Indian assessment of DESAE (version 1.2) code

1. Indian assessment of DESAE (version 1.2) code I.V. Dulera, R.K. Sinha, A. Basak and U.D. Malshe Reactor Engineering Division Bhabha Atomic Research Centre Mumbai – 400 085, India dulera@apsara.barc.ernet.in Consultancy Meeting On Nuclear Energy Modelling Tools As Integral Part of IAEA Toolbox for INPRO Methodology 18-20 May, 2005 IAEA Headquarters, Vienna

2. Indian Energy Resources – Very limited fossil fuel reserves makes nuclear the only long term sustainable option [5] [1] [2] [3] [4] References:[1] Report of working group on coal and lignite for the tenth five year plan (2002-2007) July 2001.[2] Annual report, 2002-2003, Ministry of Petroleum and Natural gas, Government of India Page 13, strategic goals of ‘Doubling Reserve Accretion’ to 12 BT (Oil+ Oil Equivalent Gas)’ and ‘Improving Recovery Factor to the order of 40% for the next two decades (2001-2020). Estimated reserves in the basins is 30 BT of hydrocarbon reserves. With 40% recovery factor it can be assumed that cumulative availability of hydrocarbons up to the year 2052 would be nearly 12 BT of (O+OEG [3] Annual report 2001-2002, page 6, Ministry of Power, Government of India[4] Annual report, page 4, 2001-2002, Ministry of Non-Conventional Energy Resources, Government of India [5] A strategy for growth of electrical energy in India, Document no. 10, August 2004, Department of Atomic Energy

3. Indian population is expected to stabilize at 1.50 Billion. Large population and limited fossil fuel resources make nuclear the only long term sustainable fuel option Assuming reducing growth rates as follows: 1991-2001: 1.99% 2001-2011:1.50% 2011-2021:1.02% 2021-2031:0.70% 2031-2041:0.40% 2041-2051:0.20% >2051: 0.0%

4. Primary and Electrical Energy – Projected Growth to realize a per capita electricity consumption of around 5000 kWhr/year

5. Indian Nuclear Power Programme – 3 Stage Programme and Extended 3rd Stage • Extended 3rd Stage - Use of Nuclear Energy as Primary Source of Energy • Source of high temperature heat for hydrogen production • Desalination for potable water • District heating in cold regions • Compact nuclear power pack for supplying electricity to the regions not connected to the electrical grid system

6. DESAE Code (version 1.2)– Indian Assessment • DESAE is an excellent code to plan and optimize country’s nuclear power programme by studying possible combinations of different types of reactors • Estimation of nuclear fuel resources and their optimization • Estimation of infrastructure needed for various aspects of fuel cycle • Estimation of overall economics • - Investments in nuclear plant building, in fuel recycling, in fuel fabrication etc. • Estimation of amount of important material needed

7. DESAE Code – Indian Assessment- Commissioning Experiences • The code was commissioned on computer systems having Microsoft Windows XP (Home edition) as the operating system. The other important features of the computer are: Pentium 4 2.4 GHz, 256 MB RAM, 80 GB Hard Disk • During initial commissioning, the code was installed without MATLAB being on the machine • Code could not be run completely with abrupt end • Code was installed with MATLAB Version 6.5 pre-installed on the machine • Code could be run successfully • On another machine, the code was installed with MATLAB 7.0 version pre-installed on the machine • Code could not be run completely with abrupt end • Recommendation: The executable version not requiring MATLAB on the machine will be preferable

8. DESAE Code – Indian Assessment- Input Interfaces • Unless all seven types of reactor types are selected, program abruptly ends • Difficulty in combining several NPP to particular NFC type •  Individual NFC for each NPP or Flexibility of linking NPP to NFC type • Difficulty in linking fuel made from reprocessed fuel of a particular type of NPP to other NPP as input fuel •  Code can become more useful if Input of reprocessed fuel from NFC to NPP linking is also incorporated in the code

9. DESAE Code – Indian Assessment- Input Interfaces

10. DESAE Code – Indian Assessment- Input Interfaces • New reactor type has to be selected from one of these options, which may not be the case, as in INPRO many innovative designs with different fuel cycles are being worked out •  Flexibility in the code for incorporating a new reactor • The characteristics of the reactors will differ from reactor to reactor • The characteristics will also differ for different fuel cycles such as Thorium fuel •  Code can become more useful if Input of reprocessed fuel from NFC to NPP linking is also incorporated in the code

11. DESAE Code – Indian Assessment- Input Interfaces ? ? Natural Reactor life Staff • The characteristics of the reactors will differ from reactor to reactor • They will also differ for different fuel cycles such as Thorium fuel cycle •  The Code can become more useful if there is a flexibility in introducing characteristics for individual reactor type, different fuel cycle and materials

12. DESAE Code – Indian Assessment- Incorporation of type of reactors being developed in India • Advanced Heavy Water Reactor (AHWR) type reactors • Flexibility of introducing near term and long term fuel cycles • Case study for hydrogen producing high temperature reactors • Recommendation: Interface, if self explanatory will be understood better by English speaking people

13. DESAE Code – Indian Assessment- Code should have the flexibility to accommodate varying fuel cycle for reactors in time domain • AHWR - Incorporation of near term and long term fuel cycles

