FNCA Newsletter No.7
Radiation Safety & Radioactive Waste Management

C o nte nts
M a r. 2 0 1 3

Topics from participating countries
P.1 – P.12

Issued by
Nuclear Safe ty
Research Association(FNCA Secretariat,
JAPAN)

List of Project Leaders P.13
FNCA Framework

P.14

Topics from Participating Countries
Australia
Mr. Lubi Dimitrovski
Australian Nuclear Science &Technology Organisation (ANSTO)
Intermediate Level Waste Return Project
The Australian Reactor

The now retired High Flux
Australian Reactor (HIFAR) at Lucas
Heights first went critical on the 26
January 1958. HIFAR was the firstnuclear reactor in the southernhemisphere and it was used for
producing neutrons for scientificresearch and the production ofradioisotopes for medicine and industry.
After close to 50 years of reliable
operation, it was retired in January 2007
with the commissioning of the new,state-of-the-art OPAL reactor.

Fig1. The retired HIFAR

megawatts. The original uranium
enrichment of the fuel used in HIFAR
was 93% U235. In 1983, 60% enriched
HEU fuel was introduced and a stepwise
reduction towards LEU was actioned in
2004. The conversion to LEU wascompleted in 2006.
Approximately 37 spent fuelelements were generated by HIFAR eachyear. Once discharged from the reactor,
the spent fuel elements were stored
underwater for several years to allow
much of the short-lived activity to decay.

HIFAR's reactor core consisted of 25
fuel elements and has a nominal
maximum thermal power output of 10

1

governmental agreements made withFrance and UK specifies that the wastes
arising from the reprocessing of the
ANSTO’s spent fuel in these countries
will be returned to Australia. It isinternationally accepted that countries
are responsible for the management of
the radioactive waste they produce.

The fuel elements were then transferred
to an engineered dry storage facility,
consisting of holes drilled into the
bedrock and lined with stainless steel
welded tubing.
The National Radioactive Waste
Management Act 2012 defines “highlevel radioactive material”, as “material
which has a thermal energy output of atleast 2 kilowatts per cubic metre. Unlike
power reactors, Australia’s research
reactors do not generate any used fuelthat would be classified as HLW.

Intermediate Level Waste Return from
FranceVitrified Waste Residues

A total of 1288 spent fuel elements
were sent to France. The waste residues
arising from the reprocessing of theseelements were melted together with glassmaterial at high temperatures forincorporation into the glass matrix. The
melted mixture is poured into stainlesssteel canisters, and after controlled
cooling, the canisters are sealed bywelding and then decontaminated toremove possible surface contamination.
A maximum of 28 vitrified waste
canisters will be loaded into a Frenchdesigned and developed transport andstorage package (TN 81 cask), andshipped back to Australia in the second
half of 2015.

Spent Fuel Shipment for Reprocessing

As Australia does not have a nuclear
spent fuel reprocessing facility, the used
HIFAR fuel elements were sent overseas
for reprocessing. Reprocessing is thechemical process whereby fissile andfertile materials in the spent fuel arerecovered in order to provide fresh fuelfor existing and future nuclear power
plants. It offers benefits in increased
uranium and plutonium utilisation, and areduction in the volume of high level
waste. The resulting liquid waste fromthe reprocessing process is thensolidified for long-term storage.
Between 1996 and 2009 there wereeight overseas shipments of used
ANSTO’s nuclear fuel - four shipments
to France (for reprocessing), three
shipments to the United States (US) as
part of the US DOE spent fuel take backprogram and one shipment to the United
Kingdom (UK) for reprocessing. Eachshipment was carried out safely using
approved
andlicensedtransport
packagesondedicated
INF-2
classification ships.

