NUMO’s Safety Strategyfor implementing
Geological Disposal Project
Nuclear Safety Research Forum 2010
Tokyo, Japan23 February, 2010
Hiroyuki Tsuchi
Nuclear Waste Management
Organization of Japan (NUMO)
Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Nuclear fuel cycle
Uranium mine
Fuel fabrication

HLW (approx. 5%)

Recovery of uranium/plutonium (approx. 95%)

Fuel

Reprocessing

MOX fabrication

Spent fuelNuclear power
generation

LLW for geologicaldisposal
Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Classification of radioactive wastes & disposal methods
GenerationpointCategory

Sub-surface

Uranium waste

Sub-surface

HLW

HLW

Reprocessing
plant

Sub-surface
GeologicalPit disposal

50100300

Near-surface
TRU waste25

Sub-surface
disposalGeological(undecided)

Reprocessing/MOX
fabrication
plantsDepth[m]0 LowGeologicaldisposal inmore than
300m deep
undergroundRadioactivity

Near-surface

Nuclear power plant
waste

HLLW

TRU waste

LLW

Uranium waste

Near-surface

LLW

Uraniumenrichment/ fuelfabrication
plantsTrench disposal

VLLW

Nuclear power plant
waste

Nuclear powerplant

Disposal method

Example of disposal

GeologicalHigh

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Classification of specified radioactive wastes
HLW
Specific 1stradioactive
Waste

Hull,and Ends

Specific 2ndradioactive
Waste

TRU

Nitric aciddrainHighconcentration
radioactive
waste

Slice
airairSpent silver
adsorbent

Dry andpellet

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010P.3

Layout example of disposal facilities

CoastalInlandSurfacefacilities
Surfacefacilities

Ramp
Shaft

Ramp

Ramp

Shaft

Underground
Facilities（TRU）

Disposal panel
Underground
Facilities（HLW）

Underground
Facilities（TRU）

Disposal panel
Connecting Tunnel
Connecting Tunnel

Underground
Facilities（HLW）

Connecting Tunnel
Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Three Stages of the Selection Process
Preliminary
Investigation
Areas (PIAs)

Detailed
Investigation
Areas (DIAs)

Repository
Site (RS)Volunteer Areas

Selection of PIAs
by Literature
Surveys

Selection of DIAs
by Surface-based
Preliminary
Investigation• Geophysical survey• Borehole drilling, etc

Final Selection ofRepository Site by
Detailed Investigation
including measurements
and tests in theunderground facility

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Report on the
Selection ofPIAs
Design concept
Supporting
Documents

Safety Case 1
NSC:
Nuclear safety Commission

SitingFactors
for DIAs
Report on the
Selection ofDIAs

SitingFactorsfor RS
Report on theFinal Selectionof the Rep.Site

Basic Design &Safety Assessment

Detailed Design &Safety Assessment

Supporting
Documents

Supporting
Documents

Safety Case 2
NSC Basic Guidelines
for Safety Review

Selection of RS

SitingFactorsfor PIAs

Detailed
Investigation

Preliminary
Investigation
Selection of DIAs

Nomination

Literature
SurveySelection of PIAs

OpenSolicitation

Licensing

Stepwise Refinement of the Safety Case

Safety Case 3
NSC Guidelines
for Safety Review

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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NUMO’s R&D Roles
NUMO’s R&D

Utilize results

Improvement of safety and reliability

Suggest needs

Rationalization/
efficiency

Practicality/
sophistication
Application of thefundamental R&D
results
Systematization

DemonstrationRole allocation of R&D on thegeological disposal in linewith the Framework for
Nuclear Energy Policy
NUMO： R&D for safe implementation of therepository with improved technology from
economic and practical perspectives
The Government & relevant organizations
including JAEA:
R&D for establishing the safety-regulation
framework, other fundamental issues
related to safety assessment, geoscientificstudies, and improving repository
technology from the viewpoint of
increasing confidence

Fundamental R&D Coordination Executives
The Government’s
fundamental R&D

・ JAEA and other R&D organizations

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Close cooperation with R&D organizations
NUMO
Necessary technology based on the progress of
repository programme
R&D Planning
R&D Implementation
Evaluation of achievements

plan etc

outcomes

The Government’s fundamental R&D

Fundamental R&D Coordination Executives
JAEA and other R&D organizations

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Reflection of NUMO needs in Government’s fundamental R&D
Objective：
For implementing the geological disposal in line with the recommendation by theAdvisory Committee on the Evaluation of Framework for Nuclear Energy Policy ofAEC, NUMO develops and reflects its R&D needs to the Government’sfundamental R&D plan, from the perspective of the implementer.

