Jan 2010

No.3
Issued by
VAEI andJapanese FNCA
OfficeFNCA 2009 – Workshop on
Radiation Safety and Radioactive Waste Management (RS & RWM)
Agust 3-7, 2009, Hanoi, Vietnam

The FNCA 2009 Workshop on Radiation Safety and Radioactive Waste Management was held from
August 3 rd to August 8th, 2009, in Hanoi, Vietnam. This Workshop was hosted by the Institute forTechnology of Radioactive & Rare Elements (ITRRE) of Vietnam Atomic Energy Institute (VAEI), as the
local host organization, and the Ministry of Education, Culture, Sports, Science and Technology (MEXT)
of Japan, in cooperation with Nuclear Safety Research Association (NSRA) of Japan.
Representatives from nine FNCA member countries involved in policy making, regulations, operations andR&D on radio safety and radioactive waste management attended the workshop, i.e. Australia, Bangladesh,
China, Indonesia, Japan, Malaysia, The Philippines, Thailand and Vietnam.
On the first day, Session 1, the project leader of Japan, Prof. T. Kosako provided basic information andideas of radiation protection in accordance with the recent activities in IAEA and ICRP. In session 2, thecountry reports were presented on the current status and progress of radiation safety and radioactive waste
management activities in each FNCA country. Each country report was provided as a draft consolidated
report which is expected to be finalized by March 2011.
1

After Session 2, a Poster/Mini-Exhibition was held to facilitate enhancement and understanding ofactivities in RS & RWM among FNCA countries.
On the second day, an open seminar was held as Session 3 with specific safety topics “Personal dosimeter:
calibration, standardization and exposure control”. For this session, each country provided introduction andexplanations on the theme of standardization to promote comprehensive understandings from different
viewpoints of FNCA countries. And then Session 4 was held on the subject of Radioactive Waste
Management, Theme (1) is Efforts in the field of Radioactive Waste management. In Theme (2), the statusof the Japanese waste program and introduction of recent status of IAEA safety standards in the field ofradioactive waste was provided as well.
On the third day, a technical visit was made to Bach Mai Hospital in Hanoi city and the Institute for
Nuclear Science and Technology (INST) of VAEI to observe the status of radiation safety including
training and education in exposure control and radiation source management.
On the fourth day in session 5 the theme “Preparation for Radiation Safety System and Radioactive Waste
Management for first NPPs” was held as the open seminar. For this session, Vietnam regulatory andoperational personnel provided information on the status of the nuclear power development in Vietnam.
Following these presentations, a DVD presentation on Japan's early stages in nuclear power program
development was made. Japan also presented on the radioactive waste management system for nuclear
power plants. Theme (2) consisted of presentations on “Radiation Safety at Large Scale Facilities such as
Accelerators, Nuclear Research Reactors, Hospitals and/or Industry”. The presentations in this session
were provided by Malaysia, Australia and the Philippines.
In Session 6, a roundtable discussion on "Future cooperation with the other international programs such as
IAEA/ANSN and RCA/RAS9042" was held with update reports by each country related to these programs.
The "RS&RWM 3-Year Work Plan for 2008-2010" under the FNCA framework was confirmed anddiscussed, and successfully concluded. The next workshop in 2010 will be held in Tokyo.
All FNCA Project Leaders recognized the high value provided by the FNCA RS&RWM Workshops. The
benefits gained include information exchange and the sharing of experiences on common radiation safety
and radioactive waste management issues. The Project Leaders were unanimous in their support for the
FNCA RS&RWM workshops and expressed the need to sustain this cooperation to ensure that radiation
safety and radioactive waste management issues are continually addressed in the region.
Participants of this Workshop expressed appreciation to the organizers, ITRRE of VAEI and MEXT, and tothe cooperation of NSRA.
Topics from Participating Countries

Australia: Upgrading of ANSTO’s
Intermediate Level Waste Storage Facility
ANSTO’s Waste Operations receives around2,500 liters of intermediate level solid waste every
year from activities such as radiopharmaceuticals
production, site decontamination projects and2decommissioning works. These wastes are stored
in ANSTO’s intermediate level solid waste
facility in Building 27 (B27) (Figure 1). To ensurea reliable and effective facility infrastructure tocater for ANSTO’s current and future ILSW
management needs, B27 underwent an upgrade in2009 with the bringing up to full operating
capacity of the retrievable pits, and the clearingout and re-rationalization for use of the decaycells.
Decay
cells

fitted into the 7.2m deep pit (Figure 2 & 3). Eachpit is divided into eight stacks, and each of thesestacks is now capable of holding 18 waste bins.
The retrievable pits are now 55% full. The
remaining capacity will cater to ANSTO’s ILSW
management needs for the next 12 years at thecurrent generation rate.

Retrievable
Pits

Figure 2: Installation of pit guide frame
Figure 1: Intermediate level solid wastes storage
facility
Retrievable pits
The eight storage pits were part of B27’s easternend extension, constructed in 1987 to allow for
the safe storage and retrieval of intermediate levelsolid waste. Until March this year, the retrievablepits were operating at less than 70 per cent of its
designed capacity. This is due partly to the limitsof the overhead crane travel, as well as theabsence of racks in two of the storage pits.

Figure 3: Fully installed pits
Decay cells
As part of ANSTO’s commitment to effective
utilization of resources, intermediate level solid
wastes with short-lived radionuclides (half-life<2years) are subjected to a separate processing
route. Short-lived ILSW (usually fromradiopharmaceutical productions) are held ininterim storage in the B27 decay cells to allow for
decay. Six decay cells in B27 were classified
according to dose rates, ranging from 500uSv/h to
10mSv/h. A campaign was set up every two years
to reclassify and move the decayed waste
packages to a lower range decay cell or removed
to be processed as low level solid waste.

