NEWSLETTER
RADIOACTIVE WASTE MANAGEMENT

Feb. 2006

No.16
Issued by
Japan Atomic
Industrial Forum, Inc.

(MEXT) of Japan, in cooperation with the Kagamino
Town Office and Ningyo-Toge Environmental Engineering
Center, Japan Atomic Energy Agency (JAEA).
Representatives involved in policy making, regulation, operations and R&D on radioactive waste management attended the Workshop from the nine FNCA
countries, i.e., Australia, the People’s Republic ofChina, Indonesia, Japan, the Republic of Korea,
Malaysia, the Philippines, Thailand and Viet Nam.
The FNCA 2005 Workshop on RWM began with the
opening address by Prof. Toshiso Kosako, FNCA RWM
Project Leader of Japan, professor of the University ofTokyo, followed by the welcome address by Ms.
Miwako Shimizu, Atomic Energy Division, Researchand Development Bureau, MEXT, and also followed by
the congratulatory address by Mr. Chikao Yamasaki,
mayor of Kagamino-cho.
Following the Opening Session, in Session 1, country reports were presented on progress status ofradioactive waste management activities in each
FNCA country. On the first day of the Workshop,
Poster Session/Mini-Exhibition was also held. In thisSession, the projects and R&D regarding RWM were

The FNCA 2005 Workshop on
Radioactive Waste Management
September 27 - October 1, 2005,
Kagamino-cho Okayama Japan
Toshiso Kosako
Professor
Nuclear Professional School
Graduate School of Engineering
The University of Tokyo

Shinichi Fukuda
Project Manager
Asia Cooperation Center (ACC),
Japan Atomic Industrial Forum,Inc.
(JAIF)The FNCA 2005 Workshop on Radioactive Waste
Management (RWM) was held from September 27 to
October 1, 2005 at Kagamino-cho, Okayama, Japan.
This Workshop was hosted by the Ministry of
Education, Culture, Sports, Science and Technology

1NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

presented by Japanese participants, and uranium
glass products manufactured at Kagamino-cho weredisplayed by the Kagamino Town Office.
On the second day, in Session 2, sub-meeting (1)was held on “Safety Assessment of Disposal Facility for
Low and Intermediate Level Waste (LILW)”. The
progress reports were presented by 4 countries, andthe information exchange on the reports was made.
In Session 3, sub-meeting (2) was held on “SiteInvestigation and Siting Procedures of Disposal Facility
for LILW”. The progress reports were presented by 4
countries, and the information exchange on the reports
was made.
In Session 4, a roundtable discussion (1) on“Revision on the Consolidated Report on RWM and
IAEA Joint Convention” was held. It was recognizedthat it is useful for the FNCA countries to revise theConsolidated Report and it was agreed to revise theConsolidated Report.

in Indonesia and the Philippines in August 2005. The
reports were presented by Indonesia and thePhilippines.
In Session 6, a roundtable discussion (3) on “RWM
Three-Year Work Plan for 2005-2007” and “a draft ofthe minutes of the Workshop” was held. Items agreed
by the Workshop participants are as follows:- The FNCA 2006 RWM Workshop will be held in
China in October 2006.
- The Discussion/Survey Meetings on Decommissioning/
Clearance will be held in Australia and Malaysia in
2006.
- The sub-meeting themes at the next Workshop areagreed as “Conceptual Design of Near Surface
Repository”, “Waste Treatment and Conditioning for
Disposal” and “Management of Medical Waste”.
Those themes would be finalized after consultation
between the host country of the next Workshop andJapan.
- The Revised Consolidated Report (interim version)
will be issued by the end of March 2007 and the final
version will be published by the end of March 2008.
In advance of the Workshop, extra technical visits to
Kyoto University Research Reactor Institute (Kyoto
University Research Reactor (KUR)) and Japan
Synchrotron Radiation Research Institute (Spring-8)
were made on the way to Kagamino-cho where theWorkshop was held.