Basic policy：
Develop NUMO’s R&D needs systematically, in particular, focusing on thedetailed investigation phase which involves important decision making;
Cover a wide distribution of geo-environmental conditions, considering thesituation where the sites for investigation cannot be identified due to thevolunteer siting approach;
Determine overpack materials, emplacement methods among other important
judgments to be made during the detailed investigation period;
The site-specific needs will be additionally evaluated as appropriate after
volunteer applications received.
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Important NUMO needs (tentative) – 1/2
From viewpoint of “engineering feasibility”
Knowledge accumulation on long-term behaviors/ interactions of
the engineered barriers(e.g. re-establishment of overpack corrosion rate; assessment technology ofcorrosion resistance of welded parts, etc.)

Alternative technologies of the engineered barrier system(e.g. alternative solidification method of TRU waste, etc.）

R&D for improving engineering feasibility of fabrication/transportation/ emplacement of the engineered barriers(e.g. sophistication of element technologies on transportation/ emplacementof engineered barriers using PEM/ block/ pellet)

Confirmation/ demonstration of technologies for investigation/assessment of geological environment(e.g. applicability of technologies for deep geological investigation in coastal/marine areas)
Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Important NUMO needs (tentative) – 2/2
Needs from viewpoint of “safety assessment”
R&D on the performance assessment scenarios based on
probability
R&D on the performance assessment considering the long-term
evolution of geological environment(e.g. standardization/ validation of conditions for performance assessment)

Needs from viewpoint of “long-term safety assessmentof geological environment”
Review on methods/concepts of extremely long-term assessment(e.g. more than 100,000 years)

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Overview of R&D system
Atomic Energy
Commission (AEC)
Basic
policyNuclear Safety
Commission (NSC)

Agency for Natural Resources
and Energy (ANRE)
Supervision

Nuclear and Industrial
Safety Agency (NISA)

NUMO

9Geological investigation /assessment
9Design/ production of the engineered barrier system
9Design/ construction of facilities/ installments
9Repository operation/ closure
9Performance/ safety assessments
・Informationexchange
・Jointresearch・Suggestneeds
・ProvideoutcomesUtilities
R&D from waste-producer
perspective

GuidelineRegulation

Implementation of these activities
R&D required for their implementation

・Technicalsupport
・Teaching

Fundamental
R&D
Coordination
Executives

・Suggest needs
・Confirm outcomes

R&D organizations

・R&D
・Construction
orders/implementation(JAEA/CRIEPI/AIST)

Fundamental R&D

POSIVA, etc.)

Universities

Consultants, Engineering andconstruction companies

Implementation of repositoryproject

Fundamentalresearch

R&D/ design/ construction

Implementers (JNFL/NAGRA/SKB/National
budgetNuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Evaluations and advices by third-party
Promote the project getting evaluations and advices about
the issues such as promotion of public understanding fromdomestic and international experts.
NUMO-hosted international meetings
ITM（International Tectonics Meeting）
Example of achievement; Probabilistic assessment of magmatism

Evaluations and advices for NUMO’s activities
by domestic and international experts
ITAC （ International
TechnicalAdvisoryCommittee)
DTAC（Domestic Technical Advisory Committee）
Example of achievement; Information Package(「Repository Concepts」，「Siting Factors for the Selection of Preliminary Investigation Area」)
Technical Reports(「Technology and Safety of High Level Radioactive Waste Geological Disposal Background andTechnical Justification of Siting Factor for the Selection of Preliminary Investigation Area」)

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Schedule of implementation and R&D of NUMO
Implementation

NUMO is driving to implement the deep geological disposal by doing NUMO’s R&D.
2000

now▼

2002

Open solicitation▼
Establishment of NUMO▼2020

Selection ofSelection ofPIAs▼
DIAs▼
Literature Preliminary
SurveyInvestigation

2040

Selection of a ▼Licensing
repository site▼
Construction,
DetailedOperation,Investigation
ClosureFor open solicitation

NUMO’s R&D- Siting factors for PIAs’ selection- Repository concepts for volunteer siting environment, etc.

For LS and selection of PIAs＞＞＞

- Software supporting for LS- Software developing of repository concepts based on literature information, etc.