The process of bringing the remaining 30 per centonline involved first of all the extension of part ofthe eastern end wall and the overhead crane rail.
This extension will enable the crane travel toreach the eight eastern-most stacks of the facility.
This greater access is necessary also for the
installation of the pit frames, plugs and bin guideframes. Due to the radiation shine from theintermediate level solid wastes stored in theexisting pits, steel plates were placed over the pit
as shielding for workers working on the crane railand building wall. Dose rates at the walls weredecreased from 80uSv/h to less than 7uSv/h after
shielding afforded by the 10mm thick steel plates.
A limit of 10uSv per day was set for external
contractors working on the project.

However since commencement of operation of the
Decay Cells departure from the original intended
use of these cells over the years has caused
several problems. Wastes with long-lived
radionuclides were stored in the cells, resulting inover-spilling containment and increased dose
emanation from the cells to the outside of thebuilding. Missing and incomplete documentation

The pits were carefully measured out for thedesign and manufacture of the pit frames, plugs
and bin guide frames. Once completed, the pit
frames, plugs and bin guide frames were carefully3

of the packages also made identification thewastes impossible. Deterioration of the waste
packages posed a contamination issue, a problem
exacerbated by improper ‘stacking’ of the
packages (Figure 4).

entering the cell when depositing the waste
packages.

Figure 7: Shielded box for use inside decay cells
The waste logging and storage systems were also
revised to prevent recurrence of similar problems
in future.

Figure 4: State of decay cells before clean up
A dedicated team was organized to clean up the
decay cells under close monitoring by healthphysics surveyor. The wastes were removed fromthe cells, repackaged and reassigned to the proper
waste storage areas (Figure 5).

Figure 5: Removal of wastes from decay cell
The cells were then decontaminated down to fixedcontamination and painted over. Concrete blocks
and steel plates were installed to provide
additional shielding to all the cells (Figure 6).

Standard Dosimetry in Bangladesh
M. Moinul Islam1, Satyajit Ghose2 & Md.
Shamsuzzaman1
Figure 6: Decontaminated decay cells painted
after extra shielding were installed

1

Health Physics and Radioactive Waste
Management Unit
2
Nuclear Safety & Radiation Control Division
Bangladesh Atomic Energy Commission

Specially designed shielded boxes (Figure 7) will
be used in the cells as secondary containment andshielding to prevent unnecessary dose to operators
4 Participated in IAEA/WHO dose quality audit
programme for radiotherapy. The observed dose
variation is within IAEA acceptance limit

A considerable number of stakeholders around thecountry using the radiation measurement devices
as a result of rapid increase in nuclear applicationsin health, industry, agriculture sectors as well as
nuclear research conducted at a 3-MW TRIGAMark II research reactor. Approximately five
thousand radiation workers are now employed indifferent
radiological/nuclear
facilities
inBangladesh and eighty percent of the workers are
directly involved at a diagnostic X-ray
installation. To minimize the risk and avoid
radiation hazards to occupational worker, public
and the environment all the radiation measuring
instruments must be calibrated and tested at a
certain intervals (not exceeding 12 months) as per
Nuclear Safety Radiation Control Act 1993 &Rules-1997. For the purpose of calibration andstandardization of these radiation monitoring
equipments a secondary Standard Dosimetry
Laboratory (SSDL) was established at Atomic
Energy Research Establishment (AERE) Savarsite in 1988. This standard laboratory is traceable
to Primary Standard Laboratory of National
Physical Laboratory (NPL), UK.

Secondary Standard Dosimetry Laboratory
Facility at INST
Calibration Facility at SSDL
The following standard sources and equipments
are available in SSDL for calibration of radiation
measuring instrument:
Gamma Calibrator: OB 34, OB 85 and OB 2
Standard sealed radioactive sources are used tocalibrate beta-gamma radiation survey instrument.
Beta
Calibrator:
Used
tocalibratecontamination monitoring instruments andpersonal dosimeters.

Objectives

Neutron Calibrator: A collimated beam neutron
calibrator of model OB 26(241Am-Be) is used forcalibration and standardization of Neutron
measuring instruments.

 To ensure that the calibration of radiation
measuringequipments
confirms
tointernationally accepted standards

Calibration of X-ray Machine: An X-ray
machine has been provided by IAEA is now
available in Secondary Standard Dosimetry
Laboratory to perform calibration work for x-rayunits

 Calibration & standardization of radiation
monitoring devices used in health sectors,
research, industry, agriculture QA services in teletherapy, deep-therapy &diagnostic X-rays, fluoroscopy, medical
LINACSStrengthening of SSDL Facility
In July 2006, the Ministry approved the‘Strengthening of Secondary Standard Dosimetry
Laboratory Facilities’ project and provided a total
amount of (~ US$ 3.2 million) to implement the
project at AERE Savar. The Health Physics &Radioactive Waste Management Unit of Atomic
Energy Research Establishment (AERE) has the
responsibility for implementing the project. The
main purposes of the strengthening of SSDL
facility are:Recent Work Approximately 900 TL dosimeter and 86
radiation measuring instruments (e.g. Survey
meter, pocket dosimeter) have been calibratedusing SSDL facility over the last year Quality Assurance programme for 60Co
teletherapy machine used for cancer treatment
are being conducted5 To enhance the existing calibration andstandardization facility of radiation measuring
equipments (e.g. survey meter, area monitor,
pocket dosimeter etc.)

Publication 60 recommendations, the results ofthe studies are relevant to ICRP 2005. The
studies concern on the implication of dose limits
and the implementation of the changing
parameters in ICRP Publication 60. Somethoughts on the implication of adopting ICRP
2005 to Indonesian regulation are also discuss.

 To conduct quality assurance programs on
personal dosimeters
 To facilitate the calibration work of radiation
beams at different radiotherapy centers

Study on Dose Limits

 To improve and ensure the quality assurance
programme for teletherapy, deep-therapy X-ray
unit, diagnostic X-ray, brachytherapy, LINAC
etc.

BAPETEN has assessed the impact of applying
dose limits from BSS-115 [3]. The agency
reviewed personal dose records from stakeholders which are reported routinely. Figure 1
show 2005 personal dose records in Industry andResearch gathered by BAPETEN. Among 1447
radiation workers, about 0.8% or 11 persons
received effective doses more than 20 mSv/year
which came from radioisotope production asshown in Figure 2.