Waste Rock Yard

Uranium Glass Centerpiece
Ningyo-Toge Environmental Engineering Center, JAEA

On the third day, technical visit to Ningyo-Toge
Environmental Engineering Center, JAEA (Open-Pit
Mining Site, Waste Storage Facilities, etc.) was madeand visit to a studio of uranium glass product operated
by the Kagamino Town Office was also made.
On the fourth day, in Session 5, a roundtable discussion (2) on “Interim Reporting of Decommissioning/
Clearance Task Group Activity” was held to confirm theresult of Discussion/Survey Meetings which were held

Memorial of the first discovery of the uranium ore deposits in Japan

2

NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

The mission of the GIRDD is to develop technological basis and enhance reliability of safe geological disposal of high-level radioactive waste (HLW). Two
unique research facilities ENTRY and QUALITY are in
operation in Tokai. Various bench-scale experiments
are in progress in ENTRY to develop and verify models
for simulation and performance assessment whereas
fundamental data on geochemical behavior of radionuclides under controlled atmosphere are being collected
in QUALITY. Construction of two undergroundresearch laboratories is in progress, one in Mizunami in
crystalline rock formation and the other at Horonobe insedimentary rock formation. JAEA’s R&D program on
geological disposal is intended to provide data andinformation needed to support activities of the implementation body NUMO and preparations by the regulatory body for formulating safety guidelines and standards.

Take-off of the new nuclear R&D
organization JAEA
Tomio Kawata
Director General
Geological Isolation Research andDevelopment Directorate
Japan Atomic Energy Agency (JAEA)

On October 1, 2005, the former Japan Atomic
Energy Research Institute (JAERI) and Japan Nuclear
Cycle Development Institute (JNC) were merged andthe Japan Atomic Energy Agency (JAEA) was
launched as a comprehensive and multidisciplinary
research and development organization in the field of
nuclear science and technology. The merger was
intended to bring basic research and the R&D on specific projects closer together, and thus to contribute
more efficiently to the long-term energy security and thesettling of the global environmental issues through thepeaceful use of atomic energy and the application of
nuclear science.
The JAEA’s mission covers a broad range of the
R&D fields as illustrated in Figure 1. The head office islocated in Tokai-mura with the branch head office atTsuruga and the support office at Tokyo. There are ten
R&D centers with various missions located throughout
the country.
Among various program directorates founded in the
JAEA, there are two directorates which directly deal
with the matter related to waste management; Nuclear
Cycle Backend Directorate (NCBD) and Geological
Isolation Research and Development Directorate(GIRDD).
The mission of the NCBD is to coordinate and bring
into forth a plan for rational decommissioning of retired
R&D facilities and for safe treatment and disposal of
low-level radioactive waste arising from various R&D
sites, and to promote R&D to better achieve rational
decommissioning and waste management. At present,
several decommissioning projects are in progress orunder preparation including those for Japan
Reprocessing Test Facility (JRTF) at Tokai-mura and forthe prototype advanced thermal reactor Fugen atTsuruga. The NCBD is also playing an important role inassisting government’s effort to establish new institutional frameworks for the disposal of such waste as
TRU waste or to establish related safety standards.

Figure 1 JAEA’s Mission

Figure 2 Two major decommissioning projects: JRTF and Fugen

Figure 3 Three R&D Centers for HLW Geological Disposal Technology

3NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

Policy. It identifies the necessity of establishing laws
and regulations on disposal, the waste-procedure’s
responsibilities and roles in treatment and disposal,
nature of an implementing body and a schedule for
implementation. According to this report, together withJAERI (Japan Atomic Energy Research Institute), JNC(Japan Nuclear Cycle Development Institute) and JRIA
(Japan Radioisotope Association), which are major producers of RI and Research institutes, etc., establishedRANDEC (Radioactive Waste Management andNuclear Facility Decommissioning Technology Center)in December 2000, to promote activity toward realization of an actual disposal business.
The Ministry of Education, Culture, Sports, Scienceand technology (MEXT) established a Special
Committee on the Business of Disposal of Waste from
RI and Research Institute, etc., (February 2002), andthe special committee discussed promotion of the shallow land disposal business and issued its final report(March 2004). The report said that the establishment of
the implementing body of the disposal business for RI
and Research waste would be expected until October
2005. However, because of a delay of examination
about establishment the implementing body by unification of JAERI and JNC, the MEXT has re-established aSpecial Committee on the Business of Disposal ofWaste from RI and Research Institute, etc., (December,2005). The special committee will discuss the establishment of the implementing body for RI and Research
waste disposal business from the point of the view offund security of the long term business which is estimated about 19,000 Million yen for 300 years, and local
promotion by the disposal business.

