practice_final - 22.313 THERMAL-HYDRAULICS IN NUCLEAR POWER...

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22.313 THERMAL-HYDRAULICS IN NUCLEAR POWER TECHNOLOGY Tuesday, May 17 th , 2005, 9 a.m. – 12 p.m. OPEN BOOK FINAL 3 HOURS Problem 1 (30%) – Hydraulic analysis of the PWR primary system at cold zero-power conditions A greatly-simplified schematic of the PWR primary system is shown in Figure 1. The core and steam generators are represented by two form losses of coefficients 7 and 4, respectively. The loop can be modeled as a series of four identical round tubes of 1.45 m ID and 10 m length. The flow within the loop is driven by a pump that delivers a constant head, Δ P pump =200 kPa, regardless of the flow. Core (K=7) Steam generator (K=4) Pump 10 m 10 m g Figure 1. Simplified schematic of the PWR primary system You are to evaluate the hydraulic behavior of the system at cold zero-power conditions. In this situation the fluid can be considered isothermal at 20 ° C and atmospheric pressure. The properties of water at this temperature and pressure are reported in Table 1. i) Calculate the steady-state mass flow rate in the system. Clearly state all your assumptions. (10%) ii) Now consider flow start-up from stagnant conditions. At t=0 the pump is turned on and the flow is established. Calculate the time it takes for the mass flow rate to reach 50% of its steady-state value. (15%) ( Hint: use the following integral + = c 2 1 2 2 x c x c ln x c dx ) iii) A nuclear engineer wishes to simulate the PWR primary system by means of an experimental flow loop with the same form coefficients and geometrically similar, but of
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1/10 scale (the pump head is also scaled down to 1/10). Would such loop have the same
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This note was uploaded on 11/27/2011 for the course CHEMICAL E 20.410j taught by Professor Rogerd.kamm during the Spring '03 term at MIT.

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practice_final - 22.313 THERMAL-HYDRAULICS IN NUCLEAR POWER...

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