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Additional resources for System 80+ Standard [nucl. powerplnt] Design - Vol 04
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CERTIFICATION - ii 4. i Power i i |ii i , i i iiiii i iiii i iiiii ii i Operation Loads are derived from conditions encountered during transient and steady-state operation in the design power range. ) 5. Reactor Trip Loads correspond to those produced by control element assembly deceleration. B. Upset Condition (Condition in the (CEA) fuel assembly motion and II) Condition II situations are unplanned events and operating basis earthquakes (OBEs) which may occur with moderate frequency during the life of the plant.
In this region of local inlet turbulence, Inconel 625 was selected rather than Zircaloy-4 to provide additional strength and relaxation resistance. Inconel 625 is a very strong material with good ductility, corrosion resistance and stability under irradiation at temperatures below 1000°F. The fuel assembly upper and lower end fitting are of cast 304 stainless steel and the upper and lower end fitting posts are Type 304 stainless steel machined components. This material was selected based on considerations of adequate strength and high corros_on resistance.
821 MeV). No evidence of a chemical reaction was observed on the cladding ID. Short-term chemical compatibility during upset and emergency conditions is demonstrated by the fact that conditions favorable to a chemical reaction between Zircaloy-4 and AI_O_ are not present at temperatures below 1300°F (R_f_rence 39). 1). The reaction between Zircaloy-4 and AI_O 3 described by Idaho Nuclear (Reference 40) was observed _o occur rapidly only at temperatures in excess of 2500°F, well above the peak Zircaloy-4 temperatures in the higher-energy fuel rods described in Chapter 15.