For PI and selection of DIAs＞＞＞

- Siting factors for DIAs’ selection- Systematization of geological environmental investigation and evaluation- Improvement of repository design and performance assessment, etc.

For DI and selection of a repository site

Demonstration

For promotion of long-term project

Fundamental
R&D (JAEA)- Important issues of construction, operation and closure- Requirement management system, etc.

Research on the deep geological environment at URLs in Horonobe and Mizunami
Investigation
Investigation
Detailed investigations infrom
thesurface
duringexcavation
research galleriesnd2 report
Improving
thereliabilityofdisposal
technologies
atTokai
R&Dcenter(H12)Generic

Site-specific
Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Current situation of NUMO’s R&D
On-going R&D activities

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Case1: Improvement of assessment technology for seismic/fault activities
Objective: Establish methods for designing seismic-resistant repository; assessing active folds
Characteristics of deep-underground seismic motion
Surface facility

Sedimentary layer
Shallow rock formation

Seismicresistantdesignfor NPP

Surface

Ａｃｃｅｌａｒａｔｉｏｎ （gal)＋repository
Propagation
property

Deep rock formation

ＥＬ-500ｍ
repository

Requiredesigning andassessment ofseismic motion
specific to ‘deep
underground’

Model experiment using CT- scanner

Repository:□ 5m × 5m

ＥＬ-1000ｍ

20 rows × 2 tiers

Identification of relevant active fold zones
1000

Master fault
Fault caused by folding

Branching of fault

Wave growth ratio per 1km (m/106yrs)

Hypocenter
property

Seismic response identified by 2D dynamic analysis

Wave growth=ratio100HL10５6ｙｒｓ
yrs
101000L（ km）

HL

10Shinjo,
Niigata

2m
10.1
0.1

110100

Wave length
Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

P.16Case2: Improvement of technologies for construction/operation systems
Objective: Review comparison of waste emplacement methods; applicability of low alkaline
cementAssessment of vertical/ horizontal emplacement using the Prefabricated EBS
Module (PEM)
Fabrication in
the surface
facility

Horizontal emplacement

Waste package
BufferExternal
container

Verticalemplacement
Block type

Pellets type

Repository construction technology using
low alkaline cement
Corrosion test in
low alkaline
environment, using
carbon fiber
material –alternative for steelmaterial (photoimages: productionof test material)

Combination of ＰＥＭ and the capsule transportation system

Bentonite plug

Concrete plug

fractureGrout
overpack
Bentonite buffer

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

Collaborative research on
tunnel support, plug, etc. (e.g.
NUMO, CRIEPI)
tunnel support

Collaborative
research on
applicability to grout(e.g. NUMO, SKB,POSIVA, Nagra)
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Case 3: Improvement of repository design by 3D analysis of radionuclide migration
Objective: Develop the 3D analysis code of radionuclide migration, which allows simulation ofits detailed behaviors, to study their effects on different repository designs
Comparison of release between different waste emplacement methods
1.0E+06

1.0E+06
1.0E+05

Cs-135の移行率 [Bq/y]

Cs-135の移行率 [Bq/y]

1.0E+05
1.0E+04

EBSNBS

1.0E+03
1.0E+02
1.0E+01
1.0E+00
1.0E-01
1.0E-02

Verticalemplacement

1.0E-03
1.0E+01

1.0E+02

1.0E+03

1.0E+04

1.0E+05

1.0E+06

1.0E+07

時間 [y]

1.0E+03

EBS
NBS

1.0E+02
1.0E+01
1.0E+00
1.0E-01
1.0E-02

Horizontal
emplacement

1.0E+08

1.0E+04

1.0E-03
1.0E+01

1.0E+02

1.0E+03

1.0E+04

1.0E+05

1.0E+06

1.0E+07

1.0E+08

時間 [y]

Effect of plug for a fault – groundwater flow analysis
断層

fault

fault

1.E-01規格化した移行率の最大値 [1/y]断層

規格化した移行率の最大値 [1/y]1.E-01
1.E-02
1.E-03
1.E-04
1.E-05
1.E-0601020304050

60708090

坑道方向位置[m]Cross-sectional flow
velocity distribution

1.E-03EBSNBS
1.E-04EBSNBS

1.E-05

1.E-06は断層を示す1.E-07
1.E-08

3D model1.E-02

Without plug

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

100は断層を示す

1.E-07はプラ グを示す

1.E-080102030405060708090100

坑道方向位置[m]With plug at crossing offault and tunnel

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Case 4: Development of Requirements Management System
Conceptualization ofrequirements management
and engineering works
Works and RM
process for thestepwise program.