Fig2. The TN-81 Cask

The TN-81 cask measures around7.2m in length and 2.7m in diameter,when fully loaded weighs close to 120
tonnes. Containment and shielding is beprovided by the thick forged steel
cylindrical vessel with the weldedbottom,theexternal
lead-filled
aluminium
profilesandthe

The waste arising from reprocessingof spent fuel elements shipped to the US
under the US Department of Energy(DOE) Foreign Research Reactor Spent
Nuclear Fuel Acceptance Program(FRR-SNF) will not be returned toAustralia.
Howevertheinter-

2primary/secondary
lids
with
the
associated seals. The TN-81 cask isdesigned to withstand a drop of 9 metres,
temperatures above 800 degrees Celsius,
earthquakes and jet plane crashes.
Technological Wastes

The technological wastes produced
during the operation and maintenance ofthe reprocessing facility such as
contaminated gloves and tools will also
be returned at this time.

Fig5. Process flowchart for spent fuel processing
and waste cementation in Dounreay, Scotland

Fifty-one 500L cemented drums havebeen designated for return from
Dounreayto
ANSTO.
Howevernegotiation is currently underway on theinter-governmental level for a policy
option to permit the substitution of theradioactive waste at Dounreay for analternateradiologicallyequivalentamount of vitrified ILW at Sellafield,
England. A feasibility study into thereturn of the reprocessed wastes from the
UK to Australia found in favour of thevitrified waste form. Some of thebenefits for vitrified residue option are
given below:

Fig3. The cemented technological wastes

The technological waste will becemented within cast-iron fibre cement
over pack containers (CBFC Type 2) andthe six CBF-C2 containers will be placedin a rack which will be securely fastened
inside a 20 foot ISO IP2 container for
shipment.


Fig4. Cemented technological wastes secured inrack within the ISO IP2 transport container

Intermediate Level Waste Return from UK

A total of 114 spent fuel elements
were sent to United Kingdom. The
reprocessing and waste immobilisation
process at Dounreay, Scotland isoutlined in the flowchart below.

3

A new transport and storage
package will need to be sourced
for the 51 x 500L cemented
drums.
A single TN-81 transport andstorage cask can be used for the2-6 x vitrified containers. The
same
packagehandling
equipment/tooling acquired for
the French return waste can beused.
Reduction in waste and primarycontainment volume of the
returned waste from 25m3 to lessthan 1m3.



A smaller footprint required forstorage.
Reduced number of required
shipments.

Bangladesh
Dr. M. Moinul Islam, Ms. Moutushi
Shidha Shome , and Mr. Shanjib
Karmakar
Bangladesh Atomic Energy
Commission (BAEC)
Precipitation Characteristics aroundthe Country in Bangladesh

(a)

(b)

For establishment of a nuclear facility,
it is a primary criterion for selecting asuitable site, so as to provide reasonableassurance that the facility can be operated
at the site without undue risk on thehealth and safety of the occupational
workers, the general public and therelated environment. It is based on theevaluation of detailed information and
data
about
geography,
geology,hydrology, meteorology, seismology,transportation
andcommunication,
demography, industrial installations,facilities in the vicinity, and the region
surrounding the site.
The evaluation of extreme values of
meteorological phenomena e.g., thevalue of precipitation must be
documented for an appropriate period oftime. Since the type and amount ofprecipitation may influence the amountof surface erosion, the occurrence anddepth of groundwater, leaching andtransport of nuclear materials, and therate of evaporation in the area. Thus
precipitation and water level are
important factors in the consideration or
selection process of a site. This reportbased on the available information
concerning long-term annual andmonthly variations in precipitation indifferent districts of Bangladesh. All the
precipitation data have been collectedfrom the 34 stations throughout thecountry with the courtesy of Bangladesh
Meteorological Department (BMD).

Fig6. Option to substitute the (a) 51 x 500L cemented
ILW from Dounreay, Scotland with (b) 2-6 x 150L
vitrified residue canisters from Sellafield, England.

Interim Storage in ANSTO

An interim storage facility will belocated at the Lucas Heights Science andTechnology Centre (LHSTC) site for the
storage of the French return waste.
License applications will be submitted to
the regulator, Australian Radiation
Protection and Nuclear Safety Agency(ARPANSA) shortly for the siting andconstruction of the Interim Waste Store(IWS). The IWS will be operational by2015 to receive and temporarily store thereturned waste from France. The
Australian National Radioactive Waste
Management Facility (NRWMF) is
anticipated to be operational by the endof the decade, at which time the French
returned waste will be transported forlong-term storage in the NRWMF.
The UK returned waste will betransported directly from port to the
NRWMF. However in the unlikely eventthat the NRWMF is not operational at
the time of the UK waste return, the IWSat the LHSTC has been designed toaccommodate the UK returned wastes.