 To conduct R & D works on Medical Physics
related field

The personal dose records in industry andresearch show only a few workers reside on thethird band of the projected effective dose (20 to
100 mSv/year) in Table 5 of ICRP 2005 [1].
Based on the investigation to the workers, it turns
out that most of the doses relate to non-routine
situation that needs additional specific measuresor pre-planned protection strategy like inmaintenance and non-compliance to procedures.
This evidence endorses the adoption of therecommendation.

Challenges in the Implementation of the New
ICRP
Recommendations:
Views
from
Indonesia
Syahrir, National Nuclear Energy Agency
Introduction
Indonesia has two independent government
agencies in nuclear energy, i.e. National Nuclear
Energy Agency (BATAN) and National Nuclear
Energy Regulatory Agency (BAPETEN).
BATAN is an operating organisation and has arole as a promoting body in nuclear technology.
And BAPETEN is a regulatory authority on
nuclear energy through regulation, authorizationand inspection. In addition to BATAN, somemedicine and industry utilize radiation sources
and all of them are authorized by BAPETEN.

Figure 1. Personal dose in industry and research in
2005.

BAPETEN is in the process of imposing BSS-115
to its regulation. BAPETEN and BATAN havesome studies on adoption of BSS-115 and ICRP
60. Since ICRP 2005 is continuation to ICRP
6

than those from ICRP 30. Similar results wereobtained from International Internal Dose
Intercomparison which is coordinated by IAEA.
The comparison indicates significant differences
as a result of different dosimetric parameters usedsuch as fraction of intake, retention factor, doseconversion factors etc.
Discussion
ICRP 2005 reinforces that optimisation isprobably the main tool for reducing exposure,particularly at workplace. Table 5 [1] on bands ofprojected effective dose is useful to reinforce
optimisation by implementing dose constraints
and reference levels based on representative
persons:

Figure 2. Personal doses in radioisotope production in
2005.

Although most of radiation protection officers inIndonesia know well on regulation related toradiation protection, according to the BAPETEN
survey, many of them have never come acrossneither ICRP 60 nor BSS-115. Optimisation, as
stated in those documents, is not as concerned asdose limitations. It would be very useful toprovide them examples on optimisation forradioprotection purposes.
Assessment
CalculationofInternal

Radiation

1. dose effective to a representative persons
below 0.01 mSv/yr is considered
exemption, no need to control (noenvironmental monitoring)
2. The 20 to 100 mSv/year band to arepresentative person can be used toreinforce emergency situation.
The concept of intervention for existing exposure
situation is used by BAPETEN to cope withTENORM in mining and industry.

Dose

The calculation of effective dose or corresponding
conversion coefficients for external exposure, as
well as dose coefficients for internal exposure, arebased on absorbed dose, weighting factors (wR
and wT) and reference values for the human bodyand its organ and tissues. Internal dose calculation
using ICRP 30 and 68 recommendations arecompared.

By adopting the recommendations, we are abiding
to dosimetric models and parameter values that
the Commission recommends for determining
doses. Parameters for effective dose are absorbed
dose, weighting factors (wR and wT) and reference
values for the human body and its organ andtissues. Based on the prior internal dose
calculation, it seems the new weighting factors
and reference values are significant theircontribution to the effective dose compares to the
old ICRP 26. The new dosimetric calculation
results internal effective dose considerably larger
than the old one, conversely its dose limit(20 mSv/year) is lower than one from ICRP 26(50 mSv/year). The Radioisotope Production
Installation in Serpong should be more wary once
the recommendations imposed in Indonesia.

The results of whole body counting systemmeasurements to workers in Serpong Nuclear
Center were used to determine their internal
effective doses based on ICRP Publication 30 and
68; these publications implements ICRP 26 and
ICRP 60, respectively. Three most frequent
radionuclides found on workers were used in thecalculation, i.e. 131I, 137Cs, and 95Zr. The
comparison calculation results for intake time t =30 are given in Table 1.

There should be human resources associated withcalibration and personal dosimetry services
develop and maintain appropriately in order tocomply with international regulation. Moreover

The comparison shows that the results of intake
and dose from ICRP 68 are always larger thanones from ICRP 30 for the three radionuclides.
On average, the dose from ICRP 68 is 1.27 larger
7

BAPETEN shall provide standard and guidance in
implementing the recommendation, especially to
avoid misunderstanding among stakeholders. In
this case, harmonization among stakeholders isimportant for its accomplishment. At least, thereis same perception on the terminology anddosimetric quantities
recommendation.

mentioned

inthe

There should be program to disseminate therecommendation to the whole world which may
need different approaches to accomplish it.

Table 1. Comparison of internal dose calculation based on ICRP 30 and 68
No.
1.

2.

3.

Radionuclide

Intake (Bq)
ICRP 30ICRP 68FK

ICRP 30ICRP 68

FK

131

61865

104771

1.69

0.54

0.80

1.48

184237312015

1.69

1.62

2.37

1.46

8287621403548

1.69

7.29

10.67

1.46

3112

6104

1.96

0.03

0.03

1.00

21700

42565

1.96

0.19

0.21

1.11

39147

76788

1.96

0.34

0.37

1.09

12527

34039

2.72

0.07

0.09

1.29

81802

222289

2.72

0.43

0.56

1.30

I

137

Cs

95

Zr

Dose HE (mSv)

to change their mind set from dose limits toradioprotection optimization principle (ALARA).

Conclusions

Since the recommendation relates to dosimetricmodels and their relevant parameters, BATAN
and BAPETEN have to prepare the infrastructure
and its human resources appropriately. They may
need expertise from ICRP or other internationalorganizationon
implementing
therecommendation, especially on dosimetric issues.

Based on 2005 personal dose records in Industry
and Research which is not much different to theother years, Indonesia may adopt new dose limits
with caution on determining personal doses since
the changes in parameters and reference values
for the human body and its organ and tissues.
It is important to use the same understanding on
relevant terminology and dosimetric quantities(representative
person,existing
exposuresituation, effective dose, sievert, gray etc.). It
needs appropriate human resources with expertisein the new dosimetricmodeling forradioprotection.