Info. exchange with overseaorganizations“RMS2010” held inTokyo at 26/Jan./2010
NUMO, SKB, POSIVA,ONDRAF/NIRAS, Nagra，domestic organizations

Preparation of e-contents•Contents for “repository design at eachsite-selection stage•Trial use of the outcomes of thefundamental R&D (e.g. JAEA-KMS)

Developments of NUMO-RMS•Original system suitable for RM in
NUMO and the stepwise program.

RWMC(2005)

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Background of 2010 Technical Report
YR 2000• Published the JNC 2nd Report• Establishment of the Final Disposal Act• Establishment of NUMO

Launch solicitation of nationwide municipalities
using volunteer approach

Development ofoverseas programmes
Amendment of theFinal Disposal Act

Preparation for the Literature Survey

Progress ofoverseas/domestic R&D

NUMO became the implementer of the LLW
geological disposal

Development of theNuclear Reactor Act

NUMO
Implementation of the repository project
For siting & PR support

2010 Technical Report（tentative）
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Objectives of 2010 Technical Report
For building public confidence in NUMO’s repository project,
Clarify NUMO’s safety concepts (precedent publication in 2009):
Specify the safety measures
Express NUMO’s policies on its technical activities for
ensuring safety
Demonstrate Japanese technology advancement, which
supports NUMO’s safety concept
Incorporate NUMO’s R&D and thefundamental R&D activities since 2000

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

Government’s

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Series of the NUMO 2010 Report groupSimple

NUMO manifesto

Technical Reports

NUMO’s policy
policyNUMO’sPR version
version ofof thethe NUMO
NUMO 20102010
PRReport
ReportLeafletBrochure

Pick-up useful information
to support PR activities
2010 TechnicalTechnical Report
Report2010

Transfertechnical
policies onsafety

Summary

Summary

DetailSafety Report
Report 2009
2009
SafetyReportIntegration2010 TechnicalTechnical Report
Report -- MainMain
2010
Main
reportProjecProjecTechnologies
Technologies

FY2009FY2010
Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Structure of the Safety Report 2009
Chapter 2: Breakdown of the structure of safety
GlobalaimAims
Measures

Achievement of safe geological disposal
Long-term safety

Safety during implementation(1I Site selection and confirmation(1) Avoid non nuclear accident(2) Engineering measures(2) Avoid radiation accident(3) Evaluation of long-term safety(3) Conservation of natural environment

Chapter 3: Policies and measures for implementation of safety geological disposal project

Chapter 4: Detail
descriptions

Policies

Breakdown of policy

Policy 1z Implementation by step-wise decision making based on the advanceplanningz Repetitious confirmation of safety by coordination between 3
measuresz Ensuring safety during implementation

Section 4.1

z Well planned R&D
z QA of technical informationz Organizational

Section 4.2

z Implementation based on understanding of safety by local
residencez Information disclosure (e.g. demonstration of technologies)
zConsideration for future generation

Section 4.3

Implementation by step-wise decision making basedon repetitious confirmation of safety

Policy 2
Implementation by credible (reliable) technologies

Policy 3
Technical works toward public confidence building

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

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Drat schedule for production of the 2009 & 2010
ReportFY ２００９Workshop

SafetyReport
2009(2009R)FY ２０１０

Safety Report
2009 Workshop▽2010RInternationalworkshop▽Mid Workshop &Symposium▽(2010R)

2010R main Workshop▽AESJ review ▽Review report

Draftproduction

Completion ofthe 2009R
Modifications ▽Review by AESJ etc.

2010 Report

FY ２０１１

Draft production
Modifications▽Review reportCompletion of the 2010R▽PR version of 2010R

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010P.24

Summary
9Preparation for the literature survey has completed.
- Reliability improvement by showing recent findings 9Develop & publish the 2010 Technical Report for obtaining
the public confidence toward NUMO’s repository projectand its safety; promoting its project implementation
9In regards to stepwise research & technical development,
their comprehensive visions and progress will be laid out tothe general public in an easily understood manner;
9For ensuring the transfer of NUMO’s technology, therequired human resources will be secured and fostered withthe mid and long term vision.

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010P.25

Thank you
for your attention
For further information:www.numo.or.jp/en/index.html

Nuclear Safety Research Forum Tokyo ,Japan 23 February 2010

P.26