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Chemical Engineering Basics MCQ with detailed explanation for interview, ... B Fuel cost is much lower than that used in pressurised water or boiling water reactor . Boiling water reactor uses the following as moderator, coolant and working fluid_____? In boiling water reactor, moderator is . Enriched uranium is required as a fuel in a nuclear reactor, if light water is used as moderator and coolant, because light water has (A) High neutron absorption cross-section (B) Low moderating efficiency (C) High neutron scatter cross-section (D) Low neutron absorption cross-section Answer: Option B 02. 2. Submitted by: Farjan Ahmed Soomro. Normally the fuel rods are kept sufficiently cool in the reactor and spent fuel pools that this is not a concern, and the cladding remains intact for the life of the rod. Page-7 section-2 Learn Power Plant Engineering MCQ questions & answers are available for a Mechanical Engineering students to clear GATE exams, various technical interview, competitive examination, and another entrance exam. Ans: d. 8. During the first nuclear heatup, nuclear fuel pellets can crack. Power Plant Engineering MCQ with detailed explanation for interview, ... A moderator, apart from its high neutron slowing power, and low non-productive neutron, should be . So as to prevent this from happening, it is required that the decay heat stored in the fuel assemblies at any one time does not overwhelm the ECCS. The Navy, seeing the possibility of turning submarines into full-time underwater vehicles, and ships that could steam around the world without refueling, sent their man in engineering, Captain Hyman Rickover to run their nuclear power program. As a result, GE developed a set of rules in 1977 called BPWS (Banked Position Withdrawal Sequence) which help minimize the effect of any single control rod movement and prevent fuel damage in the case of a control rod drop accident. C. The coolant water is pressurised to prevent boiling of water in the core. He found that it was, after subjecting his reactors to quite strenuous tests, proving the safety principles of the BWR.. Ans: c 35. c) Tarapur. A. coolant water is allowed to boil in the core of the reactor. Physicists calculate with fission cross-section, which determines this probability. Answer/ Hint Bottom entry control rods also permit refueling without removal of the control rods and drives, as well as testing of the control rod systems with an open pressure vessel during refueling. 12. The BWR uses ordinary water (light water) as both its coolant and its moderator. In other words, steam semi-insulates the heated surface and surface temperature rises to allow heat to get to the cooling fluid (through convection and radiative heat transfer). A BWR may be designed to operate using only natural circulation so that recirculation pumps are eliminated entirely. When operating on the so-called "100% rod line," power may be varied from approximately 30% to 100% of rated power by changing the reactor recirculation system flow by varying the speed of the recirculation pumps or modulating flow control valves. This advantage is partially offset by the fact that hydraulic forces provide much greater rod insertion forces than gravity, and as a consequence, BWR control rods are much less likely to jam in a partially inserted position due to damage to the control rod channels in a core damage event. Ans: a. Multiple Choice Questions with Answers on Refrigeration and Air-Conditioning ... 01 1. But other researchers wanted to investigate whether the supposed instability caused by boiling water in a reactor core would really cause instability. 3. 5. A. a) The saturation voltage V CF of silicon transistor is more than germanium transistor. The coolant water is pressurised to work as moderator. Then, either all of the A control rods or B control rods are pulled full out in a defined sequence to create a "checkerboard" pattern. If all feedwater is lost, the reactor will scram and the Emergency Core Cooling System is used to restore reactor water level. c) Breeder reactor. The BWR uses ordinary water (light water) as both its coolant and its moderator. Typical computer simulations divide the reactor core into 24–25 axial planes; relevant quantities (margins, burnup, power, void history) are tracked for each "node" in the reactor core (764 fuel assemblies x 25 nodes/assembly = 19100 nodal calculations/quantity). A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. A newer design of BWR is known as the advanced boiling water reactor (ABWR). There are two available hydraulic power sources that can drive the control rods into the core for a BWR under emergency conditions. Which element is used as moderator in nuclear reactor? (d) to prevent the water coolant from boiling in the core (e) to eliminate the coolant loop of the pressurised water. The coolant is kept at a lower pressure than in a PWR (about 7 MPa or 1 000 psi) allowing the coolant to boil as it receives heat from the reactor. The enriched uranium is packed into fuel rods, which are assembled … A typical fuel cycle lasts 18–24 months, with about one third of fuel assemblies being replaced during a refueling outage. The fact that the fuel rods' cladding is a zirconium alloy was also problematic since this element can react with steam at extreme temperatures to produce hydrogen, which can ignite with oxygen in the air. This is done through uranium enrichment—which increases the concentration of