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BATAN R&D ON REACTOR TECHNOLOGY AND NUCLEAR SAFETY PROGRAM

BATAN R&D ON REACTOR TECHNOLOGY AND NUCLEAR SAFETY PROGRAM. Dr. Setiyanto, M.Sc. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY NATIONAL NUCLEAR ENERGY AGENCY OF INDONESIA Presented at:

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BATAN R&D ON REACTOR TECHNOLOGY AND NUCLEAR SAFETY PROGRAM

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  1. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY BATAN R&D ON REACTOR TECHNOLOGY AND NUCLEAR SAFETY PROGRAM Dr. Setiyanto, M.Sc. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY NATIONAL NUCLEAR ENERGY AGENCY OF INDONESIA Presented at: • Workshop on “Advanced Reactors and Small and Medium-sized Nuclear Reactors (SMRs) for Embarking Countries” 19-20 August 2013

  2. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY BackgroundPresidential Regulation No. 5 Year of 2010 “RPJMN 2010-2014” • Based on presidential regulation no. 5 year of 2010, the research and development on nuclear energy and control include energy and non-energy area. • The R&D in Energy area include nuclear mining, nuclear fuel elements, nuclear reactor and waste management. • The reactor technology and nuclear safety R&D is performed at the Center for Reactor Technology and Nuclear Safety. Monday, 19-20 August 2013 CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY 2

  3. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Main Task of the Center for Reactor Technology and Nuclear Safety • To perform the development of reactor technology and physics • To perform an assessment and analysis on reactor safety • To perform the development reactor utilization • To perform the development of nuclear safety technology, • To perform facility operation

  4. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Output of the Center for Reactor Technology and Nuclear Safety • Innovative research reactor (IRR) conceptual design • Cogeneration power reactor conceptual design • Evaluation of Technology, Technology and Reliability of PWR Power Reactor.

  5. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Innovative research reactor (IRR) conceptual design The innovative research reactor conceptual design include: • Conceptual design of neutronics core parameters • Design parameter of secondary cooling system • Design parameter of primary cooling system and and safety • Data and analyses ZRA release of innovative research reactor.

  6. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Innovative research reactor conceptual design result • Program period: 2010-2014 • Result 2010 : User Criteria Document of IRR • Site and Environment • Benefits and Usage of Reactor • Reactor core neutronic design • Core and system thermal-hydraulics design • Control system design • Safety feature design • Fuel design

  7. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Innovative research reactor conceptual design • 2012 : Reactor Core Conceptual Design of IRR • Reactor core neutronic design ( thermal neutron flux: ~ 4x1014 n/cm2s) • Core and system thermal-hydraulics design • Radiation Protection design

  8. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Innovative research reactor conceptual design • 2013 : Reactor Conceptual Design of IRR (on going) • Reactor core neutronic design • ( thermal neutron flux: ~ 1x1015 n/cm2s) • Core and system thermal-hydraulics design • Radiation Protection design • Engineering Safety features design • Auxiliary System design • Instrumentation and Control design • Electrical System design • Ventilation and Air Condition monitoring design • Reactor Building design

  9. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Cogeneration power reactor conceptual design • To provide conceptual design of cogeneration power reactor • Type of reactor: High Temperature Gas Cooled Reactor (HTGR) or Reaktor Gas Temperatur Tinggi (RGTT) • Name of Reactor: RGTT200K • Power : 200 MW, based on Babel Electrical need • K = kogenerasi (cogeneration) for H2 production and desalination • Target 2014: Conceptual design of reactor core, cooling system, safety and control system of helium cooling inventory.

  10. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Cogeneration power reactor conceptual design • Design Road Map Safety, conversion and core conceptual design Safety system conceptual design Conversion system unit conceptual design Core conceptual design

  11. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Cogeneration power reactor conceptual design

  12. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Evaluation of Technology, Safety and Reliability of PWR Power Reactor. • Design evaluation of reactor core management, core reactivity dynamics, subsystem and component, radiation protection feature. • Evaluation of accident analysis of reactor cooling inventory system, radiological accident consequences, severe accident evaluation PSA level-2, containment performance analysis and severe accident management program of PWR. • Evaluation of non-safety related instrumentation and control system, operator support system, steam generator design of PWR • Evaluation of measurement package of thermal system, modified grinding machine support equipment.