REFERENCES
1. ICRP, Draft Recommendations of The
International Commission on RadiologicalProtection (January 2007).
2. FOODAND
AGRICULTURE
ORGANIZATION OF THE UNITED
NATIONS, INTERNATIONAL ATOMICENERGY AGENCY, INTERNATIONALLABOURORGANISATION,OECD
NUCLEAR ENERGY AGENCY, PAN
AMERICAN HEALTH ORGANIZATION,WORLDHEALTHORGANIZATION,
International Basic Safety Standards forProtection against Ionizing Radiation and for

Basically, no fundamental differences between
ICRP 2005 and ICRP 60 so if Indonesia will leavebehind ICRP 26, ICRP 2005 should be adopted.
The adoption of the new recommendation will
drive the implementation of optimization more
stringent. Emergency situation may be applied toa facility with projected effective dose more than
20 mSv/year. It is time for the users, especially inindustry radiography and radioisotope production,8the Safety of Radiation Sources, Safety SeriesNo. 115, IAEA, Vienna (1996).

service at the Tokyo factory in Hino city. Also,
Fuji Electric Systems has a calibration facility inthe site, which provides traceability to national
standards of Advanced Industrial Science andTechnology (AIST).

3. BAPETEN, Study on the Impact of BSS115’s Dose Limit Application to Industry andResearch, in Indonesia, BAPETEN (2006)
4. TEDJASARI, R.S., Assessment of Internal
Radiation Dose Calculation to Radiation
Workers Using ICRP Publication 30 and 68,
in Indonesia, BATAN (2005).

Figure 1 Fuji Electric Systems Calibration facility
building

In order to calibrate various types of Fuji
Electric Systems radiation measuring equipment,
the facility employs 4 kinds of calibrators withdifferent nuclides and the intensities.

Radiation measuring calibration in JapanThe calibrator for high level gamma-ray can be
operated remotely with using ITV camera and a
movable carriage, which can move an object
being calibrated in 3 axis directions.

Radiation measuring equipment has become
widely used among Nuclear Power Plants,
laboratories of universities or companies, or
medical facilities in Japan. Especially electric
personal dosimeters are widely used andnecessary to have the traceability from national
standard to practical measurement devices. In
spite of the number of dosimeters currentlyoperated, calibration facilities are limited in
numbers in Japan. For that reason, more efficientsystems which can perform speedy calibration areneeded.
In this article, the calibration devices andfacilities of Fuji Electric Systems are introduced,
because this company is one of the leading
manufacturing company of radiation measuring
products in Japan and its contents are suitable forthe examples of information for the latest trend of
calibration.

Figure 2 High level gamma-ray calibrator

8 types of radiation sources are held in thefacility, which can handle a wide range ofirradiation from BG level to 200mGy/h (Refer tofigure 1). Also, a specific source can be chosenwith the auto-selection system for equipment witha specified calibration manner.

Fuji Electric Systems offers total radiation
measuring
services,suchasdesign,manufacturing, repairing and other after-sales
9The automatic control panel operates thecalibrators, data collection, the organizing ofcalibration results, generations of calibration
records, source operation records and source
storage record.

Figure 4 Objects calibrated
Table 1 Nuclide, intensity and irradiation dose
equivalent rate range

Figure 3 Control Panel

Their middle level gamma-ray calibrator is ideal
when using for personal dosimeters andenvironmental
radiation
monitors.
The
characteristics of this device are that it performs
automated simultaneous calibration of 50 units
and that only takes about 10 minutes. Neutron
calibrator calibrates survey meters, neutron area
monitors and dosimeters. It is equipped with anautomated transportation system for personal
dosimeters, which allows continuous irradiationof over 20 units.

Radiation Dosimetry at Malaysian Nuclear
AgencyDr Mohd Abd Wahab Yusof1 and Mr Taiman Bin
Kadni2
1

2

Also, there is a small and compact-sized beta-ray
calibrator which calibrates multi-ray dosimeters.

1.

Fuji Electric Systems calibration facility offers awide range of efficient and highly accurate
calibrations for various measuring equipment
utilizing the automated system.

Waste Technology Development Centre(WasTeC), Nuclear Malaysia

Secondary Standard Dosimetry Laboratory(SSDL), Nuclear Malaysia
Introduction

The main activities of the Secondary Standard
Dosimetry Laboratory (SSDL) of the Malaysian
Nuclear Agency (Nuclear Malaysia) are to
maintain the reference standards i.e. secondary
10

standards for dosimetry in radiotherapy,
brachytherapy, radiation protection and radiation
processing such as sterilization of medical
products and food irradiation. The standards at
this laboratory are maintained and reference
standards calibrated against the Primary Standard
Dosimetry Laboratory (PSDL) and IAEA
Dosimetry Laboratory. SSDL-Nuclear Malaysia
also regularly participates in international intercomparison of radiation measurements organizedby the IAEA or the Regional Metrology
Organization (RMO).

Figure 2: Standardization of 90Sr/90Y beta sources(1.85 GBq and 74 MBq) using extrapolation chamber

2. Calibration Services
In Malaysia, radiation-measuring instruments are
required to be calibrated annually. The Nuclear
Malaysian is the sole provider of calibration
service for all radiation measuring instruments
used in Malaysia. The service offered by Nuclear
Malaysia is accredited in accordance with the
ISO/IEC 17025:2005 standards.

Figure 3: Calibration facilities for
gamma sources

2.1 Therapy level dosimeters
All therapy level dosimeters from radiotherapy
centres in the country are calibrated in terms ofboth air kerma calibration coefficient (NK) andabsorbed dose to water calibration coefficient(NDW). All of them are calibrated against 60Co
gamma source. These calibrations are performed
against secondary standard dosimeters withtraceability to the IAEA standard for 60Co gamma
rays.