The current status of low level
radioactive waste management arisingfrom RI facilities, institutes etc.
Yoshiaki Sakamoto
Assistant Principle Resercher
Waste Disposal Project Group
Nuclear Cycle Backend Directorate
Japan Atomic Energy Agency

In Japan, the radioactive waste arising from facilities using radioisotope including hospital (hereafter, RI
waste), research reactor and from other facilities using
nuclear sources/materials for research or industrial use,etc. (hereafter, Research Institute waste) is currently
treated for storage and kept temporarily at the individual
facility generating it, however is not disposed at present.
The Atomic Energy Commission (AEC) issued Basic
Policy on Treatment and Disposal of Waste from RI and
Research Institute, etc. (May 1998), through the discussion of its Special Committee on Nuclear Back-End

Figure Undertaken plan of the waste disposal

Figure RI and Research waste

4NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

concept and prioritized safety in the dismantling activities.
Major activities anticipated for the decommissioningof the reactor include, license application, characterization survey, safety analysis report, time scheduling,
quality assurance programme, radiation protection plan,safety & environmental impact assessment, plan for
management of decommissioning waste and plan for
final radiological survey. It is obvious that the mostimportant factor prior to decommissioning lies on thegovernment decision or policy on several criticalaspects such as relating to the management of spent
fuels. This in turn will be subjected to the commitment
with the reactor supplier as well as commitment tobeing a party of the Joint Conventions.
Safety and environmental assessment is viewed as
one of the most critical aspect in the decommissioning
plan. The regulatory authority will define the safety criteria or performance objectives need to be achieved fromcarrying this activity. Likewise for the assessment, several scenarios which will give rise to additional radiationdose to the members of the public and workers need tobe evaluated in details. In addition, potentially hazardous toxic and radioactive waste needs to be identified and characterized for the purpose of a thoroughsafety assessment during decommissioning (including
accident analysis, where necessary). The assessment
should be conducted to define protective measures,
which takes into account the specifications of decommissioning.
It is anticipated that main activities to be carried out
during decommissioning process are initial characterisation of the installation, fuel removal, decontamination,
dismantling, transporting waste, storage, waste conditioning, disposal and final radiological survey. In initialcharacterization, radiation and contamination surveys
will be conducted to determine the type of radionuclides, maximum and average dose rates and contaminated levels of the inner and outer surfaces of structures or components in the reactor installation. Major
types of waste anticipated from this decommissioning
project, apart from the fuel elements, are the concrete
debris, which are used as biological shield, the piping
components, the aluminum swimming pool vessel andthe ion exchanger use for cleaning the deionised water(see cross sectional diagrams).
Under the existing purchase and supply agreement,
spent fuels elements will be returned to the country of

Decommissioning Plan for MINT’s TRIGAMARK II Research Reactor
Syed Abdul Malik Syed Zain
FNCA RWM Project Leader of Malaysia,
Manager, Radioactive Waste
Management Centre
Malaysian Institute for Nuclear
Technology Research (MINT)
Ministry of Science, Technology &Innovation (MOSTI)

Thanaletchumy Karuppiah
Research Officer, Radioactive Waste
Management Centre
MINT, MOSTIMalaysia only operates one nuclear research reactorof the type TRIGA MARK II which reached its first criticality on 28 June 1982. The reactor is equipped withfive major types of experimental facilities, consisting of
the central thimble, a rotary specimen rack, two pneumatic transfer systems, four beam ports and a thermalizing column. Presently, most of the operating hours are
spent on irradiation of samples for the neutron activation analysis purpose. Recently the reactor has completed its 23 years of operation and a study on decommissioning plan for the RTP (Reactor TRIGA PUSPATI)
and relevant facilities are being carried out by theInstitute although the reactor will continue to operate forseveral years more.
When the reactor was first commissioned in 1982, it
was not subjected to licensing procedure. However, inline with the international practice, efforts to license thereactor are presently being carried out. Similarly, theapplicability of regulations and licensing process todecommission government’s research reactor are notclearly defined in the Atomic Energy Licensing Act 1984
regulated by the Atomic Energy Licensing Board,
although under the licensing regulations, it states therequirement of a Class G license for decommissioning
nuclear facility.
Basic strategies foreseeable for the reactor decommissioning project include; establishment of an efficient
project management team, development of the technologies for application in the project, immediate dismantling after the decision for the decommissioning,decontaminate all the contaminated items, unrestricted
use of the site after decommissioning, minimization of
the radioactive waste with application of a zero release5NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

