research reactor

Implementation Report

Basic Professional Training Course in Nuclear Safety

Level II: Research Reactor

Jakarta, 18 ~ 29 July 2005

NATIONAL NUCLEAR ENERGY AGENCY

NUCLEAR ENERGY CONTROL BOARD

2005

Basic Professional Training Course on Nuclear Safety Level II: Research Reactor

Place Education and Training Center – BATAN, Pasar

Jumat, Jakarta. Date 18 ~ 29 July 2005 Organizer Education and Training Center – BATAN and

Planning Bureau - BAPETEN Language Instruction will be in Indonesian Participant The training course is open up to 20 participants

from BATAN and BAPETEN but attended only 19 participants, 15 persons from BATAN and 4 persons from BAPETEN. The list of participants can be found in attachments.

Qualification The participants should have attended The Basic

Professional Training Course on Nuclear Safety Level I, which had been conducted twice in year 2003 and 2004

Background Safety is fundamental aspect especially on nuclear field. BATAN and BAPETEN want to ensure and establish the safety aspect and safety culture on implementing nuclear energy in Indonesia.

Purpose To enhance knowledge of participants on nuclear safety, particularly in research reactor. The training course will help participants to develop necessary skills and techniques in executing their tasks and in applying nuclear safety standards in research reactor facility and its supporting facilities.

Training Objective

After taking the course the participants should be able to describe the following

q The task and responsibilities of regulatory body and operating organization regarding to safety aspect of research reactor;

q The principles of safety culture, in which each safety-related issue always receives the priority commensurate with its importance for all actions by, and at all level;

q The personal computer program for desk-top exercise on accident analysis.

Nature of the course

Based on the four quadrants competency that introduce by IAEA in order to perform the training needs analysis, the curriculum of this training course is categorized into three domains, i.e. Basic Competency, Specific Competency of Research Reactor, and Regulation and Administration Competency. Basic Competency

1. Neutronics Aspect (3 sessions) 2. Thermal-hydraulics of Research Reactors (4 sessions) 3. Occupational Radiation Protection in RR (3 sessions) 4. Research Reactor Design (4 sessions) 5. Core Management (3 sessions)

Specific Competency

6. Safety Requirements for Research Reactors (3 sessions) 7. Safety Assessment of Research Reactor and Preparation of the

Safety Analysis Report (3 sessions) 8. Accident Analysis of Research Reactors (3 sessions) 9. Exercises on Computer Codes for Accident Analysis – (6

sessions for each topics) 10. Safety in Relation to External Events (3 sessions) 11. Safety in Utilization and Modification of Research Reactor (3

sessions) 12. Operational Limits and Conditions (2 sessions) 13. Maintenance, Periodic Testing and Inspection (3 sessions) 14. The Code of Conduct on the Safety of Research Reactors (4

sessions)

15. Management of Research Reactor Ageing and Some aspects of ISI (4 sessions)

16. Source Term in Research Reactor (ORIGEN Code) (5 sessions) 17. Radioactive Materials Releases to Environment (3 sessions) 18. Waste Management in Research Reactor (2 sessions) 19. Decommissioning of Research Reactor (2 sessions) 20. Emergency Preparedness for Research Reactor (3 sessions)

Regulation and Administration Competency

21. Operating Organization and Recruitment, Training and Qualification (2 sessions)

22. Management Systems, included. Quality Assurance (3 sessions)

23. Regulatory Structure, Review and Assessment of Research Reactor (4 sessions)

The total allocated time for lectures and exercises is 81 sessions (1 sessions equal to 45 minutes). The detail curriculum, syllabus, and training schedule can be found in attachments. Lecturers

20 senior staffs were actively involved during the preparation and gave lecture in that training course, 14 lecturers from BATAN, 5 lecturers from BAPETEN, and one lecturer from Bandung Institute of Technology (ITB). Beside that, IAEA expert Dr. W.L. Deitrich had given assistance and consultation on composing the training curriculum and syllabus of this training course. Training Material

The training materials that consist of handouts and presentations as well as translation of some relevant IAEA documents were distributed to the participants during the course, and the soft-files in CD were distributed in the last day.

Six IAEA documents were translated during the preparation of this training course as follows.

• DS-272 Safety Requirements on Safety of Research Reactor

• GC48-7 Code of Conduct on Safety of Research Reactor • Tecdoc-792 Management of Research Reactor Ageing

• SRS-41 Safety of New and Existing of RR in Relation with External Events

• GS-G-1.2 Review and Assessment of Nuclear Facility by Regulatory Body

• RS-G-1.1 Occupational Radiation Protection

The training material: handouts, presentations, and translated IAEA documents will also be available in Indonesian ANSN web site. Course Evaluation:

1. The course was officially opened by the Director of Education and

Training Center of BATAN and the Director of Planning Bureau of BAPETEN.