Figure 4: Calibration of survey
meter using x-ray machine

2.3 Beam output calibration of medical linear
accelerator (linac).
Nuclear Malaysia is also provided calibration
services of megavoltage X-rays beam output (i.e.
6MV and 10MV) of linear accelerator (Linac).
The beam output measurements are performed byusing ionization chamber immersed in water
phantom of dimension 30 cm x 30 cm x 30 cm.
The IAEA TRS-398 is used to determined theabsorbed dose to water at specified depth e.g. 5
cm and 10 cm depth based on the energy of themegavoltage X-rays.

Figure 1: Calibration facilities for therapy level
dosimeters

2.2 Radiation protection instruments
Radiation monitoring instruments (survey meters)
are calibrated against X-rays, gamma rays, beta
rays and neutron. Beside survey meters, thelaboratory also calibrates its personal dosimeterssuch as pocket dosimeters and electronic personal
dosimeters (EPDs).

3. Personal Monitoring Service11

Nuclear Malaysia provides personal monitoring
services to all radiation workers in Malaysia. The
service is based on both film and thermo
luminescence dosimeter (TLD) badges. Bothdosimeters are used to monitor whole body dose.
TLD is also used for monitoring partial body
exposure with special emphasis on finger ring
dosimeter and area/environmental monitoring.
The dosimeters are issued on monthly basis andthe dose of personal dosimeters are processed andevaluated every month. The Harshaw 6600
Automatic TLD reader is used to evaluate
personal dose equivalent of TLD badges while theextremity dosimeters are evaluated using Harshaw
5500 TLD reader. The personal monitoring
service has been certified according to the Quality
Management Systems MS ISO 9001:2000 since
May 2003 by the local certification body i.e.
SIRIM QAS International Sdn. Bhd. In addition,
the E-SSDL (online service) is used to upgrade
the personal monitoring service.

APMP.RI(I)-K2:Nuclear Malaysia participated ina key comparison of air kerma standards for CCRI
reference beam qualities (5 qualities) and ISO
4037 narrow spectrum series (2 qualities) in lowenergy X-ray region (10kV-50kV) which
commenced in the middle of September 2008.
Three transfer ionization chambers {NE 2536/3(0.3 cm3), Exradin Magna (3.0 cm3) andOyogiken AE-1340C (0.24 cm3)} were comparedat seven beam qualities. The key comparison was
co-ordinated by NMIJ/AIST, Japan. Ten (10)National Metrology Institutes (MNIs) wereparticipated in this comparison.
5.2 Comparison with the IAEA.
The performance of SSDL Nuclear Malaysia
therapy level dose measurements is regularly
monitored through a postal TLD service provided
by the IAEA. In May 2008, Nuclear Malaysia
participated in IAEA/WHO TLD Postal dosequality audit for 6MV X-ray beam from medical
linear accelerator (linac). The results of this intercomparison show that the level of dose measured
were within the IAEA acceptance limit.
5.3 Comparison with the National PhysicalLaboratory (NPL), U.K.
The National Physical Laboratory (NPL), United
Kingdom provides traceability to the international
measuring system for high dose measurements.
High dose dosimetry quality control using
dichromate transfer dosimeters supplied by the
NPL were used for comparison. The comparison
involved the measurement of doses within therange of 9 - 40 kGy using 60Co gamma radiation.
Prior to irradiation of dichromate dosimeters,
ceric-cerous dosimeters were used to determine
dose range of 9 – 40 kGy at Nuclear Malaysia’s
60
Co self-shielded irradiator for high dose
irradiation. After irradiation, the dichromate
dosimeters were returned to the NPL for
evaluation. The results of this comparison were
within 3 – 6 % of the NPL’s standard.

Figure 5: TLD readers facilities at Nuclear
Malaysia
4. High DoseApplication

DosimetryforIndustrial

The reliability and accuracy of the dosimetersystem plays a very important part of processcontrol and quality assurance in industrial
radiation processing. Nuclear Malaysia supplies
ceric-cerous dosimeters to the commercial
irradiation plants. These dosimeters can measuredoses in the range of 5 kGy – 50 kGy.

5.4 Personal dosimetry inter-comparison.
Nuclear Malaysia also participated in personal
dosimetry inter-comparison programme in
October 2007 organized by the Chiyoda Technol
Corporation (CTC), Japan. Two radiation
qualities i.e. 60kV X-ray (narrow spectrum series)

5. International Comparison Activity
5.1 Key comparison.
12and 137Cs were used for the irradiation of personal
dosimeters. The personal dosimeters, including
glass badges supplied by CTC, were irradiatedwith doses of 0.3 mSv, 2 mSv and 20 mSv.
Nuclear Malaysia used both TLD badge and film
badge for this intercomparison programme. The
results were in good agreement with deviation ofless than 10%.
Nine facilities from sevencountries (Brazil, China, Indonesia, Korea,
Malaysia, Taiwan and Vietnam) were participatedin this inter-comparison.

8.

Calibration
andCapabilities (CMCs).

Measurement

Nuclear Malaysia’s Calibration and Measurement
Capabilities (CMCs) have been approved andpublished in Appendix C of the Bureau
International des Poids at Mesures (BIPM) Key
Comparison Database (KCDB) since 11
September 2008. Nuclear Malaysia’s CMCs
include 15 calibration services:c. APM-RAD-MNA-1001: Air kerma rate, 60Co
(radiation therapy)

6. Low Energy X-ray Standard (10 – 50 kV).

d.APM-RAD-MNA-1002: Air kerma rate, 137Cs(radiation protection)

Secondary standard ionization chamber type
M23344 (0.2 cm3) traceable to the PhysikalischTechnische Bundesanstalt (PTB), Germany isused to established the CCRI reference beam
qualities at low energy X-rays at Nuclear
Malaysia.

e. APM-RAD-MNA-1003: Air kerma rate, 60Co
(radiation protection)f. APM-RAD-MNA-1004: Air kerma rate, CCRI
X-ray beams, 100kV-250kV(radiation therapy)

Table 1: Characteristics of reference X-ray beams
at Nuclear Malaysia.