Uranium-235 from 0.7% to around 4%. BWR designs incorporate failsafe protection systems to rapidly cool and make safe the uncovered fuel prior to it reaching this temperature; these failsafe systems are known as the Emergency Core Cooling System. Ans: a . Answer/ Hint Research into nuclear power in the US was led by the 3 military services. a) Boiling water. In a nuclear power station using boiling water reactor (BWR), water used as. (c) boiling water (d) sodium graphite (e) none of the above. b) Pressurized water. This concern led to the US's first research effort in nuclear power being devoted to the PWR, which was highly suited for naval vessels (submarines, especially), as space was at a premium, and PWRs could be made compact and high-power enough to fit in such, in any event. Their approach is to simulate worst case events when the reactor is in its most vulnerable state. The ECCS is designed to rapidly flood the reactor pressure vessel, spray water on the core itself, and sufficiently cool the reactor fuel in this event. (c) boiling water (d) sodium graphite (e) none of the above. APLHGR, being an average of the Linear Heat Generation Rate (LHGR), a measure of the decay heat present in the fuel bundles, is a margin of safety associated with the potential for fuel failure to occur during a LBLOCA (large-break loss-of-coolant accident – a massive pipe rupture leading to catastrophic loss of coolant pressure within the reactor, considered the most threatening "design basis accident" in probabilistic risk assessment and nuclear safety and security), which is anticipated to lead to the temporary exposure of the core; this core drying-out event is termed core "uncovery", for the core loses its heat-removing cover of coolant, in the case of a BWR, light water. This limit ensures that the centerline temperature of the fuel pellets in the rods will not exceed the melting point of the fuel material (uranium/gadolinium oxides) in the event of the worst possible plant transient/scram anticipated to occur. Containment variants were constructed using either concrete or steel for the Primary Containment, Drywell and Wetwell in various combinations.. D. No moderate is used. These mock fuel assemblies are put into a test stand where data points are taken at specific powers, flows, pressures. Take the Quiz for competitions and exams. Subsequently, numerous ABWRs were built in Japan. This contains 20 Multiple Choice Questions for Mechanical Engineering Nuclear Power Plant - MCQ Test 1 (mcq) to study with solutions a complete question bank. Parallel to the development of the ABWR, General Electric also developed a different concept, known as the simplified boiling water reactor (SBWR). Q3. BWRs contain multiple safety systems for cooling the core after emergency shut down. The saturated steam that rises above the separator is dried by a chevron dryer structure. Heat is produced by nuclear fission in the reactor core, and this causes the cooling water to boil, producing steam.  This extraordinarily low CDP for the ESBWR far exceeds the other large LWRs on the market. To illustrate the response of LHGR in transient imagine the rapid closure of the valves that admit steam to the turbines at full power. For this reason the spent fuel storage pools are above the reactor in typical installations. Which among the following is not an adverse environmental impact of tidal power generation? C. The coolant water is pressurised to prevent boiling of water in the core. In a PWR, the reactor core heats water, which does not boil. Boiling water reactor uses the following as moderator, coolant and working fluid (a) ordinary fluid (b) heavy water (c) molten lead (d) hydrogen gas (e) none of the above. At this power level a single feedwater pump can maintain the core water level. Ans: c. 35. Most of the radioactivity in the water is very short-lived (mostly N-16, with a 7-second half-life), so the turbine hall can be entered soon after the reactor is shut down. 1) coolant water boils in the core of the reactor., 2) fuel is natural uranium and heavy water acts both as moderator & coolant., 3) use of moderator is not required, 4) coolant water is pressurised to prevent bulk boiling of water in the core, 5) NULL Approximately 22% of the nuclear reactors installed in the different nuclear power plants use the BWR reactor.. PCIOMR analysis look at local power peaks and xenon transients which could be caused by control rod position changes or rapid power changes to ensure that local power rates never exceed maximum ratings. Several calculated/measured quantities are tracked while operating a BWR: MFLCPR, FLLHGR, and APLHGR must be kept less than 1.0 during normal operation; administrative controls are in place to assure some margin of error and margin of safety to these licensed limits. Categories Mechanical Engineering MCQs Post navigation. The first generation of production boiling water reactors saw the incremental development of the unique and distinctive features of the BWR: the torus (used to quench steam in the event of a transient requiring the quenching of steam), as well as the drywell, the elimination of the heat exchanger, the steam dryer, the distinctive general layout of the reactor building, and the standardization of reactor control and safety systems. `` BWR '' redirects here which their geometry is controlled by the decay. Cause its power to 100 % power to rise and so does not boil moisture separators taken! 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