4

Table 1: The Average annual precipitation (mm) during the period(2001- 2011)
Divisions

2001

2002

2003

2004

2005

2006

2007

2008

2009

2010

2011

Average

Dhaka

1842

2118

1662

2213

2176

1711

2405

1920

1630

1621

1776

1915

Sylhet

3193

3448

2925

3660

3269

2746

3427

2613

2869

3614

2575

3121

Rajshahi

1420

1649

1402

1911

1772

1179

1717

1470

1248

985

1644

1490

Rangpur

2315

2850

2350

2587

2826

1673

1835

1873

2132

1898

1822

2196

Khulna

1619

2238

1691

2062

1906

1805

1977

1713

1575

1311

1860

1796

Barisal

2787

2597

2226

2682

2590

2280

2686

2353

2084

2042

2357

2425

Chittagong

3202

2983

2910

3214

3842

2709

3600

3159

2915

2822

3400

3159

Fig 2: Variation of annual precipitationin different divisions Bangladesh

Fig 1: Average rainfall distribution different districts around the country
Table 2: Monthly average precipitation (in mm) around the country (2001- 2011)

Figure3: Monthly rainfall distribution in different divisions around the country

5

The average annual precipitation inseven divisions of Bangladesh form
2001 to 2011, ranging from a minimumof 1490 mm to a maximum of 3159 mm.
Thevariationof
total
annualprecipitation is shown in Figure 2. From
this figure it has been observed that the
total amount of annual precipitation ishigher in Chittagong and Sylhet region
whilst the lower precipitation record
observed in the Rajshahi region. The
monthly precipitation distribution isshown in Figure 3, from the analysis ofdata it is seen that rainy season withheavy rain occurs in June, July month,while the dry season with least rain wererecorded in December. The maximum
rainfall occurs from May until October.

However, besides its large benefit,
radioactive application also has radiation
hazard to the workers, the public, and theenvironment. Radioactive waste isdefined as any radioactive material andany material as well as equipment thathas been contaminated by radioactive
material or becomes radioactive due tothe operation of a nuclear installationand cannot further be used. Based on thepotential dangers that can be caused, theradioactive waste need to get a proper
management for to endanger people andthe environment.
At the present time, the main legal
frameworkofradioactive
waste
management in Indonesia is the Act no.
10 Year 1997 on Nuclear Energy, theGovernment Regulation No.. 27 Year
2002 on Radioactive Waste Management,
the Government Regulation No. 26 Year
2002 on Safety of Transport ofRadioactive Materials, and the others.
Regarding to the regulation theRadioactive Waste Technology Center(RWTC - NNEA) is the centralized for
management radioactive generating for
all Indonesian areas.

During the site selection procedure
the region must be assessed to determine
the potential for flooding due to naturalcauses such as runoff resulting fromprecipitation that may affect the safety of
the nuclear installation. The collected
rainfall data analysis will be useful forsite
selection
processfortheestablishment of a nuclear facility in the
country.

Transportation of Radioactive Waste
Into RWTC

There are two regulations ontransportation of radioactive waste. The
Government Regulation No. 26 Year
2002 on Safety of Transport ofRadioactive Materials and the Decree ofthe Head of Nuclear Energy Regulatory
Agency (BAPETEN) No. 04/KaBAPETEN/V-99 on Safety Conditions
for Transportation of Radioactive
Substances.
Transportationofradioactive materials is defined as the
movement of radioactive materials fromone place to another through a public
transportation
line
using
vehicle/transporter by land, water or air.
There are four parties involved onradioactive waste transportation, every
party has an obligation and responsibility
for the implementation of radioactive

Indonesia
Dr. Suryantoro
National Nuclear Energy Agency(BATAN)Radioactive Waste Managementin Indonesia
Introduction

Nowadays, the use of nuclear energy
in various fields, such as in research,
agriculture, medicine, industries, andenergy,has
progressed
rapidly.
Radioactive Sources such as Co-60, Cs137, Ir-192 are used for sterilization,level gauge, thickness gauge, nondestructive testing etc.