g.APM-RAD-MNA-1005: Air kerma rate, CCRI
X-ray beams, 20kV-50kV (radiation therapy)

Constant
potential (kV)

10*

25**

30**

50**

50**

Added filter(mmAl)

0

0.3

0.13

1.0

3.5

h.APM-RAD-MNA-1006:Air kerma rate, 40kV250kV, ISO-4037 narrow spectra series(radiation protection).
i. APM-RAD-MNA-1007:
Ambient
dose
equivalent rate, 60Co (radiation protection)

HVL (mmAl) 1.039 0.243 0.170 1.030 2.283
Air kerma rate
100cm, 10mA
17.1
(mGy/min)viii.APM-RAD-MNA-1008:
Ambient
dose
equivalent rate, 137Cs (radiation protection).
37.3

115.5

50.4

13.2

j. APM-RAD-MNA-1009:
Ambient
dose
equivalent rate, 137Cs (radiation protection)* Inherence filtration : 1 mm Be + 3 mm Al

k.APM-RAD-MNA-1010:
Ambient
dose
equivalent rate, 137Cs (radiation protection)** Inherence filtration : 4 mm Be + 3 mm Al.
7. Quality
System
Accreditation

andLaboratory

l. APM-RAD-MNA-1011:
Personal
137
equivalent rate penetrating, Cs

Nuclear Malaysia currently maintains certificationof Quality Management Systems MS ISO
9001:2000 and the Laboratory Accreditation
Scheme of Malaysia (SAMM), which meet therequirements of MS ISO/IEC 17025:2005.
Compliance Assessment for ISO/IEC 17025:2005
was carried on 13 June 2008 by technicalassessors from Department of Standards Malaysia(DSM). Whereas compliance audit for ISO
9001:2000 was carried out on 12 February 2008
by auditors from SIRIM QAS International Sdn.
Bhd.

dose

m.
APM-RAD-MNA-1012: Personal dose
equivalent rate penetrating, 60Co
n.APM-RAD-MNA-1013: Absorbed dose rate totissue, 90Sr/90Y
xiv.APM-RAD-MNA-1014: Absorbed dose rate
to tissue, 90Sr/90Y
xv. APM-RAD-MNA-1015: Absorbed dose rate
to water, 60Co (radiation therapy)

13

Additional information can be found at:
http://kcdb.bipm.org/appendixC/RI/MY/RI_MY.pdf
9.

International
Radiation
Protection (IRPA) held its
13th Biennial Convention last
October 2-4, 2009 in Puerto
Princesa City, island of
Palawan.. The theme of theConvention-Strengthening
Radiation
Protection
Worldwide - The Philippine
Challenges”
fittingly
underscored the role.

Recalibration of the Secondary Standard
Ionisation Chamber

The soft X-ray ionization type M23344 (0.2 cm3)
was calibrated at the Physikalisch-Technische
Bundesanstalt (PTB), Germany using radiation
qualities according to CCRI (10 kV – 50 kV) andISO 4037 narrow spectrum series radiation
qualities (15 kV, 20 kV, 25kV, 30kV & 40 kV).
10. Future Plan

The Philippine Association for Radiation
Protection (PARP), an associate society of the of
PARP in its commitment to better enhance thepractice of radiation protection and safety in thePhilippines. Young professionals and practitioners
from regulatory bodies, organizations, suppliers
and members of the public gathered together tolearn, share experiences, and discuss radiation
protection issues and challenges in Philippine
setting.

i.
Nuclear Malaysia plan to construct three
more irradiation rooms for X-ray and protectionlevel gamma sources as well as gamma cell forhigh dose dosimetry activities. The additional
irradiation rooms are needed to cater the demandof the calibration service of radiation monitoring
instruments and high dose dosimeters as well as toupgrade the radiation standards in the future.
ii.
A proposal to purchase a new 60Co selfshielded irradiator for high dose dosimetry
applications with activity of 60Co source of about
889TBq @ 24kCi.

Scientific lectures in the areas of nuclear power;
Philippine contributions on strengthening thesafety and security of radioactive sources
worldwide; global threat reduction initiative;
national challenges and situation in dealing withradiation in pediatric health care; optimization ofprotection of patients in radiation therapy; andcargo inspection using x-ray imaging technology.
were given during the Convention by international
experts from the Australian Nuclear Safety
Organization and US Department of Energy as
well as by local experts.

iii.
Malaysian Nuclear Agency / Australian
Nuclear Science & Technology Organisation(ANSTO) high dose dosimetry intercomparison
using
ceric-cerous
dosimeters.
Thisintercomparison will involve dose measurementsof 20 kGy, 25 kGy and 30 kGy of 60Co gamma
beam.

PHILIPPINE ASSOCIATION FORRADIATION PROTECTION (PARP) HOLDS
13 TH BIENNIAL CONVENTION

14The Convention also had the election of the key
officers who will hold office for the next coupleof years. A Fellowship Night and an Educational
Tour added greater experiences to the participants
who traveled from Metro Manila to see thebeautiful and serene, nature sanctuary of theworld in the chosen venue (Palawan).

Assessment
Driving
Radioactive
WasteManagement Solutions), at the 5th Plenary
Meeting on the IAEA International Project on
SADRWMS in Croatia, 23-27 June 2008.
PurposeThe Chatuchak waste processing and waste
storage facilities have been chosen as a test casefor the SAFRAN software within the frameworkof the SADRWMS project. This test case related
activities consisting in:

The PARP is a professional society which draws
membership from users of radiation andradioactive materials in the different peacefulapplications in medicine, industry, research,education and training in the Philippines. The
PARP was organized in 1961 to seek solutions toimprove radiation protection for the benefit of theFilipinos and the environment. Over the years, theAssociation primarily gives trainings andseminars to concerned sectors, with emphasis on
safety and protection against the hazards ofradiation. The PARP collaborates closely with thePhilippine Nuclear Research Institute, theDepartment of Health and other professionalsocieties, and with IRPA, to implement plans andobjectives aimed towards attainment of its goals
and objectives.



