Page 329 - Corrosion Engineering Principles and Practice
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300     C h a p t e r   8                                                                                                           C o r r o s i o n   b y   W a t e r    301


                         Boiling  water  reactor  designs  can  be  modified  to  accommodate  a
                      superheater  to  raise  the  steam  temperature  for  improved  efficiency.
                      Experimental  nuclear  superheaters  have  been  built  to  superheat  the
                      steam from the boiling water reactor. Corrosion rates for stainless steels
                      and nickel alloys under heat transfer in the 600°C temperature range are
                      about  25  µm/y.  However,  experience  has  shown  that  even  minute
                      amounts of entrained moisture in the entering steam can carry sufficient
                      chlorides that cracking of the stainless steel cladding of the nuclear fuel
                      elements may ultimately ensue. Alloys with higher nickel contents (e.g.,
                      N08800, N06600, or N06690) have resisted SCC under these conditions.

                      8.5.6  Nuclear Pressurized Water Reactors
                      In a pressurized water reactor (PWR) (Fig. 8.19), high-purity water is
                      pumped past nuclear fuel elements where it becomes heated. The heated
                      water then goes to the tube side of a heat exchanger, giving up its heat to
                      boil water on the shell side. Steam is generated from the boiler water.
                         The water adjacent to the core is called primary water. It is usually
                      treated with hydrazine to remove oxygen, with lithium hydroxide or
                      ammonium hydroxide to pH 10 to 11 to minimize corrosion product
                      transport, and with 25 to 50 cc hydrogen per kg of water to suppress
                      radiolytic  decomposition  of  water  (thereby  minimizing  corrosion
                      product transport).
                         The nuclear fuel must be clad with a corrosion-resistant material to
                      prevent  the  release  of  radioactive  gases  and  fission  products  to  the
                      primary water. The fuel itself is usually uranium oxide, which is quite
                      resistant to the primary water. The fuel is clad with austenitic stainless
                      steel or Zircaloy-2 (R60802) or the extra-low nickel Zircaloy-4 (R60804).



                       Containment structure
                                            Steam (nonradioactive)
                           Steam
                     Control  generator
                      rods
                 Nuclear
                  reactor                                      Generator

                                                Turbine



                        Core
                                                   Condensor cooling water
                     Radioactive water                (nonradioactive)
                                 Pump
                                                                     Cooling tower
                 FIGURE 8.19  Pressurized water reactor.
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