6materials transportation safely andsecure. They are consignor (waste
producer), Carrier, Consignee (RWTC),
and Regulator (BAPETEN).
Some important things related to thetransport of radioactive waste shall beconsidered :themanagementofradioactive waste. RWTC
will response associated withradioactive
waste
management cost. WP thenfind carrier to transport theradioactive waste to RWTC.

1. The transportation of radioactive
waste only be done if the bothconsignor and consignee has thelicense of utilization on nuclear
energy from BAPETEN.

3. RWTC reported periodicallyto the BAPETEN about waste
management
activities(especially inventory).
Transportation of radioactive
materials is done by high safety
standards due to ensure the safety,
security, tranquility, and health workers,
the public and the environment during
activity. In order to achieve safety
objective, the consignor and consignee
must apply safety principles i.e.:

2. Before transporting has done, theconsignor must get an approval
letter of radioactive materials
transportation from BAPETEN
3. The consignor shall perform inpackaging of waste accordance withthe type and category packaging..

1. During transportation, theradioactive substances do notleave from container in bothnormalandaccident
conditions.
2. Radiation
exposure
atpackaging surface was not
upper than safe limits
3. In the case of the transport ofnuclear material, it must be insubcritical condition.
4. The heat generated byradioactive substances should
be removed completely.

4. Carrier shall provide signs,
labels, and or plaques on the
packaging and transport vehicles.
Here is a flow diagram ofradioactive
wastetansportation
procedures from waste producer(WP) to RWTC :E d fUR

BAPETEN
N ifi
Approval letter

i

Li
E
E

Consignor (WP)

CARRIER

Consignee (RWTC)

Od

T
I f

i

d

i
li

Radioactive Waste Management at
RWTCi

Based on its form, radioactive waste
is managed by RWTC can be classified
into liquid, semi-liquid, solid, and spent
nuclear fuel. RWTC - NNEA as theexecuting agency for radioactive waste
management in Indonesia is responsible
for the management of radioactive waste
involved to be processed, stored. RWTC
has a vision to become a national center
for radioactive waste management
services and development of technology
on environmental safety and marine
radioecology. To realize the vision and

Figure 1. Flow diagramtransportation
H d of waste
L tt

From the diagram above, the generalprocedure for radioactive wastetransportation to PTLR - BATAN
can be explained as follows:
1. Consignor (WP) apply for antransportation approval letter
to BAPETEN.
2. After obtaining approval
from BAPETEN, radioactive
WP requests to RWTC for7mission, RWTC is equipped withequipment and supporting facilities.
The management of radioactive waste
in RWTC can be summarized in the
Figure 2.

Figure 2. Flow diagram of radioactive waste processing

concentrated in the ash, and then further
immobilized in a steel drum volume of
100 liter using cement matrix.
Non corrosive inorganic liquidradioactive waste is processed byevaporator to produce distillate andconcentrate. The concentrate is thenimmobilized in a 950 liter concrete shellusing cement matrix. Capacity ofevaporator unit is 0.75 m3/hr. Whilecorrosive liquid radioactive waste istreatedbycoagulation-flocculation

Liquid radioactive waste management

Liquid radioactive waste is classified
into organic and inorganic. For example
Organic liquid radioactive waste are
Tributhyl Phosphate (TBP), kerosene,
and other mixed organic solvents.
Organic liquid
is treated using
incinerator. Flue gas from incineration
process is filtered through HEPA filter
and then scrubbed using NaOH for
neutralization. While the radio nuclides

8management of DSRS, which are
returned to the country of origin (reexport), or are transfered to RWTC. At
RWTC, DSRS is grouped by similarityof radio nuclides type, then wasconditioned on a 200 liter shell drum,
350 liter concrete shell, or 950 liter
concrete shell depend on the dimensionsof each DSRS. The conditioned DSRS isstored in Interim Storage Building.