Defining the assessment context for the safetyassessment;Description of the site, facilities and of all
relevant activities the safety assessment needs
to address;

Define waste streams and provide data
(inventories,
throughputs,
activity
concentration etc.) required for thequantitative assessments.

Filtration System

Chemical Precipitation System

R
Raaddiiooaaccttiivvee LLiiqquuiidd
W
Waassttee TTrreeaattm
meenntt
FFaacciilliittiieess

Thailand Test Case : Safety Assessment for
Predisposal Radioactive Waste Management
Facilities in Bangkok, Thailand

15

Retention Pool

Background:

SADRWMS Project objective

Thailand proposed to be a Test Case of IAEA
International Project on SADRWMS (Safety

Methodology implemented in software tool;
15





to visibly, systematically and logically address
pre-disposal radioactive waste management
projects in a structured way•

Pretreatment•

Treatment

to establish a traceable and transparent recordof the safety basis for decisions on proposed
waste management solutions.

•

Conditioning•

Storage

Safety Assessment types•

Normal operation and accidents•

Impact on workers and members of the public•

Impact outside and inside the facilities

Storage No.2

Storage

Site Information and Current Situation

Site historyDescription of the existing facilities and theircurrent condition to the extent relevant for theplanned facilities or activities



Disused Seal ed Sou rc es

Reasons for and objectives of the planned
activities or facilities

S
Sttoorraaggee FFaacciilliittiieess
Scenario Development and Assessment of
Impacts

Classes of facilities•

Waste Management facility•

Waste producer•

The specific type of waste management
facilities are defined by the activities going onin the facility

Treated W ast es
In Drum St orage•

System performance (doses and other impacts
to workers and to the public) under normal
conditions•

Potential impacts (all relevant external andinternal hazards) from all relevant events andprocesses

Description of Planned Activities•

Overview of the activities / facilities•

Non-radiological risks•

In case of complex and extended programmes,
definition of individual tasks for which
detailed planning and safety assessments are
performed•

Environmental impacts (radiological and nonradiological)•

Identification of interdepencies between thevarious activities and•Tentative schedule for the various activities

Scenario Development Normal Operations

Types of activities
16•

Addressing all conditions under which
systems and equipment are being operated as
expected•

Basic assumption for this assessment: nointernal or external challenges outside thenormal operation envelopes for all phases ofoperation
Primary Assessment Goal:
Do doses and discharges meet criteria?
Anticipated
Accidents

Operational

Occurrencesand anticipated operational occurrences (expected
at least once in the lifetime of the facility) accidents within the envelope of theconservative accceptance criteria for designbasis accidents

The Management of radioactive waste in
Vietnam accidents exceeding these criteria but notcausing severe damage and releases

Vietnam has been intensively preparing for the
first project of nuclear power plant, which isplanned to be in commercial operation by 2020.
Following the introduction of the IAEA and theworld general trend in production of electricity,
the VAEI and Vietnam Agency for Radiation and
Nuclear Safety (VARANS) have co-coordinatedto realize matters concerning the radioactive
waste management such as estimation of theactuality of radioactive waste, building up a
nuclear law, infrastructure preparation, staff
training, studies on radioactive waste treatment
and storage.

 accidents with severe damage and releases(severe accidents)
Assessment Context•

Basic radiation protection principles:-

Justification-dose limitation-

optimization•

National regulatory criteria•

Internationallyconventions•

Further criteria (e.g. non-radiological impacts,
conventional safety)

accepted

standards

The actual situation of radioactive waste and the
management of them in Vietnam

and

In Vietnam, though the activities relating to theuse of radioactive materials is still limited, there
has been a remarkable amount of radioactive
wastes to be stored. Based on the present meansof estimation and classification, most ofradioactive wastes in Vietnam are in low andmedium levels.

Use of Safety Assessment Results Design

Identifying required and most cost effective
improvements or upgrading in waste
management facilities



Building confidence that the designed system
is robust and will meet safety requirementsDemonstrating the quality and reliability of
the analysis used to evaluate performance ofthe pre-disposal system.

Radioactive wastes from Dalat Institute for
Nuclear Research (DINR)
Dalat Institute for Nuclear Research is one of afew establishments that produce radioactive
materials in Vietnam. These radioactive materials,
which are produced from the research reactor andfrom isotope preparation laboratories, are in liquidand solid states. The liquid wastes which have a
total amount of about 5 – 15 m3 per month, almost
contains 131I, 51Cr, 60Co, 139Ce, 134Cs, 54Mn withtotal radioactivity of 3.7-37 KBq/L. They arecollected into reservoirs and treated by ion
17exchange method, then concreted on an equipped
technology line (imported from Russia). The solid
wastes produced from activities of Dalat nuclear
reactor have been stored in the provisional storage
at the DINR. In 1997, IAEA supported the DINR
to strengthen infrastructure for the radioactive
waste management with an equipment system ofradioactivity measurement, radioactive waste
classification, a press can reduce the volume ofcompressed material from 3 to 10 times, and astorage of 750 m3 capacity comprising 8
underground concrete trenches that have acapacity of 94m3 each, a depth of 4 meters andwalls of 40 cm thick.

management and treatment of these wastes wererather simple. They were stored and isolated for acertain period of time to lower their radioactivity
to acceptable limits. After that they were treatedas other normal/non-radioactive medical wastes.
The radioactive objects that were most concerned
were the sealed sources used for malignant
growths and tumors that have initial radioactivityof 8000-12000 Ci. These sources were mainly
60
Co, 137Cs. There were also small sealed sources
used for contact therapy such as Ra and Co
needles. In principle, such sources like the usedradium do not produce other radioactive materials
during operation, but they became radioactive
sources/wastes themselves when being disposed.
They were very dangerous due to their highradioactivity. These sources and some otherexpired sealed sources were stabilized and stored
at Dalat Nuclear Research Institute thanks to thehelp of IAEA.

