GO GREEN Current Status of HTGR Conceptual Design at the Center for Reactor Technology and Nuclear Safety Tagor M. Sembiring, Zuhair, Ign. Joko Irianto,

Presentasi berjudul: "GO GREEN Current Status of HTGR Conceptual Design at the Center for Reactor Technology and Nuclear Safety Tagor M. Sembiring, Zuhair, Ign. Joko Irianto,"— Transcript presentasi:

1 GO GREEN Current Status of HTGR Conceptual Design at the Center for Reactor Technology and Nuclear Safety Tagor M. Sembiring, Zuhair, Ign. Joko Irianto, Sumijanto Reactor Development Div. PTRKN–BATAN Workshop on Advanced Reactors and Small and Medium-sized Nuclear Reactors (SMRs) for Embarking Countries 19 August 2013 BATAN Head Quarters - JAKARTA

2 Contents Introduction User Consideration of HTGR Reactor Status of HTGR Conceptual Design Problems Summary Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN2

3 Introduction (1) The HTGR R&D Programs has a long history in Indonesia BATAN started the HTGR R&D programs in 1989 with by set-up a team work for a technology assessment of PWR and HTR reactors. In the 1993-1998, BATAN established a team focused on the assessment of HTGR reactors and its heat application Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN3

4 Introduction (2) During 1993-1998, several national seminars on the technology and application of HTGT are carried out In the period, stake holders from national oil and gas companies, state companies, universities, government institutes were joined in some assessments with BATAN. In the 1999 – 2005, one center in BATAN had a duty for advanced reactors technology assessment including HTGR (Research Center for Advanced Reactor System) Senin, 19 Agustus 2013PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN4

5 Introduction (3) Participated with HTGR international community, through IAEA (CRP on Evaluation of HTGR Performance), especially benchmark analysis on initial core of HTTR (Japan), HTR-10 China and ASTRA (Russia) (IAEA –TECDOC-1382 and IAEA-TECDOC- 1694) Since 2006, the Center for Reactor Technology and Nuclear Safety has a duty for HTGR R&D programs. Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN5

6 User Consideration of HTGR Reactor (1) Based on the National Medium – Term Development Plan (2010-2014) from Presidential Regulation of The Republic Indonesia No. 5/2010: “….to carry out the conceptual design of core, conversion and safety system for the advance reactor …” Center for Reactor Technology and Nuclear Safety (BATAN) implemented it in carrying out a conceptual design of HTGR reactor Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN6

7 User Consideration of HTGR Reactor (2) We started a conceptual design by making a User Consideration Document (UCD) in the year of 2010 The assessment was carried out based on the site of Bangka Belitung Island (study by the Center for Nuclear Energy Development) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN7

8 User Consideration of HTGR Reactor (3) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN8 No.Items /ParametersValue 1.Energy (ouput)200 MW (th) 2.TypePebble 3.OperationBase load 4.Life time60 years 5.Fuel managementonce-through 6.Enrichmentlow 7.Heat process application (cogeneration) H2 production and water desalination

9 User Consideration of HTGR Reactor (4) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN9 YearsMain focus 2011Core design 2012Energy conversion system unit design 2013Helium Inventory Control System (Safety Related System) and Auxiliary System 2014Safety Analysis and Final Document

10 Status of HTGR Conceptual Design (1) Fuel and core descriptions Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN10 Pebble fuel: Diameter of pebble (cm) Diameter of fuel zona (cm) Graphite shell thickness (cm) 6,0 5,0 0,5 TRISO: Fuel Kernel Radius of fuel kernel (cm) Density of fuel kernel (g/cm3) 235U enrichment (%) Boron impurity (ppm) Coating layers Coating layers materials Coating layer thickness (cm) Density of coating layer (g/cm3) 0,025 10,4 8,2-10 0,5 C/IPyC/SiC/OPyC 0,0095/0,004/0,0035/0,004 1,05/1,9/3,18/1,9 0,092

11 Status of HTGR Conceptual Design (2) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN11 Reactor parameters: Power (MW)200 Core Volume (m 3 )66,657 Avarage power density (MW/cm 3 )3 Inlet temperature (oC)550 Outlet Temperature (oC)950 He pressure (MPa)7 Aliran massa pendingin (kg/s)120 Core Specifications: Height (m)9,43 Radius (m)1,5 Number of pebbles per m 3 5.394 Number of pebbles in the core359.548 Packing fraction of pebble in the core (%)61 Boron impurity in graphite (ppm)2

12 Status of HTGR Conceptual Design (3) The fuel flexibility are studied such as using MOX and Th fuels Computer codes : MCNP5 MCNPX and VSOP-94 Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN12

13 Status of HTGR Conceptual Design (4) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN13 Figure 2. The fuel reactivity feedback coefficients

14 Status of HTGR Conceptual Design (5) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN14 Figure 3. keff vs water density in the water ingress accident

15 Status of HTGR Conceptual Design (6) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN15 Analysis of efficiency Using 1 compressor

16 Status of HTGR Conceptual Design (7) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN16 Using 2 compressors

17 Status of HTGR Conceptual Design (8) The software for energy conversion unit system: Chemcad CycleTempo Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN17

18 Status of HTGR Conceptual Design (9) Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN18 Modeling the Helium Inventory System

19 Status of HTGR Conceptual Design (10) The software for helium inventory control system: Chemcad SuperPro Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN19

20 Problems (1) Using obsolete code, such as VSOP-94 The pebble-HTGR transient analysis codes are needed, such as water ingress, reactivity insertion Benchmark data for transient cases of HTGR reactor are needed Human resources experiences in HTGR system are so minimal, such as helium inventory system, fuel management mechanism, I&C etc. Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN20

21 Problems (2) The IAEA HTGR Review Team (6 experts) will review the HTGR R&D program in BATAN including fuel aspects In the review meeting some softwares/codes will be delivered to BATAN Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN21

22 Summary (1) BATAN has a long history in the HTGR R&D program During initial core in HTTR-Japan and HTR- 10-China, BATAN participated in the IAEA CRP among advanced countries in HTGR reactor technology (IAEA-TECDOCs) The 200 MW (th) HTGR conceptual design has been carried out since 2010 based on the feasibility study in the Bangka Belitung island Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN22

23 Summary (2) The core, primary and secondary circuits of the core have been designed In the year of 2014, the conceptual design will be finished The IAEA technical assistances are needed for finishing the design especially in the safety aspect point of view, as well as preparing the HTGR R&D road map in BATAN Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN23

24 Thank you very much for your attention Q&A? Senin, 25 Agustus 2014PUSAT TEKNOLOGI REAKTOR DAN KESELAMATAN NUKLIR, BATAN24