The IRIS Reactor Technical Specifications
Disclaimer:
Information presented in this article are based on publicly available data of the IRIS reactor project, as properly cited from the original source. This article is NOT part of the official IRIS project led by Westinghouse. For more reliable information, the reader should refer to any official websites and information sources of the IRIS project and/or the IRIS consortium. All trademarks and registered trademarks shown in this article are the property of their respective owners.
| General Plant Data | |
| Core thermal power | 1000 MWt [ref.2-page35] |
| Power Plant Net Output | 335 MWe [ref.2-page35] |
| Nuclear Steam Supply System | |
| Number of coolant loops | Integral RCS [ref.2-page35] |
| Steam temperature/pressure | 317/5.8 °C/MPa [ref.2-page35] |
| Feedwater temperature/pressure | 224/6.4 °C/MPa [ref.2-page35] |
| Reactor Coolant System | |
| Total core flow rate | 36000 kg/s [ref.3-page53] |
| Primary coolant flow rate | 4700 kg/s [ref.2-page35] |
| Reactor operating pressure | 15.5 MPa [ref.2-page35] |
| Core inlet temperature | 292 °C [ref.2-page35] |
| Core (riser) outlet temperature | 330 °C [ref.2-page35] |
| Reactor Core | |
| Fuel assembly total length | 5.207 m [ref.2-page35] |
| Fuel inventory | 48.5 tU [ref.2-page35] |
| Average linear heat rate | 10.0 kW/m [ref.2-page35] |
| Average core power density (volumetric) | 51.26 kW/l [ref.2-page35] |
| Specific power (= core thermal power/fuel inventory) | 20.6186 kW/kg-HM |
| Fuel material | Sintered UO2 [ref.2-page35] Westinghouse standard PWR fuel |
| Fuel average density | 96% Theoretical Density [ref.3-page203] UO2-TD = 10.96 g/cc |
| Rod array | Square 17×17 XL [ref.2-page38,ref.5-page155] |
| Number of fuel assemblies | 89 [ref.2-page35] |
| Number of fuel rods/assembly | 264 [ref.2-page35] |
| Fuel pellet diameter | 8.19 mm [ref.1-page634] |
| Pellet-clad gap | 0.082 mm [ref.1-page634] |
| Clad thickness | 0.572 mm [ref.1-page634] |
| Outer diameter of fuel rods | 9.5 mm [ref.2-page35,ref.5-page155] |
| Pitch (center-to-center) | 12.54 mm [ref.1-page634] |
| P/D | 1.32 [ref.3-page34] |
| Average H/HM ratio (Hydrogen to Heavy Metal ratio) | 3.4 [ref.3-page34] |
| Volume fractions | 33.50% fuel 54.92% moderator 11.58% structure |
| Volume ratios | fuel-to-moderator: 0.6099 moderator-to-fuel: 1.6396 |
| Enrichment | 4.95 Wt % U-235 [ref.2-page35] |
| Coolant average density | 0.7295 g/cc [ref.6-page31] 0.727664 g/cc (calculated from enrichment and H/HM data) |
| Equilibrium cycle length | 30-48 months [ref.2-page35] |
| Average discharge burnup | 60 000 MWd/tU [ref.2-page35] |
| Reactor Pressure Vessel | |
| Cylindrical shell inner diameter | 6.21 m [ref.2-page35] |
| Wall thickness of cylindrical shell | 28.5 cm [ref.2-page35] |
| Total height (including clossure head) | 22.2 m [ref.5-page154] |
| Active core height (core barrel) | 426.7 cm [ref.5-page156] |
| Active core inner diameter (core barrel) | 241.27 cm [ref7-page45] calculated from core thermal power, power density, and active core height |
| Active core outer diameter (core barrel) | 285 cm [ref.5-page157] |
| Steam Generators | |
| Type | Vertical, helical coil tube bundle, once-through, superheated [ref.2-page35] |
| Number | 8 [ref.2-page35] |
| Thermal capacity (each SG) | 125 MWt [ref.2-page35] |
| Number of heat exchanger tubes (each SG) | 656 [ref.2-page35] |
| Reactor Coolant Pump | |
| Type | Spool type, fully immersed [ref.2-page35] |
| Number | 8 [ref.2-page35] |
| Pump head | 19.8 m [ref.2-page35] |
| Primary Containment | |
| Type | Pressure suppression, steel [ref.2-page35] |
| Geometry | Spherical, 25 m diameter [ref.2-page35] |
| Design pressure/temperature | 1300/200 kPa/°C [ref.2-page35] |
References
- Duderstadt, James J. and Louis J. Hamilton. (1976), Nuclear Reactor Analysis, John Wiley & Sons, Inc, New York.
- IRIS@NuclearNews
- MIT Master Thesis – Thermal Hydraulic Performance Analysis of a Small Integral PWR Core
- J-NucEngDes – Carelli – The exciting journey of designing an advanced reactor
- J-NucEngDes – Carelli et al. – The design and safety features of the IRIS reactor
- Data from US NRC
- Reactor dosimetry in the 21st century
Useful links
- IRIS official website
- IRIS – 2003 FINAL TECHNICAL PROGRESS REPORT
- IRIS@wikipedia
- Water density as a function of temperature and pressure
Standard PWR nuclear fuel assembly (17×17) technical specifications
| Geometry | Square 17×17 matrix |
| Fuel assembly dimension | Square 214 x 214 mm |
| Composition per assembly | Total: 289 Fuel: 264 Control rod guide thimble: 24 Instrumentation thimble: 1 |
| Fuel material | UO2 (U235,U238,Oxygen) |
| Cladding material | Zircaloy-4 98.23 weight % zirconium with 1.45% tin, 0.21% iron, 0.1% chromium, and 0.01% hafnium |
| Gap filler | Helium gas |
| Fuel average density | 95 – 96% Theoretical Density UO2-TD = 10.96 g/cc |
| Moderator (coolant) | light water (H2O) average density 0.7295 gr/cc |
| H/HM ratio (hydrogen to heavy metal ratio) | 1.7 – 3.4 (depends on enrichment level) |
| Enrichment | 2.5 – 5 Wt % U235 |
| Fuel pellet diameter | 8.19 mm |
| Pellet-clad gap | 0.082 mm |
| Clad thickness | 0.572 mm |
| Outer diameter of fuel rods | 9.5 mm |
| Pitch (center-to-center) | 12.54 mm |
| P/D | 1.32 |
Related Links
- Data from Oak Ridge National Laboratory
- Data from KAERI Nuclear Training Center
- Data from dspace@MIT
- Data from US NRC
- Zircalloy@wikipedia
- Water density as a function of temperature and pressure
Free Scientific Softwares
- JANIS (Nuclear Data Library)
- OpenFOAM (Computational Fluid Dynamics)
- OpenFEM (Finite Element Method)
- Scilab (Numerical Mathematics, Matlab-like)
- Lazarus (Integrated Development Environment, Delphi-like)
- From French EDF
- MATPACK (German C++ Library)
- VE-Suite
- Serpent – monte carlo reactor physics code
Catatan : Semua content berasal dari blog Saudara Syeilendra P. Pemuda Indonesia yagn sedang studi di Jepang ini merupakan salah satu sumber inspirasi dan motivator di bidangnya yang bersedia membagi ilmu walaupun jadwal studi yang ketat.
Terima kasih atas sharing ilmu dan pengalamannya.
Source : Syeilendra Pramuditya
No comments:
Post a Comment