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Thermodynamics Thermal Hydraulics © Copyright 2016 193008 – Thermal Hydraulics OGF - Polling 1. Convection heat transfer improves when nucleate boiling begins on the surface of a fuel rod because: © Copyright 2016 193008 – Thermal Hydraulics 0% 0% io n of nk e. ... .. f.. . 0% bu bb le ot m th e st ea m st ea m bu bb le f.. . 0% bl a D. m C. te a B. steam bubble formation decreases coolant flow rate along the fuel rod. steam bubble formation increases coolant flow rate along the fuel rod. a steam blanket begins to form along the surface of the fuel rod. the motion of the steam bubbles causes rapid mixing of the coolant. as A. OGF - Polling 2. How does the convective heat transfer coefficient vary from the bottom to the top of a fuel assembly if reactor coolant enters the fuel assembly as subcooled water and exits as superheated steam? Increases continuously. Increases, then decreases. Decreases continuously. Decreases, then increases. as es ,t he ... 0% De cr e co nt ... 0% as es ea se s ,t nt ... 193008 – Thermal Hydraulics In cr co se s ea In cr © Copyright 2016 0% he ... 0% De cr e A. B. C. D. OGF - Polling 3. Departure from nucleate boiling should not be allowed to occur in the core because... 193008 – Thermal Hydraulics . bu bb l.. . 0% ste am bu bb l.. as ste am bu bb l.. ste am as © Copyright 2016 0% . 0% . 0% as D. bu bb l.. C. ste am B. as steam bubbles begin to blanket the fuel rod, the radiative heat transfer decreases. as steam bubbles in the coolant form and then collapse, water hammer occurs. as steam bubbles begin to blanket the fuel rod, its temperature rises sharply. as steam bubbles form in the coolant, voidsinduced reactivity changes cause undesirable power changes. as A. OGF - Polling 4. Which one of the following parameter changes will reduce the departure from nucleate boiling ratio? Decreasing reactor power. Increasing pressurizer pressure. Increasing reactor coolant flow rate. Increasing reactor coolant temperature 193008 – Thermal Hydraulics gr ea sin gr ea . .. 0% In cr sin gp re sin ea In cr ea ... ea gr as in De cr e © Copyright 2016 0% ea . .. 0% .. . 0% In cr A. B. C. D. OGF - Polling 5. How does the critical heat flux vary from the bottom to the top of a typical fuel assembly during normal 100 percent power operation? Increases continuously. Increases, then decreases. Decreases continuously. Decreases, then increases. as es ,t he ... 0% De cr e co nt ... 0% as es ea se s ,t nt ... 193008 – Thermal Hydraulics In cr co se s ea In cr © Copyright 2016 0% he ... 0% De cr e A. B. C. D. OGF - Polling 6. Which one of the following is most likely to result in fuel cladding damage? 193008 – Thermal Hydraulics ... ith ta gw tin ra in a An 0% ... 0% nt dv er te ga tin Op er a © Copyright 2016 0% ... t1 .. . 0% ga D. Op e C. tin B. Operating at 110 percent of reactor vessel design pressure. An inadvertent reactor trip from 100 percent power. Operating at a power level that exceeds the critical heat flux. Operating with saturated nucleate boiling occurring in a fuel assembly. Op er a A. OGF - Polling 7. Which one of the following describes a function of core bypass flow? 0% li. .. sc oo de on ... ve nt s bo r m 193008 – Thermal Hydraulics Pr e sa de Pr ov i © Copyright 2016 0% s.. . 0% ea .. . 0% ex ce D. Pr ov i C. ve nt s B. Provides a means of measuring core flow rate. Prevents boron precipitation in the core baffle area. Prevents excessive reactor vessel wall differential temperature. Provides cooling to various reactor vessel internal components. Pr e A. OGF - Polling 8. Which one of the following must exist for natural circulation flow to occur? © Copyright 2016 193008 – Thermal Hydraulics 0% he a ts in k ... 0% ... 0% ts ou rc . .. he a Th e Th e he a ts ou rc . .. 0% Th e D. ts in k C. he a B. The heat source must be larger than the heat sink. The heat source must be located higher than the heat sink. The heat sink must be larger than the heat source. The heat sink must be located higher than the heat source. Th e A. OGF - Polling 9. During the reflux boiling method of core cooling, steam from the reactor core is condensed in the __________ side of a steam generator and flows back into the core via the __________. (Assume the steam generators contain U-tubes.) hot leg; hot leg cold leg; hot leg hot leg; cold leg cold leg; cold leg d. .. d le g; co l d co l co l g; le le g; d 0% .. . 0% ho t l.. . 193008 – Thermal Hydraulics co l ho t g; le ho t © Copyright 2016 0% .. . 0% ho t A. B. C. D. OGF - Polling 10. A reactor coolant system natural circulation cooldown is in progress with steam release from the steam generator (SG) atmospheric steam relief valves (operated in manual control). If high point voiding interrupts natural circulation, which one of the following will occur? (Assume feedwater flow rate, SG relief valve position, and core decay heat level are constant.) © Copyright 2016 193008 – Thermal Hydraulics ... SG le ve lw ill ... lw SG le ve lw ve le SG 0% ill ... 0% ill ... 0% ill lw D. 0% ve C. le B. SG level will increase and SG pressure will increase. SG level will increase and SG pressure will decrease. SG level will decrease and SG pressure will increase. SG level will decrease and SG pressure will decrease. SG A. OGF - Polling