  13. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Evaluation of Technology, Safety and Reliability of PWR Power Reactor. Analysis flux distribution and neutron spectrum PWR 1000MWe

  14. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Evaluation of Technology, Safety and Reliability of PWR Power Reactor. Point Kinetic Model for PWR Simulation

  15. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Evaluation of Technology, Safety and Reliability of PWR Power Reactor. Containment performance and aerosol studies

  16. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Evaluation of Technology, Safety and Reliability of PWR Power Reactor. Technology assessment

  17. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Laboratory Facilities 1. Test Component Rig Test Component Rig = TCR is a means to perform testing of components such as static and dynamic seals, safety valves (safety valve), on-off valve arrangement, the limiting valve (check valve) used at a particular temperature and pressure. Design Test Component Rig as follows:- Input Pressure: 26 MPa = 260 bar- Temperature: 400oC- Fluid Process: demineralized water- Operating Pressure: 125 bar- Operating Temperature: 400oC s.d- Flow Rate: 0.07 ~ 0.1 kg / sec- The maximum revolution speed: 20,000 RPM,  Max Motor Power: 10 kw  Electricity consumption: 100 KW

  18. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Laboratory Facilities 2. Reactor Thermal Hydraulic TEST LOOP (General Loop) Reactor Thermal Hydraulic Test Loop is a means to conduct research and development of reactor safety technology, viewed from the aspect thermal hydraulic, at steady state and transient, the power channel type light-water nuclear power plant (PWR) and heavy water (PHWR). Variety of research done on steady-state conditions is a change in pressure, the bubble fraction, critical heat flux (CHF), the coefficient of heat transfer and others. While in transient conditions such as loss of coolant accident or a small leak (SB Loca) loss or waster heat flow and other Reactor Thermal hydraulic Test Loop is as follows:- Planning Pressure: 180 bar operating pressure: 150 bar.- Temperature planning: 357oC, operating temperature: 325oC- The capacity of the cooling flow: 11.8 kg / sec.- Total power requirements: 6 MW- Material strand Stainless Steel (AISI316)- Heating the test using 3.2 MW of electricity.

  19. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Laboratory Facilities 2. Primary Loop 3. Primary Loop Strand and Chemical Water Corrosion Test is a means to test the dynamic and fretting corrosion of materials, as well as technically able to simulate chemical and physical conditions of the steam generator PWR and PHWR type nuclear power plants. By using this strand can be studied primary and secondary cooling system of NPP. This test strand design conditions as follows:Primary side :- Pressure: 180 bar,- Temperature: 357oC,- Discharge: 500 kg / hour.Secondary side:- Pressure: 100 bar,- Temperature: 311oC, - Discharge: 400 kg / hour.- Power Consumption: 120 KWatt

  20. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Laboratory Facilities 4. Beta Test Loop 4. BETA TEST LOOP BETA Test Loop is a means to conduct research and development of reactor safety technology, viewed from the aspect thermal hydraulic, at steady state (steady state) and transient. Variety of research being undertaken include rewetting, the study of heat transfer in narrow gap, SB. Loca, etc.. Design BETA Test Loop conditions as follows:- Planning Pressure: 10 bar,- Temperature planning: up to 850oC- The capacity of the cooling flow: 11.8 kg / sec.- Needs total electric power: 250 KWatt- Material strand Stainless Steel (SS-304)- Heating the test section 25KWatt of electricity.

  21. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Laboratory Facilities 5. Means Of Experiments Condensate Used for the experimental process of condensation of steam at atmospheric pressure, with pressure injection system and a wide variety of injection angles to determine the condensation process.

  22. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Closing remark • All activities regarding R&D on reactor technology and nuclear safety program are provided to support the deployment of Nuclear Power Plant in Indonesia either Small and Medium Size or Large Size Reactors. • As a technical support organization, the center for reactor technology and nuclear safety is continuously improve its capacity building through research and analysis of the current and future technology. • An assistance from IAEA, especially from Nuclear Power Technology Development Section of IAEA would be very helpful for improving our researchers and engineers capacity building.

  23. CENTER FOR REACTOR TECHNOLOGY AND NUCLEAR SAFETY Thank you very much for your kind attention Selasa 22 Mei 2012 PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN 23

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