2. On the final day, participants were given time to evaluate the training by themselves. It was concluded that some follow-up trainings expected where participants can learn further detail on certain specific field:

• BPTC in Nuclear Safety Level II in other nuclear facilities such as nuclear fuel fabrication and nuclear waste management.

• Special training course on utilization of personal computer program for accident analysis (PARET, RELAP, ORIGEN).

• Topics on “safety culture” and “human performance” should be more elaborated. Actually these topics belong to the fourth quadrant of training needs assessment.

3. Based on the pre-test and post-test results, all participants gain their knowledge on the topics which be given in this training course. In average, the improvement is 20%.

4. Finally, Mr. Karsono, Director of Education and Training Center of BATAN, gave closing remark and officially closed the course, on Friday, 29 July 2005.

Acknowledgement

The organizing committee acknowledges BATAN and BAPETEN for the cooperation to conduct the training course and contribute senior expert as lecturers. Gratefully acknowledges to the IAEA for giving assistance and providing expert for this Training Course.

Attachment 1 List of Participants

NO Name Organization

1 Maman Kartaman ACenter for Development of Nuclear

Fuel Technology

2 Nur Tri Harjanto Center for Development of Nuclear Fuel Technology

3 Nur Rahmah HidayatiCenter for Development of Nuclear

Safety Technology

4 Yoyok Dwi Setyo PambudiCenter for Development of Nuclear

Safety Technology

5 Nurul Huda Center for Development of Nuclear Safety Technology

6 Tulis Jojok SuryonoCenter for Development of Nuclear

Safety Technology

7 Arief Tris Yulianto Center for Development of Nuclear Energy

8 Nafi FeridianCenter for Development of Nuclear

Energy

9 Aep Saepudin Catur Center for Development of Research Reactor Technology

10 CahyanaCenter for Development of

Research Reactor Technology

11 Hari PrijantoCenter for Development of

Research Reactor Technology

12 Abdul Rohim IsoCenter for Research and

Development of Nuclear Techniques

13 Teguh SubektiCenter for Research and

Development of Nuclear Techniques

14 Gatot SumartonoWaste Management Facility,

Serpong

15 Chevy CahyanaWaste Management Facility,

Serpong

16 Hesty Rimadianny BAPETEN

17 Achmad Bussamah BAPETEN

18 Akhmad Khusyairi BAPETEN

19 Bambang Eko Aryadi BAPETEN

Attachment 2 Training Curriculum

No. Subject Sessions Lecturer

Basic Competency

1 Neutronics (criticality, reactivity, kinetics, etc.) 3 Ir. Tagor Malem Sembiring (P2TRR)

2 Thermal-hydraulics of Research Reactors 4 Ir. Dewanto Saptoadi, M.Eng (P2TRR)

3 Occupational Radiation Protection in RR 3 Dr. Yus Rusdian Ahmad (BAPETEN)

4 Research Reactor Design (TRIGA Mark II) 2 Ir. R. Henky Poedjo Raharjo, M.Sc. (P3TkN)

5 Research Reactor Design (Multi-purpose Reactor)

2 Drs. Alim Tarigan (P2TRR)

6 Core Management 3 Mochammad Imron, S.Si. (P2TRR)

Specific Competency

7 Safety Requirements for Research Reactors 3 Ir. Yanuar Wahyu Wibowo, M.Sc(BAPETEN)

8 Safety Assessment of RRs and Preparation of the SAR

3 Dr. M. Dhandhang Purwadhi, MT. (P2TRR)

9 Accident Analysis of Research Reactors (Deterministic and Probabilistic)

3 Dr. Ir. A. Riza Antariksawan (P2TKN)

10 Computer Codes for Accident Analysis Relap - Exercises

6 Dr. Ir. A. Riza Antariksawan (P2TKN)

11 Computer Codes for Accident Analysis - Exercises

6 Ir. Endiah Puji Hastuti, MT. (P2TRR)

12 Safety in Relation to External Events 3 Dr. Sindur Mangkusubroto (ITB)

13 Safety in Utilization and Modification of RRs 3 Ir. R. Henky Poedjo Raharjo, M.Sc. (P3TkN)

14 Operational Limits and Conditions 2 Drs. Alim Tarigan (P2TRR)15 Maintenance, Periodic Testing and Inspection 3 Drs. Setyono Soeryat

(P2TRR)16 The Code of Conduct on the Safety of

Research Reactors4 Sudiyono, ST. (P2TRR)

17 Management of RR Aging (incl. NDT and ISI) 4 Dr. M. Dhandhang Purwadhi, MT. (P2TRR)

18 Source Term & Origen 5 Pudjianto (P2TRR)19 Radiation Releases to Environment 3 Ir. Pande Made Udiyani,

M.Si. (P2TRR)20 Waste Management in RR 2 Dr. Ir. Djarot Sulistyo W.

