclide Release Scenarios

Features, Events and Processes

Performance Assessment

Production Lines

Description of the Disposal System

Design Basis

TURVA-2012

Synthesis

Site Description Biosphere Description

Main supporting reports

Safety case portfolio reports

S a f e t y

c a s e p o r t

f o l i o T U R V

A - 2 0 1 2

TURVA -2012

3238 pages not including the

supporting reports


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Lessons learned in geologic

disposal of SNF

• Integrate site characterisation data (above

and below ground) iteratively in repository

layout and in safety case• Apply a step-wise approach for the R&D

programme

• Establish & manage the requirements early on

• Communicate effectively among site

characterisation, repository design and long-

term safety

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Incorporating site data into the safety case

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Lessons learned from the site

selection process

• The site selection process approach should be

stepwise and systematic in the early phases

• Stepwise means that the results of the earlier phases

are used to guide the investigations in the next steps.

• Focus on more site-specific features for the last sites

• The suitability of the final site must be confirmed by

underground investigations

– Ideally using an underground characterisation facility, as in

Finland (ONKALO)

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From site characterisation to

Host Rock Classification


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Lessons learned on management

and cost estimates

• Understanding the interaction between design, costs

and safety is essential

• Cost estimates should begin in the very early phase

• Cost estimates should be always in real-time

• Cost estimates show where to concentrate resources

from the cost point of view

• Cost estimates are one of the tools for a successful

project management

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Case of Russian Federation

geologic disposal programme

• Vitrified HLW (decay heat


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- 80 m: Decommissioning

Waste Repository (LargeScale Components)

- 195 m: Low &

Intermediate Level Waste

(LILW) Repository

- 315 m: Underground

Research Laboratory

(URL) and Demonstration

Tunnels

- 470 m: vitrified HLW (class 1)

Oversized

Access Tunnel

Technical Rooms

& Vehicle Parking

Shafts &

Connections

Saanio & Riekkola, 16.9.2013

S i & Ri kk l k h


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Saanio & Riekkola know-how

related to the disposal of radioactive waste

Repository Technology

• Technical design of nuclear waste repositories• Layout adaptation to site specific conditions

• Description of operation

• Management of technical requirements

• Backfilling technology

• Environmental impact analysis

• Cost estimates of the repositories

Design

• Main design

• Layout design

• HVAC design

• Project development• Structural design


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Long-Term Safety• Management of safety requirements

• Integration of site and engineered barrier

system into long-term safety assessment

• Features, events and processes

• Performance assessment

• Formulation of radionuclide release

scenarios

• Complementary considerations (e.g.

natural analogues)• Planning and management of safety

case


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Rock Engineering Department• Rock mechanical analyses

• Risk analyses

• Time schedules and cost estimates

• Life cycle analyses of rock caverns

• Geological modeling

• Rock engineering mapping

• Groundwater flow modeling

• Groundwater analysis

• Inflow analysis

• Estimations for sealing requirement

• Planning and management of monitoring

measurements


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Bentonite laboratory (B+Tech Oy)

• Research and development on

clay-based engineered barriers

for spent nuclear fuel disposal.

• Specialised clay laboratory and

experimental facilitïes

• Modeling capabilities to study

clay-based barriers

• Detailed information is providedat www.btech.fi.

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Major Clients and References

– Nuclear Waste

• Posiva (Finland), URL (Onkalo) and HLW

disposal facility

• TVO (Finland), LILW disposal facility• SKB (Sweden), HLW disposal facility

• KEPCO E&C/KRMC (Korea), LILW disposal

facility

• KAERI (Korea), URL and HLW disposal

facility

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Thank you!

Contact:Timo SaanioVice President

[email protected]

tel. +358 09 566 6500 (office)

+358 40 506 5671 (mobile)

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mailto:[email protected]:[email protected]


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Repository design and site

characterisation reports

• WR 2012-50 Repository design 2012• WR 2012-24 Rock Suitability classification – RSC 2012.

• POSIVA 2012-19 Design, Production and Initial state of the Underground

Disposal Facility Closure

• WR 2011-32 Foreign Materials in the Repository - Update of Estimated

Quantities• WR 2010-17 Drilling and Associated Drillhole Measurements of the

Investigation Holes in the EDZ Tunnel at Chainage 3620

• WR 2008-83 Assessment of the Potential for Rock Spalling at the Olkiluoto

Site

• WR 2008-66 EDZ Programme, EDZ Studies in ONKALO 2007-2008

• WR 2008-45 R20 Programme: Development of Rock Grouting Design,

Techniques and Procedures for ONKALO

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www.posiva.fi


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23

KBS-3V Safety Case Reports

• POSIVA 2012-12 Synthesis report

• POSIVA 2011-02 Olkiluoto Site Description 2011

• POSIVA 2012-04 Performance Assessment 2012

• POSIVA 2012-05 Description of the Disposal System 2012

• POSIVA 2012-06 Olkiluoto Biosphere Description 2012

• POSIVA 2012-07 Features, Events and Processes 2012

• POSIVA 2012-08 Formulation of Radionuclide Release

Scenarios 2012

• POSIVA 2012-10 Biosphere Assessment BSA-2012

• POSIVA 2012-11 Complementary Considerations 2012

• POSIVA 2013-01 Models and Data for the Repository System

2012

www.posiva.fi


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KBS-3H related reports

• POSIVA 2008-01 KBS-3H Design Description 2007

• POSIVA 2007-09 KBS-3H Process report,

• POSIVA 2007-08 KBS-3H Evolution report,

• POSIVA 2007-07 KBS-3H Radionuclide Release and Transport

reports

• POSIVA 2007-10 Safety assessment for a KBS-3H spent nuclear

fuel repository at Olkiluoto - Complementary evaluations of safety

report

• POSIVA 2008-03 Horizontal Deposition of Canisters for Spent

Nuclear Fuel. Summary of the KBS-3H Project 2004-2007• SKB TR 12-01 KBS-3H Complementary studies 2008-2010.

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www.posiva.fi


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• Founded 1962

• Main office in Helsinki, Finland

• Branch office in Seoul, South Korea

• ISO 9001:2008 quality management

system

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Olkiluoto LILW

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C O N T R O L

B U I L D I N G

T R A N S P O R T T U N N E L

H A L L

W A S T E

S I L O S

R E S E A R C H

T U N N E L

E X P E R I M E N T A LD E P O S I T I O N H O L E S

SHAFT

LOW LEVEL

WASTE

MEDIUM LEVEL

WASTEC O N S T R U C T I O N T U N N E L


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Forsmark HLW

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South Korea HLW

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Wolsong LILW

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Service Business Areas of


UndergroundFacilities

NuclearWaste

ManagementMining

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Technical Consultation Services

Documents

Pastina[1].pdf