1 / 30

Nuclear Reactors Schemes and thermodynamics

Nuclear Reactors Schemes and thermodynamics. William D’haeseleer. P W R Pressurized Water Reactors. T prim ~ 300 °C (max ~ 320 à 330°C; T sat = 345 °C) p prim ~ 155 bar ► Primary circuit = liquid. Note that level pressurizer is at ~ 20 m above output reactor;

rian
Download Presentation

Nuclear Reactors Schemes and thermodynamics

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript


  1. Nuclear ReactorsSchemes and thermodynamics William D’haeseleer

  2. P W RPressurized Water Reactors

  3. Tprim~ 300 °C (max ~ 320 à 330°C; Tsat = 345 °C) pprim ~ 155 bar ► Primary circuit =liquid

  4. Note that level pressurizer is at ~ 20 m above output reactor; this amounts to ~ 2 bar difference (observe that psat= 128.6 bar at T=330°C)

  5. Thermodynamic Cycle in PWR (primary cycle)

  6. Typical Parameters Tin≈ 280 à 290 °C Tout ≈ 310 à 330 °C pprim≈ 155 bar = 15.5 MPa Δppump 5 bar = 0.5 MPa

  7. Thermodynamic Cycle in PWR (secondary cycle)

  8. Example parameters Doel 4 Primary Circuit pprim = 155.2 bar (at pressurizer) T in reactor = 294 °C T out reactor = 332 °C Mass flow per loop = 23 482 m3/h Secondary Circuit p out SG = 76 bar (at outlet SG) T out SG = 291.3 °C Steam mass flow 3 SG = 6000 t/h T in SG= 224 °C p in SG = 78 bar

  9. CANDU Horizontal pressure tubes, D2O at about 100 bar, no boiling Tin = 266 °C Tout = 310 °C D2O acts as moderator in “calandria” (‘pressureless’ vessel) Continuous refueling possible Fuel = natural uranium

  10. Boiling Water Reactor BWR

  11. Typical Western LWR Typical psteam = 70 bar Tout reactor = 290 °C

  12. RBMK Vertical pressure tubes, H2O at about 70 bar, Tin = 260 °C Tout = 284 °C  Boiling occurs Graphite acts as moderator surrounding the fuel tubes Continuous refueling possible Fuel = enriched uranium (2%)

  13. RBMK

  14. Continuous loading reactor

More Related