technique. Sludge treatment outcomes ofchemical Treatment unit is immobilized
in 950 liter concrete shell size using
cement matrix.
Semi-liquidmanagement

radioactivewaste

A semi-liquid radioactive waste ismainly spent resin from 30 MW Multi
Purpose Reactor. The spent resin is
immobilized
in a 950 liter concrete
shell using cement matrix. Further
concrete shells are stored in Interim
Storage.
Solid and contaminatedradioactive waste

Management of spent fuelPresently, RWTC manages spent
nuclear fuel from GA Siwabessy
Multipurpose Reactor. Spent nuclear fuelafter taken from the reactor is stored at
the reactor storage poolfor initialcooling as long as 100 days to reduce
decay heat and activity, then transferred
to Interim Storage for Spent Fuel (ISSF).

material

In general, solid radioactive wastes
areclassified
intoburnable(combustible),compactible
anduncombustible
uncompactible.
Combustible solid radioactive waste
such as paper, wood, contaminatedclothing was processed using incinerator.
The capacity incinerator unit is 50 kg / hr.
Effluent of incinerator is processed byfiltering using HEPA filter and thenscrubbing for neutralization in washingcoloumn.
While the remaining
radionuclides is concentrated in ash,further the ash is immobilized in a 100
liter mild steel drum using cement matrix.
The compactible solid radioactive
waste such as cans, glass, soft metal, andplastic, was packed in a 100 liter shell
drum. A several the packed waste iscompressed into a 200 liter using
compactor with hydraulic force 600 kN.
And then immobilized by cement matrix.
An uncombustible uncompactible solidradioactive waste such as soil, sludge,
iron and other hard metals was packed inq 100 liter drum. Furthermore, a 100 litershell drum is inserted into the a 200 litershell drum and immobilized using
cement matrix. Finally, treated waste isstore at interim storage building.

Japan
Dr. Shoji Futasukawa
Japan Radioisotope Association

The influence on radiation handlingestablishments of the Great East Japan
Earthquake
1. Introduction

An observation earthquake biggest(Mw.9.0) in history around Japan whichassumed the bottom of the sea of 130km
from the coast was generated on March
11, 2011. The maximum seismic
intensity was 7 and the influence of theearthquake extend to the whole East
Japan (the focal region of north-south
500km, East-West 200km). By theearthquake, a huge tsunami more than
20m in height was generated, andcrushing damage occurred in the coast ofPacific of the Tohoku district and the
Kanto district. The dead person and themissing person caused by the earthquake
and tsunami disaster were equal toapproximately 20,000 people. In addition,
the Tokyo Electric Fukushima First
Nuclear Power Plant accident was

Disused Sealed Radioactive Sources(DSRS) management

Spent sealed radioactive sources
shall be managed as radioactive waste.
There are two options for the9caused by the huge tsunami. Radioactive
materials from the plant were released byenvironment and extensive areas of theEast Japan have been contaminated byradioactive materials. Therefore many
beginners measure a radiation using
radiation detectors.
Also much radiation handlingestablishments (institutes and facilities)
which have been permitted by MEXT
existed in the crushing damage area
(about 480). The MEXT investigatedwith hearing the damage situation ofthem promptly, but security wasconfirmed in all institutions and facilities
except one facility.

makers make new radiation detectors(survey meter). Also the radiation survey
meters which the certifications are notattached of inferior quality are imported.
Because many people performed
radiation measurement of the private or
public place where nobody had measureso for, some radiation sources under nocontrol were discovered. The radiation
sources most were Ra-226 which they
were used as luminous paints before
laws are established (Table1).
Many NaI(Tl) scintillation detectors
and Ge semiconductor detectors aresupplied for measurement of radiationmaterials in soil, food and so on.
Consumer Affairs Agency has set 394
NaI(Tl) scintillation detectors in 279related local government for screening
investigation of food contamination.
About 400 conventional double Ge
semiconductor detectors have been
installed (not official data). A lot ofstandard sources are necessary for the
proofreading of these radiation detectors.
Table2 shows the numbers of standard
sources supplied by JRIA before andafter the accident. The number ofstandard sources after the accident isincreased rapidly than one of before theaccident. The data also indicate theincrease of the number of the radiation
detectors.