14. DESAE Code – Indian Assessment- Assessment using the INPRO methodology for innovative nuclear energy systems based on high temperature reactors Internationally several innovative nuclear system (INS) concepts for producing high temperature process heat for electricity and/or hydrogen generation are under various phases of conceptualization, design and development. India has proposed an INPRO joint study on “Assessment using the INPRO methodology for innovative nuclear energy systems based on high temperature reactors” by interested member states. The scope of joint activities include: • Assessment of future hydrogen and/or electricity demand and means to meet these demands – Energy planning using IAEA/INPRO tools like MESSAGE, SIMPACT, DESAE, SYRTEX etc. • Assessment of candidate high temperature INS concepts to fulfill a part of the projected demands offered for assessment. This will include using INPRO manual for the assessment of one or more INS concepts as under – • Candidate hydrogen generating INS concepts • Candidate high temperature rewactor based concepts for electricity generation Deliverables will be assessment reports pertaining to: • National hydrogen/ electricity demands and • The HTR based INS offered for for assessment • List of R&D tasks for development of reactors, in conceptual stages, will be highlighted

15. DESAE Code – Indian AssessmentNuclear hydrogen production is best suited for water splitting – Environmentally benign Electrolysis Water Thermo-chemical cycle H2 H2 Thermo-chemical Processes: Cu-Cl: Copper - Chlorine, Ca-Br2 : Calcium-Bromine, I-S: Iodine-Sulfur Process Electrolysis Processes: AW: Alkali Water, MC: Molten Carbonate SP: Solid Polymer, HT: High Temperature Ref: High Efficiency Generation of Hydrogen Fuels Using Nuclear Power, G.E. Besenbruch, L.C. Brown, J.F. Funk, S.K. Showalter, Report GA–A23510 and ANL Website Ref: IAEA-TECDOC-1085: Hydrogen as an energy carrier and its production by nuclear power

16. DESAE Code – Indian Assessment- Assessment of Hydrogen Generating Innovative Nuclear Systems Some input data (Besides usual reactor characteristics): • Input as thermal power rather than electrical power • Amount of heat to be utilized for hydrogen production • Amount of heat to be utilized for electricity generation • Utilization of waste heat for desalination/ district heating • Process of producing hydrogen • From hydrocarbon sources • By thermo chemical water splitting (Iodine-Sulfur/Calcium-Bromine/ Copper-Chlorine/ other suitable method) • Reactor characteristics and operating parameters • Amount of hydrogen and oxygen produced and their parameters • Operation and safety characteristics of hydrogen producing plant • Capacity and availability factors for the hydrogen producing plant • Whether a full fledge redundant hydrogen producing plant necessary in case of a long shutdown felt necessary for maintenance of a plant if the environment ishighly corrosive – Switch over frequency and effect on nuclear reactor (Contd………)

17. DESAE Code – Indian Assessment - Assessment of Hydrogen Generating Innovative Nuclear Systems Input data (Besides usual reactor characteristics-----Continued): • Electrical power generating system • Possibility of varying energy for hydrogen production/power generation • Process stream chemicals and their inventory for hydrogen producing plant • Materials of construction / membranes / catalysts etc. • Materials required for such nuclear reactors – Graphite etc. • Fuel (TRISO Coated) behavior – High burnup – once through option or possibility of reprocessing considering difficulties involved • Fuel cycle option – 235U/Pu/233U • Choice of coolant – Helium/ Pb based/ Molten salt • Intermediate loop behavior – heat transfer for different processes at different temperatures • From chemicals related safety point of view - distance between nuclear reactor and hydrogen producing plant

18. DESAE Code – Filling up of the gaps between the existing code and the future development • The work mainly involves: • Developing interfaces for making inputs for reactor specific / fuel cycle characteristics and data • Developing interfaces for making inputs for hydrogen producing plant related characteristics and data • Developing interfaces for making inputs for small power nuclear power pack related reactor characteristics and data • Existing code to be modified to take into account these new data as variables • Options to carry out these: • If source codes are provided, these modules can be developed and incorporated by interested member states (Open software development environment where each participating state contributes in his own way) • For making reactor/fuel cycle specific input data a separate code can be developed – A proper interface also to be developed to relate to main code • For making interfaces for hydrogen plant and nuclear power pack specific characteristic and data a separate code can be developed – Interface to relate to main code

19. DESAE Code – How India can assist in the development • If requested, we can develop the new modules • Linking with the main code with the assistance of original code developers • Preparation of online help for the code for clarifying inputs etc. and explaining the terms to make the code more user friendly (The current help file is very good in explaining the execution of the code) • - Linking with the main code with the assistance of original code developers • Preparation of modified version of users manual in English by also incorporating clarifications as regards interfaces, inputs, etc. and make it more clear to people from English speaking countries • Development of interface - linking code for combined application of MESSAGE and DESAE for complete energy planning

20. Full capabilities of DESAE Code was seen by trying out a number of probable cases for proposed Indian Nuclear programme

21. Other code needs to be developed \ provided • Other codes which need to be developed/ provided to member states to address issues related to: • Assessment of inherent safety of the reactor system • Verifying the various levels of defence in depth for a particular INS • Assessment of the overall safety for INS • Assessment of proliferation resistance of INS • Assessment of degree of passiveness of the safety and heat removal systems • Assessment of safety against external events

22. Thank You