1. Safety of Research Reactor In Indonesia
Presented By
Ai Melani, S.Si

2. Content Introduction Code of Conduct on Safety of Research Reactor
Research Reactor In Indonesia
Utilization of Research Reactors
Utilizations of Research Reactor in Indonesia
Safety Assessments of Research Reactor In Indonesia
Conclusions

3. Nuclear Installations and Materials Nuclear Installations
Introduction
Nuclear
Power
Plants !?
Nuclear Installations and Materials
Nuclear Materials
At Reactor and Non Reactor
TENORM
Tin-Slag from Tin Mines
Nuclear Research Reactors
(BATAN)
RSG-GAS (30 MW)
TRIGA-2000 (2 MW)
KARTINI (100 kW)
Nuclear Installations
BATAN
Nuclear Installations non Reactor
Non-BATAN
RR Fuel Element Prod. Inst.
Yellow Cake Prod. Inst.

4. Code of Conduct on Safety of Research Reactor
Code adopted by the IAEA General Conference on 24 September 2004
Code establishes "best practice" guidelines for the licensing, construction and operation of research reactors.
The author use the requirement in “code of conduct on the safety of research reactor” to review the safety of research reactor in Indonesia

5. Research Reactor In Indonesia
TRIGA 2000 Reactor
Location: Bandung, West Java
Type: TRIGA reactor
Thermal power: 2000 kW
First critical at 1964 (250 kW)‏
Upgraded to 1000 kW on 1971
Upgraded to 2000 kW on 2000
License: valid up to 2016
Fuel Element: 107
Coolant : Light Water
Enrichment Max : 20%
Moderator: H2O and ZrH
Spent fuel storage cap:192 element

6. Research Reactor In Indonesia
Kartini Reactor
Location: Yogyakarta (Central Java)‏
Type: TRIGA reactor
Thermal power: 100 kW
Some components/structures were provided from first upgrading of Bandung reactor (1971)‏
First critical at 1979
License: valid up to 2010
Fuel Element: 69
Coolant : Light Water
Enrichment Max : 20%
Moderator: H2O and ZrH
Spent fuel storage cap:90 element

7. Research Reactor In Indonesia
G.A. Siwabessy MPR
(RSG-GAS)‏
Location: Serpong, Banten (West Java)‏
Type: Multi Purpose Reactor
Thermal power: 30 MW
Fuel: U3Si2Al
First critical at 1987
License: valid up to 2020
Number of Fuel : 48 element
Enrichment Max : 20%
Spent fuel storage cap:300 on site /1490 off site

8. Utilization of Research Reactor
Irradiation test on fuel and materials
Activation Analysis
Production of silicon semiconductor
Utilization of Research Reactors
Neutron beam Experiments:
Neutron radiography
Neutron Scattering Experiments
Production of isotopes
Other fields:
Education and training of reactor engineering
Reactor Engineering Studies
Shielding Experiments

9. Utilization of Research Reactor In Indonesia
GA Siwabessy MPR Serpong:
Isotope production, neutron beam experiments, activation analysis, education and training, reactor engineering studies, etc
Kartini Reactor Yogyakarta:
TRIGA 2000 Reactor Bandung:
Isotope production, activation analysis, education and training, reactor engineering studies, etc
Isotope production, neutron beam experiments, activation analysis, education and training, reactor engineering studies, etc

10. Safety Assessment of Research Reactors (1)
1.ORGANIZATION AND MANAGEMENT
a. Safety management system Clarifications of Responsibilities BATAN rules: Chairman, Head of Centre, Head of Reactor Division.
b. Safety objectives of organizationsBATAN Top Level Policy sets out over-riding commitment to safety and a strong safety culture.
c. Fostering Safety Culture Each Facility has activity to fostering safety culture of organization and personnel.
d. Quality Assurance System Each Facility since beginning is subject to audit of QA yearly  At BATAN Level: PSJMN, National: BAPETEN.
e. Safety Case Safety analysis Report of each facilities was prepared since early of construction. It was revised continuously needed (Modification and new safety experiment)BAPETEN conduct review and assessment as basis stipulated license.