(P2PLR)21 Decommissioning of Research Reactor 2 Dr. Ir. Djarot Sulistyo W.

(P2PLR)22 Emergency Preparedness for Research

Reactor3 Ir. Dedik Eko Sumargo

(BAPETEN)

Regulation and Administration Competency

23 Operating Organization and Recruitment, Training and Qualification

2 Drs. Naek Nababan (P2TRR)

24 Management Systems, incl. Quality Assurance

3 Drs. Reno Alamsyah, M.Sc. (BAPETEN)

25 Regulatory Structure, Review and Assessment of Nuclear Facilities

4 Dr. Khoirul Huda (BAPETEN)

Total 81

Attachment 3 Training Syllabus Basic Competency 1. Neutronics Aspect (3 sessions)

Objectives: provide the understanding on basic neutronics aspect in research reactor related to the reactor safety and core management.

Contents: neutron cycles in the core, multiplication coefficient, reactivity coefficient, burn factor, kinetics, and safety criteria in neutronic aspect.

2. Thermal-hydraulics of Research Reactors (4 sessions)

Objectives: provide the understanding on basic thermo-hydraulics in research reactor related to the design and operation of reactor.

Contents: heat transfer process, one phase convection and its correlation to any configuration of research reactor fuel element (cylinder, plat), boiling, DNBR, and flow instability.

3. Occupational Radiation Protection in RR (3 sessions)

Objectives: provide the understanding on radiation protection principles and its application in research reactor facility.

Contents: radiation protection principles, limit of occupational exposure, radiation protection organization in research reactor facility, radiation protection program.

4. Research Reactor Design (4 sessions)

Objectives: provide the understanding on research reactor technology, “multi purpose reactor” and “TRIGA reactor”.

Contents: general description on reactor system (core, cooling system, I and C, etc), features and safety characteristics.

5. Core Management (3 sessions)

Objectives: provide the understanding on core management in order to ensure the safety operation of research reactor.

Specific Competency 6. Safety Requirements for Research Reactors (3 sessions)

Objectives: provide the understanding on the safety requirements for each activity in research reactor, particularly requirements on design and operation of research reactor

Contents: objectives, concept and principles of safety, regulation, site evaluation, management and safety verification, design, operation, and decommissioning of research reactor.

7. Safety Assessment of Research Reactor and Preparation of the Safety Analysis Report (3 sessions)

Objectives: provide the understanding on preparation and contents of the Safety Analysis Report.

Contents: requirements for safety assessment regarding to the licensing process of research reactor, description of Safety Analysis Report.

8. Accident Analysis of Research Reactors (3 sessions)

Objectives: provide the understanding on accident analysis methods, deterministic and probabilistic.

Contents: objective of accident analysis, scope and procedures of assessment, methods of accident analysis.

9. Exercises on Computer Codes for Accident Analysis – (6 sessions for

each topics)

Objectives: introduction to some computer program for safety analysis of research reactor.

Contents: PARET code and RELAP5 code.

10. Safety in Relation to External Events (3 sessions)

Objectives: provide the understanding on safety of research reactor regarding to the external events.

Contents: safety concept on location and design, type of external events, design qualification for external hazards.

11. Safety in Utilization and Modification of Research Reactor (3 sessions)

Objectives: provide the understanding on practical guidance related to the safety during utilization and modification of research reactor.

Contents: organization and responsibilities in modification activities as well as safety in experimental activities.

12. Operational Limits and Conditions (2 sessions)

Objectives: provide the understanding on operational limits and condition of research reactor in order to ensure the safety of research reactor operation.

Contents: normal operation parameter, safety system setting, safety limits and design, determination of operational limits and condition, and its considering factor.

13. Maintenance, Periodic Testing and Inspection (3 sessions)

Objectives: provide the understanding on the safety guidance for maintenance and periodic testing, procedures of maintenance and periodic testing, inspection.

Contents: maintenance and periodic testing program, organization and responsibilities of maintenance and periodic testing, procedures of maintenance and periodic testing.

14. The Code of Conduct on the Safety of Research Reactors (4 sessions)

Objectives: provide the understanding on safety principles, code and conduct to be applied in research reactor management.

Contents: safety principles, government role, regulatory body role, operating organization role, and general recommendations.

