Published May 2012 | Version v1
Miscellaneous

Design of Supercritical Carbon Dioxide Compressor Testing Loop

  • 1. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
  • 2. KUSTAR, Abu Dhabi (United Arab Emirates)

Description

For small and medium-sized reactors and Generation IV reactors such as sodium-cooled fast reactor are recently under development actively. The supercritical CO2 Brayton cycle is considered as an attractive cycle for the above mentioned nuclear systems. This is because the supercritical CO2 Brayton cycle (S-CO2 cycle) is especially effective to reduce the volume of power generation system, which occupies 1.5∼2 times more space than the primary nuclear system in general. Comparing to traditional water-vapor cycle and helium cycle, the S-CO2 system has relatively much less volume and component size. Therefore, S-CO2 cycle can be used for many purposes such as nuclear ship propulsion where volume requirement is strict, or a small nuclear reactor when it is constructed on geographically limited area

Part of:
Proceedings of Korean Nuclear Society, Daejeon (KR)

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2012 spring meeting of the KNS
Dates
16-18 May 2012
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
43073518
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BRAYTON CYCLE; CARBON DIOXIDE; DESIGN; POWER GENERATION; SODIUM COOLED REACTORS
Descriptors DEC
CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; LIQUID METAL COOLED REACTORS; OXIDES; OXYGEN COMPOUNDS; REACTORS; THERMODYNAMIC CYCLES

Optional Information

Notes
3 refs, 2 figs