Radioactive wastes from the ITRRE
The ITRRE has been functioned to study thetechnology for processing radioactive and rareelements. The following main activities conductedby the ITRRE have produced a lot of radioactive
wastes:-Studying on processing uranium ores inlaboratory scale and semi-pilot scale toestablish the capability of preparation of
uranium from different domestic ores/sources.

-

Processing monazite to obtain rare earth
elements released large an amount of the highradioactivity wastes containing thorium andradium.

Radioactive wastes from industry and research
activities

These wastes were all treated, conditioned andsealed in 645 steel barrels having capacity of 200
liters each, which were stored in the precariously
storage at Phung establishment in Hanoi.
Radioactive wastes from activities of exploitationand processing of ores/minerals (Naturally
Occurring Radioactive Materials, NORM)
The industries that have produced NORM
comprise exploitation and processing of coastal
mineral sand, and fossil coal; oil and gas
exploitation.
Radioactive wastes from public healthFig 1. On-site storage at DNRR

The use of radioactive materials for diagnosis andtherapy in nuclear medicine has produced aconsiderable amount of radioactive wastes. Theseradioactive materials were mainly short term
isotopes such as 131I, 99mTc, 32P, etc. The

Recently, the sealed radioactive sources havebeen imported to Vietnam to use in several of
non-radioactive industrial branches such as
cement, paper, brewing, glass, geology, explore,18

etc. The number of these radioactive sources has
not been exactly reckoned up so far.

pecuniary penalty in the domain of radiation
safety and control;

In the judgment of Vietnam Agency for Radiation
and Nuclear Safety, most of radioactive sources inVietnam were ranked as low radioactivity, and theradioactive sources used in health care andindustries were almost short or medium lived.
However, among them there were Co and Ra
sources that had high radio-activities andrelatively long half life. Most of these radioactive
sources (801 units) were kept at the storages ofusers, where security conditions were not good
and the risk of the source- loss have been always
an implicit threat, while there were 122 units thatwere kept at the specialized storage of theInstitute for Global Physics at Luong Son, Hoa
Binh.

7. The law of atomic energy 18/2008/QH12
promulgated on June 6th, 2008.

The legal documents concerning the radiation
safety and the radioactive waste management in
VietnamHowever, there have been neither overall legal
regulations nor a government’s synchronous
system for controlling radioactive wastes. There
have not been R&D establishments of radioactive
waste to play a role of technique consultants inthis field.

* Some rules relating to radiation safety andradioactive waste management have beenpromulgated. They are Ionize radiation safety forusing X-ray in public health-care (TCVN 6561,
1999); Dose limits for the public and staffs
working in radiation exposure (TCVN 6866,2001); Safety for transportation of radioactive
wastes (TCVN 6867-1, 2001); Radioactive
management (TCVN 6868, 2001); Generalregulations for irradiation in health-care;
Regulation for exception, declaration, registrationand license in the field of radiation safety (TCVN
6870, 2001).

* Lately, Vietnam has made efforts in the field ofradiation
safety andradioactive
waste
management. That was showed in the series oflegal documents built up and promulgated asfollows:---------------

1. The Ordinance on Radiation Safety andControl, 1996;
2. The decree 50/1998/NĐ dated on July 16th,
1998 by the Government determined in detailthe implement of The Ordinance on Radiation
Safety and Control;
3. The resolution 155/1999/QĐ-TT signed on
April 16th, 1999 by the Prime Minister on the
promulgation of regulations of deleterious
wastes;4. The resolution 2575/1999/QĐ-BYT signed on
August 27th, 1999 by the Minister of Health;
5. Thejoint
circular
2237/1999/TTLT/BKHCNMT-BYT signed on
December 28th, 1999 by the Ministry of
Science, Technology and Environment and theMinistry of Health, instruction for implementof radiation safety in health care;
6. The decree 19/2001/N§-CP promulgated on
May 11 th, 2001 by the Government on
19

Invitation to AOCRP-3
The Third Asian and Oceanic Congress on Radiation Protection (AOCRP-3) is a congress forradiation protection held every four years under Asian and Oceanic Association for Radiation
Protection (AOARP). The AOARP is a regional association of International Radiation Protection
Association (IRPA).
http://www.aocrp-3.org/home.html[Date] May 24-28, 2010 [Place] Tower Hall Funabori, Tokyo, JAPAN[Highlight]
AOARP & FNCA-RS&RWM Joint Session May 24, 13:40-15:30"Present Activities of Radiation Protection Societies in Asian and Oceanic countries"
13:40-13:45 Purpose of this session
13:45-14:50 Reports from participant countries
14:50-15:30 Panel discussion
Refresher Courses May 24-27, 9:30-10:20
RC-1: Radiation protection system -history of dose constraints and limitsRF-2: New radiological data from UNSCEAR
RF-3: Definition of various radiological units and its futureRF-4: Radiological protection in medical fields
RF-5: Radiological protection for non-human species
RF-6: Concept of radioactive waste management
RF-7: Radiation safety (management and monitoring) around NPP
RF-8: Control of radon, space radiation, aircraft exposure, and NORM
RF-9: Radiation education to public and stakeholder involvements into decision making
Luncheon Seminars 12:10 13:30
LS-1: NORM/TENORM management and its discussion points
LS-2: Newest knowledge on radiological biological effects
LS-3: RWM and clearance system adopted in real sites
LS-4: Nuclear safety culture and human development in Radiation Protection field
LS-5: Development of PHITS and its applicationLS-6: IAEA and OECD/NEA activity and their future scopes
Oral Presentation Sessions
OP-1 Radon
OP-2 Emergency Preparedness and Response
OP-3 Radiation measurement OP-4 Radiation control and management
OP-5 Radioactive waste management
OP-6 NORM/TENORM
OP-7 Dosimetry
OP-8 Standard, criteria and regulation
OP-9 Exposure to medical radiation OP-10 Health effects of ionizing radiation
OP-11 Environmental radioactivity
OP-12 Radiological protection as part of the global nuclear expansion
IAEA Special session WHO Special session IRPA Special session ICRP Special Session
International Panel Discussion and Poster session
20