2. Confirmation result of a radiation
sources affected by the Great East
Japan Earthquake

As for the confirmation contents andthe result of the situation of theradioisotope sources which were used in
the radioisotope handling establishmentsof Pacific coastal areas damaged by theGreat East Japan Earthquake, following.
(1) About 230 institutes and facilities
were located in the area limits more thanseismic intensity of 4 and used theradioisotope sources having a big
quantity of radioactivity. The security
was kept in all institutes and facilities.
(2) About 250 institutes and facilities
were located in the area facing the
Pacific damaged by the tsunami and used
the radioisotope sources having a little
quantity of radioactivity. Only one
radiation source (Co-60 (2.59MBq) +Cf252 (1.11MBq), for Moisture-Gauge) in
one facility was lost, but the security was
kept in other institutes and facilities.

4. Conclusion

The Great East Japan Earthquake has
many influences in various fields.
Though it was a great earthquake
disaster, the safety of the radiation
handling establishments located in thearea almost was secured.

3. Radiation measurement since the
Nuclear Power Plant Accident

Many beginners measure radiation
using various radiation detectors since
the Nuclear Power Plant Accident.
Various kinds of domestic and importradiation detectors are supplied. Not
domestic radiation detector makers but
also domestic other various goods

10Table1. Radiation sources under no control discovered in private or public place since the accident

Date

Place

2011.10.14.
2011.11.10.
2011.11.16.

NuclidePrivatehouse Ra-226
where a person das
not live in.
Private house.
Ra-226(370Mbq)
Private house.
Ra-226(16kBq)2011.11.24.

The city land.

Ra-226(370MBq)(555MBq)(1,100MBq)
Ra-266(160kBq)

2011.12.15.

Private house.

2011.12.21.

Secondary school.

Ra-226(100kBq)

2012.01.13.

Public park.

Ra-226(11,900Bq/kg)

2012.03.09.

Private house.

2012.04.18.

Bicycle maker.

2012.11.22.

Super market.

Ra-226(90MBq)Co-60(131.4kBq/
basket)Ra-226(2GBq)

Form

Handling

Dozens of bottles which radiation powder Put it in a lead container andwas in, under a floor.
enclose it in a metal can.
Radiation source (3mmφ×20mmL) in a metal
can.
Radiation materials in a glass tube
(5mmφ×50mmL),
in
a
paper
box
(200mm×20mm×50mm) which was written
as luminous paint.
A radiation source in a lead container(45mmφ×80mmL) and other radiation
sourcesina
metal
container(15mmφ×65mmL)
Radiation powder in a glass tube
(10mmφ×50mmL), in a metal can which was
written as radium paint.
Radiation source (5mmφ×250mmL) in a tube
(10mmφ×50mmL), in a glass container(30mmφ×70mmL)
Contaminated soil.

Contaminated soil.
The bicycle with contaminatedimported. (See Fig.1)

Enclose it in a metal can.

Decontaminated.

No contamination.
No contamination.
Cover the surface with aplastic sheet, and closed tothe public takes a step with aprotective fence.
Put it in a metal cans.

basket Collection of
bicycles (3,200)

Contaminated soil. (See Fig.2)

Figure1. Same type basket of the contaminated basket

No contamination.

Put it in a metal cans.

Figure2. A lump of the contaminated soil

Table2. The numbers of standard sources supplied by JRIA

Fiscal year

2010

2011

2012 (till February)

Volume source (9 nuclides)

128

663

294

Aspect source (9 nuclides)

49

35

26

Cs-137 point source

138

834

703

Cs-137 volume source

1

121

203

316

1,653

1,226

total

the

11

sold

environment
exercises.