origin for processing. It is anticipated that a total of 129
units of spent fuel element, need to be sent back to theGeneral Atomic of the United States.
Indeed there is a need to develop decontamination
techniques for cleaning-up internal and external surfaces of components and systems, structural surfaces
and tools used in the decommissioning activity.
Dismantling of the facility may include the demolishingof the reactor building, depending on government decision whether to re utilise the building or not. Early estimate of the total waste volume from dismantling activity
is approximately 300 M3, (Table 1). Miscellaneous
wastes include ion exchange resin used for cleaning
reactor pool water and contaminated items duringdecontamination works.

In general, the waste generated from the decommissioning process will be categorized into three groups;
firstly the non contaminated waste, which will be sent tomunicipal disposal site; secondly the solid radioactive
waste, which will be packed in drums of 200 litres orother types of package according to the physical properties, and temporarily stored in the storage facility
before sending to the repository and finally the radioactive liquid waste which will be treated prior to releasing
to the environment.
A final radiological survey will be carried out at theend of the decommissioning project to demonstrate theresidual activity complies with the criteria set by the regulatory authority.

Table 1. Estimated Volume of Waste Generated After
D&D of TRIGA Reactor ProjectType of Waste

Volume (M3)1.

Concrete

200

2.

Aluminum Tank

8

3.

Stainless steel & Aluminum Piping
Heat Exchanger

54.

Graphite

3

5.

Lead

3

6.

Fuel Elements (Assuming each fuelelement is converted into 0.5 M 3 ofconditioned waste)

65

7.

Miscellaneous

10

8.

Tritiated Water

25

Total estimated volume319

Figure 2 Cross-Section of a typical TRIGA Mark II Reactor

Figure 3 Cross-Section of a typical TRIGA Mark II Reactor

Figure 1 The TRIGA Mark II Research Reactor at MINT

6

NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

Gyeongju City selected to host thesite for a final disposal of LILW in
Korea

of 307,536. All of the four candidate areas met the minimum requirements of more than one-third voter turnout
and the more than 50 percent voting in favor.
The central government is aiming to complete thefinal disposal facility in the Yangbuk region of Gyeongju
City, on the coast of the East Sea, by 2008.
The host city will receive a financial support packageof 300 billion won ($285 million) for regional development, as well as a commission estimated to be 5 to 10
billion won a year, depending on the amount of radioactive waste deposited at the site. A proton linear accelerator center is also to be built in the host city. In addition,
it would relocate the headquarters of the Korea Hydro &Nuclear Power (KHNP) from Seoul to the host city within 3 years after the permission of construction plan for
the facility.
Korea currently has 20 nuclear power plants in operation. By 2015, 6 more nuclear power plants are
expected to be completed, but, in the meantime, they
have no final disposal facility for LILW yet. The final disposal facility needs to be established by 2008 at the latest, as existing on-site storages have limited storage
capacity.
The government assures that high-level radioactive
wastes like spent nuclear fuel will not be stored in theselected site. The site will store low-and intermediatelevel radioactive wastes such as gloves, clothing,radioactive filters from the nuclear power plants andspent radioisotopes from hospitals, industries and R&D
activities.

Jong-Hyun Ha
Project Leader of Korea in FNCA-RWM
Deputy General Manager, R&D Office
Nuclear Environment Technology
Institute (NETEC)
Korea Hydro & Nuclear Power Co., Ltd.
(KHNP)On November 3rd of 2005, the Korean government
officially announced that a final disposal facility of the
low-and intermediate-level radioactive waste(LILW) will
be built in Gyeongju City as the city beat out three bidders, i.e., Gunsan, Pohang and Yeongdeok, for the
longest pending national project in a referendum on
November 2nd of 2005.
Gyeongju, the ancient capital of the Silla Kingdom,
won the project with the highest approval rate fromamong the four candidate communities, in accordancewith the regulations on choosing a bidder.
Specifically, 89.5 percent of the voters of Gyeongju
supported their city’s bid for the project that has driftedfor 19 years. It is the first time that the fate of a major
national project has been decided by a direct vote. It
also enhances the people’s participation in the government’s administration of the nation.
According to the results of the referendum, Gyeongju
reported 70.78 percent turnout of a total electoral roll of
208,607; Gunsan 70.14 percent of 196,980; Pohang
47.22 percent of 374,697 and Yeongdeok 80.21 percent