11. Safety Assessment of Research Reactors (2)
2. EMERGENCY PREPARADNESS
Each Facility established Emergency Preparedness TeamResponsible handling emergency condition: ensure on site and offsite conditions, and coordinating with external parties.
EP Team conduct exercise yearly.
3. EDUCATION AND TRAINING
BATAN has education and training centre for all the BATAN employees.
All operators are certified by BAPETEN after pass the training course and examination. Certified is for 3 years.

12. Safety Assessment of Research Reactors (3)
4. OPERATION AND MAITENANCE
Normal shift for research reactor conduct by six staffs each include supervisor and operator reactor from reactor operation division.
The Procedures for Information's transfer at shift handover at the recording and logs book in control room.
The OL&Cs are part of the QA system.
The maintenance scheduling system is used to manage the scheduling of maintenance.

13. Safety Assessment of Research Reactors (4)
5.RADIATION PROTECTION
a. Management of Radiation Exposure
System and organization for radiation and protection set out based on the IAEA BSS and includes directives on: Radiation Protection Principles: Policy on As Low As Reasonably Achievable.
The policy requires assessment of all staff having doses >2 mSv/y and documented assessment are required.
 A monthly limit of 1 mSv is used for monitoring and an annual constraint of 15 mSv is used. No worker exceeded 10 mSv/y.
b. Radiation Monitoring
All radiation workers wear TLDs and some electronic dosimeters.
Staff working with unsealed sources wears wrist and finger TLDs as well.
All identified radiological areas have are monitors and a barrier control process exist for these classified areas.

14. Safety Assessment of Research Reactors (5)
5.RADIATION PROTECTION
c. Treatment and Reduction of Radioactive Waste
Each centre has Quality management system procedures and instructions address waste minimization at the workplace level.
ensure that non-radioactive waste is not mixed with radioactive waste and waste clearance systems to segregate and clear waste.
Radioactive wastes are segregated and classified as Low Level or Intermediate Level and high Level by the organization operation (PRSG, PTRKN, PTAPB).

15. Safety Assessment of Research Reactors (6)
6.MEASURES FOR IMPORTANT SAFETY ISSUES
a. Critically Safety and Related Issues
To prevent critically in waste storage, fuel storage is maintained through conservative design and assumptions, engineering safety provisions, and administrative controls.
In shutdown and maintenance modes, there is sufficient shutdown margin even allowing for a worst case set of errors in reactivity accounting allowing one control arm to be safely withdrawn in maintenance or shutdown.
To ensure decay heat removal and tolerant to expected initiators like loss of off-site power, loss of services, In shutdown mode, pumps primary circuit still running for a few minute.

16. Safety Assessment of Research Reactors (7)
6.MEASURES FOR IMPORTANT SAFETY ISSUES
b. Operating Experience Feedback
Safety enhancement based on operating experience feedback, systems have been implemented to analyze abnormal events, identify the causes and determine countermeasures.
There is an established system of experience feedback, based on the Abnormal Occurrence Report (AOR) and follow-up after-action assignment (FAA) systems.
c. Aging Management
Each research reactor facility has been established aging management team, and the main task on this aging management team is to study on aging factors and conduct inspection related with ageing of SSC.

17. Safety Assessment of Research Reactors (8)
6.MEASURES FOR IMPORTANT SAFETY ISSUES
d. Safety of All activities and operations including experiments
The systems been established to review and approve the safety of all activities and operations including experiments.
Operations and Experiments are Controlees by the reactor operation division and approved by the internal safety division and then the regulator.
A safety analysis is also needed of these experiments. The documentation is developing under a QA system.