Thailandforpractical

filming

By the end of the week, each of theparticipants had written a script fromwhich they had then shot and edited theirown video. So now these nuclear
specialists are able to post short technical
videos on a shared global educational
resource available to anyone involved indecommissioning nuclear power-plants.
The next Workshop on Capture of High
Quality Video Materials with Core Users
will – provisionally - be held in Thailand
around November 2013.

Ms. Nanthavan Ya-anantThailand Institute of Nuclear
Technology (TINT)
Experience on the Inter-Regional
Workshop on Capture of High Quality

What is CONNECT?
CONNECTisaweb-basedcollaboration platform hosted by the
IAEA on behalf of its Member States. It
provides a gateway for interconnecting
existing and planned IAEA networks,
increasing
theparticipationofindividuals and organizations involved inthem, and making available additionalsources of information that complement
existing training workshops andmeetings. CONNECT also provides an
e-library of audio-visual material and adata-baseofconcise,structured
summaries of the “lessons learned” fromsuccessful and unsuccessful projects.

Figure1. Participants of the Workshop at the KIT,
Karlsruhe, Germany

The Inter-Regional Workshop on
Capture of High Quality Video Materials
with Core Users - Part B: Field Video
Production was held in Karlsruhe
Institute of Technology (KIT), Karlsruhe,
Germany, during the week of 18-22
March 2013.
The participants were
nuclear specialists, coming from Algeria,
China, Egypt, Indonesia, Kazakhstan, Sri
Lanka, Sudan, Tajikistan, Thailand,
Ukraine, and Yemen.

CONNECT can be accessed on
http://nucleus.iaea.org/sites/CONNECTThe purpose of the workshop was toprovide an opportunity for individualorganizations that are actively engaged
in CONNECT, or in a related IAEA
Network,
toobtainprofessional
instruction and hands-on training in theart of making short technical videos.
The classroom training in video
production technique was centred aroundan imaginary scenario to dismantle aradioactive
componentinadecommissioning nuclear Power-plant.
The KIT provided a highly realistic(though not genuinely radioactive)

12

The FNCA RS&RWM Project Leaders
Australia

Bangladesh

Dr. Lubi Dimitrovski
Manager,
Waste Operations
Safety and Radiation Servic
Australian Nuclear Science &Technology Organisation(ANSTO)

Dr. Moinul Islam
Principal Scientific Officer,
Health Physics & Radioactive
Waste Management Unit,
Atomic Energy Research
Establishment (AERE), Bangladish
Atomic Energy
Commission (BAEC)
Deputy Director General,
Department of Safety, Protection
and Quality,China National
Nuclear Corporation (CNNC)

Indonesia

Head of Safety and Environment
Division, National Nuclear Energy
Agency (BATAN)

Malaysia

Dr. Mohd Abdul Wahab
Yusof

Professor,
Nuclear Professional School,
Graduate School of Engineering,
The University of Tokyo

Mr. Yuriy Aleinikov
Head of Laboratory,
Department of Reactor Research,Institute of Atomic Energy,
National Nuclear Centre of the
Republic of Kazakhstan

13

Director,
Radioactive Waste
Management Policy Office,
Korea Radioactive Waste
Management Corporation(KRMC)

Senior Research Officer,
Waste Technology &Environment Division,
Malaysian Nuclear Agency(Nuclear Malaysia)

Ms.Oyuntulkhuur
Navaangalsan
Head,
Radiation Regulatory
Department,
Nuclear and Radiation
Regulatory Authority,
Nuclear Energy Agency

Mr. SyahrirProf. Toshiso Kosako

Kazakhstan

Dr. Chang Lak Kim

Mongolia

Dr. Zhang Jintao

China

Japan

South Korea

Philippines

Ms. Maria Visitacion B.
PalattaoHead, Regulations andStandards Development
Section, Philippine Nuclear
Research Institute (PNRI)

Thailand

Mr. Sutat Thiangtrongjit
Director,
Radioactive Waste
Management Center,
Thailand Institute of Nuclear
Technology (TINT)

Dr. Le Ba Thuan

VietnamDirector,
Institute for Technology ofRadioactive and rare Elements,
Vietnam Atomic Energy
Institute (VINATOM)

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