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

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22.313 THERMAL-HYDRAULICS IN NUCLEAR POWER TECHNOLOGY Tuesday, March 29 th , 2005, 1:00 – 2:30 p.m. OPEN BOOK MID-TERM QUIZ 1.5 HOURS Problem 1 (20%) – Calculation of Flow Quality from Void Fraction Measurements By means of X-ray imaging techniques an MIT graduate student is able to measure the void fraction in the downcomer of an experimental apparatus designed to study steam carryunder at 7.0 MPa. This student has taken course 22.313, so she is also able to calculate the relative velocity, v b =v -v v , from a Re-Eo-M diagram for bubbly flow. Does the student miss any information needed to calculate the flow quality in the dowcomer? ( Note: in answering this question, do not assume that a carryunder correlation is available) If so, what information is missing? If not, write a set of equations that would allow the student to calculate the flow quality given only the void fraction, the relative velocity and, of course, the properties of steam and water at 7.0 MPa. Problem 2 (30%) – Pressure Drop in Accelerating Single-Phase Flow
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practice_quiz - 22.313 THERMAL-HYDRAULICS IN NUCLEAR POWER...

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