18. Safety Assessment of Research Reactors (9)
7.REGULATION AND LICENSING
a. Independence
Act No. 10/1997 on Nuclear Energy:
1. BAPETEN : Regulatory Body
(Regulation, Licensing and Inspection)
2. BATAN : Promotion Body or Operating Organization

19. Safety Assessment of Research Reactors (10)
7.REGULATION AND LICENSING B A P E T N
SOCIETY
REGULATION
Safety
Healt
Peacefull
ACT
No. 10/1997
LICENSING
ENVIRONMENT
INSPECTION
assure the welfare, the security and the peace of people;
assure the safety and the health of workers and public, and the environmental protection;
maintain the legal order in implementing the use of nuclear energy;
increase the legal awareness of nuclear energy user to develop a safety culture in nuclear field;
prevent the diversion of the purpose of the nuclear material utilisation; and
assure for maintaining and increasing the worker discipline on the implementation of nuclear energy utilisation.
Function

20. Safety Assessment of Research Reactors (11)
7.REGULATION AND LICENSING
Nuclear Energy Act 10 Year 1997
LAW
Basic principles in safety arrangement for the development and beneficial use of nuclear energy.
Government Regulation “Nuclear Reactors Licensing” No. 43 Year 2006
Government
regulations
Regulation based on Law
Presidential
Decree
Regulation based on Law
Regulations of
Chairman of Bapeten
Decree Of the Bapeten Chairman “Safety Provision On Research Reactors Operation” No. 10/99.
Decree Of The Bapeten Chairman “safety provision on research reactor design” (No. 05/99)
Etc…

21. Safety Assessment of Research Reactors (12)
7.REGULATION AND LICENSING
b. Regulatory Process
Safety objective put on strategic planning and enunciated by chairman of BAPETEN at Nuclear Safety Policy Statement and at the Regulation.
Licensing Process
Perform regular and incidental inspection
Enforcement

22. Conclusions
The status on the safety of research reactor in Indonesia especially coming from the criteria put on IAEA code of conduct the safety research reactor, and each research reactor has been performed safety assessment refer to code of conduct.
Up to now the research reactor in Indonesia are in the safety condition.

23. THANK YOU

24. Reference
IAEA Code of Conduct on The safety of Research Reactor, IAEA No. GC48-7, IAEA, Vienna, 1999.
Act No. 10/1997 on Nuclear Energy, BAPETEN, Indonesia, 1997.
Safety Analysis Report of Kartini Research Reactor, PTAPB-BATAN, Yogyakarta, Indonesia, 2007.
Safety Analysis Report of Triga Mark II Research Reactor, PTNBR-BATAN, Bandung, Indonesia, 2006.
Safety Analysis Report of MPR-30 Research Reactor, PRSG-BATAN, Serpong, Indonesia, 2006.
Self Assessment Report of Kartini Research Reactor, PTAPB-BATAN, Yogyakarta, Indonesia, 2006.
Self Assessment Report of Triga Mark II Research Reactor, PTNBR-BATAN, Bandung, Indonesia, 2006.
Self Assessment Report of MPR-30 Research Reactor, PRSG-BATAN, Serpong, Indonesia, 2006.

25. Reference
Government Regulation No. 63/2000 on the provision of safety and health for use of ionizing radiation, BAPETEN, Indonesia, 2000.
Government Regulation No. 26/2002 on the safe transport of radioactive material, BAPETEN, Indonesia, 2002.
Government Regulation No. 43/2006 on the Licensing of Nuclear Reactor, BAPETEN, Indonesia, 2006.
Decree of BAPETEN Chairman No. 01/1999 on the occupational safety provision against radiation, BAPETEN, Indonesia, 1999.
Decree of BAPETEN Chairman No. 02/1999 on the limitation of environmental radioactivity level, BAPETEN, Indonesia, 1999.
Decree of BAPETEN Chairman No. 10/1999 on the safety requirements for operation of nuclear reactor, BAPETEN, Indonesia, 1999.
Decree of BAPETEN Chairman No. 05/1999 on the safety requirements for design of nuclear reactor, BAPETEN, Indonesia, 1999.