Bird’s-eye view of an Engineered Vault Type Disposal Facility

7NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

for their regulation and safety and security standards.
It has become timely to reconsider the way in whichsome radioactive sources are managed.
This has been recognised by Member States of theInternational Atomic Energy Agency (IAEA) with thedevelopment, and Board of Governors’ agreement andGeneral Conference endorsement, of the non-binding
Code of Conduct on the Safety and Security ofRadioactive Sources in 2003 and of related import andexport guidelines. There are several technical documents addressing radioactive source security matters,
and a new Safety Guide on Categorization ofRadioactive Sources (RS-G-1.9, August 2005) which
establishes the concept of dangerous sources for security purposes.
In the Australian Government’s May 2004 Budget,
funding of $4.5 million was provided to the Australian
Nuclear Science and Technology Organisation(ANSTO) for three years to implement a project on
securing of radioactive sources in the Asia-Pacificregion.

Managing Regional Radioactive
Source Security Risks - An AustralianGovernment Initiative
Lubi Dimitrovski
FNCA RWM Project Leader ofAustralia
Waste Operations & Technology
Development
Nuclear Technology
Australian Nuclear Science &Technology Organisation (ANSTO)

Introduction
Traditionally, the management 1 of radioactive
sources has focused on safe control to prevent accidental or unnecessary exposure to users and the public. Security aspects of source management weregenerally considered fulfilled by controlling sources ina safe manner. However, the terrorist events of recent
times have led to serious questioning of whether the
standard controls were sufficient, as some radioactive
sources could possibly be used in a radiological dispersion device (RDD) by those with malicious intent.
There is extensive use of high-activity, dangerous2
radioactive sources in medicine, industry, mining &exploration, agriculture, education and research &development in all countries. Often there is a lack ofwell-developed owner or user safety and security
arrangements, or of adequate regulatory oversight. A
serious incident involving a radioactive source in any
one country would have implications in other countries

Project Objectives and Scope
The objective of ANSTO’s Regional Security ofRadioactive Sources (RSRS) Project is to minimise
the probability and impact of, unauthorized access ordamage to, loss, theft or unauthorized transfer ofradioactive sources within the region. This is being
achieved by:(a) assisting countries in the region to identify and tosecure orphan and poorly controlled radioactive
sources; and(b) improving the security arrangements for radioactive sources through improvements to regulatory
infrastructure, user practices and providing
advice on physical and equipment upgrades.
Within the region close to Australia, the RSRS
Project is primarily focused on South-East Asia,
including all ten ASEAN countries, three of whom arecurrently non-Member States of the IAEA. The PacificIsland countries, particularly Papua New Guinea(PNG), are also within the geographical scope of the
project.

Figure 1 Discused Industrial Gauges in Secure Storage

1 Management means the administrative and operational activities thatare involved in the manufacture, supply, receipt, possession, storage,use, transfer, import, export, transport, maintenance, recycling or disposal of radioactive sources.
2 “Dangerous” radioactive sources means those defined as category 1,
2 and 3 in IAEA Safety Guide RS-G-1.9, August 2005.

Project Planning
The project recognises that there is a range of related international and national activities being implemented in some regional countries. To successfully imple8

NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

ment the RSRS Project and fulfil its objectives, close
cooperation and collaboration has been sought with:• Government authorities in all regional countries• the IAEA, noting the IAEA Action Plan for the
Safety and Security of Radioactive Sources(GOV/2003/47- GC(47)/7 Annex 1) and its updatefor 2006-2009 (GOV/2005/50, August 2005)• The US National Nuclear Safety Administration (USNNSA)’s International Radiological Threat Reduction(IRTR) Program and related activities.
In 2004, three meetings were held with the US
NNSA, IAEA and authorities of several South East
Asian countries to plan and identify issues and needs.
This resulted in the RSRS 2005 Programme for SouthEast Asia being so designed to achieve project objectives via the components indicated below. In November
2004, the RSRS Project also contributed to the AsiaPacific Conference on Nuclear Safeguards andSecurity, which was convened by the Minister for
Foreign Affairs. The pertinent outcome of this conference and adjacent meetings with representatives fromSouth-East Asia and Pacific Island Countries was highlevel recognition of the regional radiological security
issues and the means (via the RSRS Project) toaddress them.

