Thermal hydraulic feasibility of supercritical carbon dioxide Brayton cycle power conversion for the KALIMER-150 sodium-cooled fast reactor
- 1. Argonne National Lab., IL (United States)
- 2. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
Description
One possible approach to achieving a significant reduction in the overnight and operating costs of a sodium-cooled fast reactor is to replace the traditional Rankine steam cycle with an advanced power converter that consists of a gas turbine Brayton cycle that utilizes supercritical carbon dioxide (S-CO2) as the working fluid. A joint project between Argonne National Laboratory and the Korea Atomic Energy Research Institute has been initiated to investigate the thermal-hydraulic feasibility of coupling the S-CO2 Brayton cycle to the KALIMAR-150 sodium-cooled fast reactor conceptual design. As an initial step in investigating the system aspects of coupling the reactor to the S-CO2 Brayton cycle, the case is investigated in which the intermediate heat transfer loop is eliminated in order to achieve additional cost reductions. The main objectives are to determine the potential gain in plant efficiency and to estimate the size of the key Brayton cycle components. A S-CO2 Brayton cycle efficiency of 43.2% is calculated. Accounting for primary pump power and other in-house loads, a net plant efficiency of 40.8% is obtained, compared to 38.2% for the current (Rankine cycle) plant. If higher Na temperatures could be accommodated, then a 1% gain in plant efficiency could be obtained for each 20degC incremental increase in sodium core outlet temperature. Further investigation of the thermal sizing of the Na/S-Co2 heat exchanger is also carried out; parametric sensitivity studies are performed for the case in which the intermediate heat transport system is retained as well as the case in which it is eliminated. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Imprint Pagination
- 3690 p.
- Journal Page Range
- 15 p.
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Acronym
- NUTHOS-6
- Dates
- 4-8 Oct 2004
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36072731
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRAYTON CYCLE; BRAYTON CYCLE POWER SYSTEMS; CARBON DIOXIDE; ENERGY EFFICIENCY; GAS TURBINES; HEAT EXCHANGERS; HEAT TRANSFER; LMFBR TYPE REACTORS; REACTOR COOLING SYSTEMS; SODIUM COOLED REACTORS; SUPERCRITICAL STATE; THERMAL HYDRAULICS
- Descriptors DEC
- BREEDER REACTORS; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; COOLING SYSTEMS; EFFICIENCY; ENERGY SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MACHINERY; MECHANICS; OXIDES; OXYGEN COMPOUNDS; POWER SYSTEMS; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC CYCLES; TURBINES; TURBOMACHINERY
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name FRIDAY October 8, Paper ID N6P 134.pdf