15. Management of Research Reactor Ageing and Some aspects of ISI (4

sessions)

Objectives: provide the understanding on ageing management of components, system, and structure of research reactor, and inspection methods using non-destructive test.

Contents: definition of ageing management related to the safety of research reactor, detection and evaluation of ageing effect, mitigation of ageing effect, application of non destructive test methods on in-service inspection.

16. Source Term in Research Reactor (ORIGEN Code) (5 sessions)

Objectives: provide the introduction to generation of fission product in fuel element during operation of research reactor.

17. Radioactive Materials Releases to Environment (3 sessions)

Objectives: provide the understanding on process and estimation of radioactive release to environment in any conditions.

18. Waste Management in Research Reactor (2 sessions)

Objectives: provide the understanding on management of radioactive waste of research reactor, from core to storage.

19. Decommissioning of Research Reactor (2 sessions)

Objectives: provide the understanding on techniques and procedures of decommissioning related to the safety aspect.

Contents: Responsibilities, phases of decommissioning, planning and management of decommissioning, decontamination and dismantling of research reactor (multi purpose reactor and TRIGA).

20. Emergency Preparedness for Research Reactor (3 sessions)

Objectives: provide the understanding on emergency planning and its application in research reactor.

Regulation and Administration Competency 21. Operating Organization and Recruitment, Training and Qualification (2

sessions)

Objectives: provide the understanding on operating organization structure, recruitment, training, and qualification personnel of research reactor.

22. Management Systems, included. Quality Assurance (3 sessions)

Objective: provide the understanding on basic management system applied to research reactor and the difference between documentation system based on SS 50-C/SG-Q, ISO 9000 and DS338.

Contents: basic of QC and QA; quality assurance program (SS 50-C/SG-Q); ISO-9000:2000; management system (DS338): responsibility of management, human resources, measuring, assessment, and improvement.

23. Regulatory Structure, Review and Assessment of Research Reactor (4

sessions)

Objectives: provide the understanding on regulatory infrastructure, review and assessment process related to the safety of research reactor.

Contents: licensing, regulation, and inspection from regulatory body, objective and process of review and safety assessment of Research Reactor.

Attachment 4 Training Schedule

Week IMonday Tuesday Wednesday Thursday Friday

18-Jul-05 19-Jul-05 20-Jul-05 21-Jul-05 22-Jul-05

08.00 ~ 08.45Opening Ceremony

Pre TestSafety Requirements

(Yanuar W.)Operating Organization

(Naek Nababan)RR Design:Triga

(Henky P.R.)

Reg. Struct, Review & Assessment of RR

(Khoirul H.)

08.45 ~ 09.30Introduction to the course

(Hendriyanto)idem idem idem idem

09.45 ~ 10.30 Neutronic (Tagor M. S.)

idem Code of Conduct(Sudiyono)

RR Design:MPR(Alim T.)

idem

10.30 ~ 11.15 idemManagement System

(Reno A.)idem idem idem

11.15 ~ 12.00 idem idem idemOLC

(Alim T.)

12.45 ~ 13.30Thermal-hydraulics

(Dewanto S.)idem idem idem

13.30 ~ 14.15 idem Core Management(M. Imron)

Safety Ass. Prep. SAR(M. Dhandhang)

External Events(Sindur Mangkoesoebroto)

Accident Analysis(Antariksawan)

14.30 ~ 15.15 idem idem idem idem idem


Coffee Break

Lunch Break

Coffee Break

Time

Week IIMonday Tuesday Wednesday Thursday Friday25-Jul-05 26-Jul-05 27-Jul-05 28-Jul-05 29-Jul-05

08.00 ~ 08.45Occupational Radiation

Protection(Yus R. Ahmad)

Ageing Managements(M. Dhandhang)

Utilization & Modification of RR

(Henky P.R.)

Rad. Releases to Env.(Made P.)

Waste Management(Djarot W.)


09.45 ~ 10.30 idem idem idem idemDecomissioning

(Djarot W.)

10.30 ~ 11.15Maintenance & Periodic

Testing(Setyono)

idem RELAP & Exercise(Antariksawan)

PARET & Exercise(Endiah)

idem

11.15 ~ 12.00 idemSource Term & ORIGEN

(Pudjianto)idem idem

12.45 ~ 13.30 idem idem idem idem

13.30 ~ 14.15 Emergency Preparedness(Dedik Eko Sumargo)

idem idem idem Final Discussion

14.30 ~ 15.15 idem idem idem idem Post Test

15.15 ~ 16.00 idem idem idem idem Evaluation & Closing

Time

Coffee Break

Lunch Break

Coffee Break

Attachment 5 Photos

research reactor

Documents