Figure 2 Securing a Vulnerable Source in PNG

conducted in eight countries, including more focusedfollow-up missions conducted in several of these countries. This work will continue in 2006.
Vulnerable Sources
In the course of an expert mission to PNG, a highly
active teletherapy source was identified as being vulnerable. Further investigation revealed that while theunit was Canadian in origin, the cobalt-60 source had
been replaced in 1993 by ANSTO. This gave a clear
mandate for repatriation of the source to Australia, andan extensive operation was completed in December
2005. Considering that PNG is not an IAEA member
state, and that the source had come to the end of its
useful life, it could have very well remained undiscovered and vulnerable had it not been identified by the
RSRS Project. In other countries, the RSRS Project
has identified vulnerable sources and is working withauthorities in these countries to characterise and better secure these sources.
Regional Training
With the support of experts from the US NNSA andthe IAEA, the RSRS Project has conducted two regional technical training courses. The first of these was on

RSRS South-East Asia 2005 Program Components
A. Committing to, and Implementing, the IAEA Codeof Conduct and its Requirements
B. Improving National Legislation Addressing Source
Security
C. Improving Regulatory Requirements Addressing
Source Security
D. Improving the Authorization (Licensing) System
Addressing Source Security
E. Improving Source Registry Capabilities
F. Developing and Implementing Inspection
Programs for Source Security
G. Providing Information Outreach to Public andCoordination with Other Organizations.
Project Implementation
Expert Missions
Much of the work completed in 2005 focused on
expert technical missions. In conjunction with theregional in-country counterparts, these expert missions
have provided opportunities to assess the specificneeds of countries so that project resources can bebest utilised and develop apposite cooperation programmes. To date, fifteen expert missions have been

Figure 3 Search & Secure Workshop

9NEWSLETTER RADIOACTIVE WASTE MANAGEMENT

searching for and securing orphan radioactive sourcesin February 2005. This course involved 21 participantsfrom South-East Asia and directly addressed the RSRS
Project objective of assisting countries in the region to
identify and to secure orphan and poorly controlled
radioactive sources. In August 2005, a second course
focused on physical protection of radioactive sources,
and was attended by 34 participants from elevenregional countries. This training course was the first of
its type. Both of these courses received very favourable
evaluation, and are a key component in achieving outcomes related to project objective (b) mentioned above.
Extending on from these courses conducted inAustralia, the RSRS Project is moving into providing tailored, in-country training for regulators and related
national authorities as well as for users of radioactive
sources. The first of these courses was conducted in
October 2005 in PNG with 24 participants from various
areas of government and other organisations such as
mining companies. The course provided training onradiation protection and security requirements forradioactive sources through a series of lectures andpractical sessions.
Legislative Reviews
In conjunction with the US NNSA, the project has
worked closely with several countries to improve theirrelevant legislation to provide appropriate authority andmake requirements for source security. This typicallyinvolves peer review services for analysis of existinglegislation, standards and codes of practice, or assistance with the development of these documents. This
work cuts across many of the RSRS Project Program
Components indicated above.

securely managing radiation sources. Expert missions
conducted to help identify country-specific requirements
and address these needs. Training courses have been
conducted both in Australia and in-country to help
improve the radiation protection and security expertise
within the region. Most notably, highly-radioactive, vulnerable sources have been identified, with one being
secured through repatriation to Australia.
It is envisaged that as the project continues, more
focused and specialised assistance will be delivered toregional stakeholders. This can be achieved throughmore specialised training courses, provision of radiation
detection equipment, and assistance with identifying
and securing vulnerable sources.
Ultimately, the RSRS Project is assisting countries inways that other programs can not, as the project canoften provide more targeted assistance including to
non-IAEA Member States.
Contacts: Mr Allan Murray, Leader, RSRS Project(amu@ansto.gov.au; phone +61-2-97171-3260; fax +61-297171-9266); Mr Mark Alexander (mxa@ansto.gov.au) or
Dr Wayne Garrett (rwg@ansto.gov.au)

New JAIF Office opened on
February 21, 2006.
OtemachiTokyo

Mita Subway Line
Nippon Oil Corp.

Tokyo Star Bank

HibiyaExit

Toranomon
Sumitomo
MitsuiBank
Hibiya St.

Conclusion
The RSRS Project is meeting its objectives of helping to significantly improve regional capabilities for

Ginza

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