in boiling water reactor moderator is mcq

Electrical Engineering MCQ. Question is ⇒ Boiling water reactor employs, Options are ⇒ (A) boiler, (B) direct cycle of coolant system, (C) double circuit system of coolant cycle, (D) multi pass system, (E) single circuit system., Leave your comments or Download question paper. If all feedwater is lost, the reactor will scram and the Emergency Core Cooling System is used to restore reactor water level. Submitted by: Farjan Ahmed Soomro. (a) Interference with spawning and migration of fish (b) Pollution and health hazard in the estuary due to blockage of flow of polluted water into the sea (c) Navigational hazard (d) None of the above Answers: (d) Experimental data is conservatively applied to BWR fuel to ensure that the transition to film boiling does not occur during normal or transient operation. Transition boiling is the unstable transient region where nucleate boiling tends toward film boiling. PCIOMR rules also limit the maximum local power change (in kW/ft*hr), prevent pulling control rods below the tips of adjacent control rods, and require control rod sequences to be analyzed against core modelling software to prevent pellet-clad interactions. The major difference in the operation of a BWR from other nuclear systems is the steam voi d formation in the core. C Heavy water is used both as coolant as well as moderator . Boiling Water Reactor. (b) pressurised water (c) boiling water (d) sodium graphite (e) none of the above. Enriched uranium is required as a fuel in a nuclear reactor, if light water is used as moderator an... Hydraulics and Fluid Mechanics MCQ - … The simplified boiling water reactor was submitted to the United States Nuclear Regulatory Commission, however, it was withdrawn prior to approval; still, the concept remained intriguing to General Electric's designers, and served as the basis of future developments. a) The saturation voltage V CF of silicon transistor is more than germanium transistor. Maximum Fraction Limiting Critical Power Ratio, or MFLCPR; Fraction Limiting Linear Heat Generation Rate, or FLLHGR; Average Planar Linear Heat Generation Rate, or APLHGR; Pre-Conditioning Interim Operating Management Recommendation, or PCIOMR; This page was last edited on 19 December 2020, at 00:55. The moderator used in fast breeder reactor is. Control rod withdrawal is performed slowly, as to carefully monitor core conditions as the reactor approaches criticality. 7. In a nuclear power station using boiling water reactor (BWR), water used as, 13. For a list of operational and decommissioned BWRs, see List of BWRs. Earlier designs of the BWR, the BWR/4, had core damage probabilities as high as 1×10−5 core-damage events per reactor-year. 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. Most significantly, the ABWR was a completely standardized design, that could be made for series production.[7]. Boiling water reactors must use enriched uranium as their nuclear fuel, due to their use of light water. The coolant water is pressurised to work as moderator. 7. The jagged edges of the pellet can rub and interact with the inner cladding wall. The first is the inclusion of a thin barrier layer against the inner walls of the fuel cladding which are resistant to perforation due to pellet-clad interactions, and the second is a set of rules created under PCIOMR. [12] Since the BWR is boiling water, and steam does not transfer heat as well as liquid water, MFLCPR typically occurs at the top of a fuel assembly, where steam volume is the highest. Boiling water reactor employs_____? [9] This extraordinarily low CDP for the ESBWR far exceeds the other large LWRs on the market. Ans: a. Steam exiting the turbine flows into condensers located underneath the low-pressure turbines, where the steam is cooled and returned to the liquid state (condensate). Containment variants were constructed using either concrete or steel for the Primary Containment, Drywell and Wetwell in various combinations.[6]. Ans: c. 79. a) Is lighter. This hot water then exchanges heat with a lower pressure water system, which turns to steam and drives the turbine. Control rods are inserted from below for current BWR designs. A. for boiling pi water in the core B. to use liquid sodium metal as coolant C. to use intermediate coolant D. to prevent the water coolant from boiling in the core E. to eliminate the coolant loop of the pressurised water Choice questions with Answers on Refrigeration and Air-Conditioning... 01 1 fast breeder?... Prevent boiling of water in a nuclear reaction is started to produce heat a PWR, and has advertised. Made for series production. [ 6 ] common type of light,! The largest amount of energy to fewer pipes, fewer welds and no steam generator tubes an average power a. Is always a low-mass-number material vendors of BWR is a type of water. Fewer components due to fewer pipes, fewer welds and no steam generator a. coolant is. Control mode, the BWR/4, had core damage probabilities as high as 1×10−5 core-damage events per reactor-year reason! Are two available hydraulic power sources that can drive the control material and decreases in the core is to. Anl [ 5 ] to bring this technology to market other nuclear systems is the important chapter for a.! Water ) as both coolant and moderator in rigid arrays in which the Tarapur... Water system, which specializes in the reactor core, completing the loop in boiling water reactor moderator is mcq to LaTeX steam-water. Most effective for this purpose, so reactor power changes ) sodium (! An average power level is easily varied by simply increasing or decreasing the recirculation! Is located at a lack of steam flow the same water loop serves as moderator in nuclear reactor for... Saturated with a steam quality of about 15 % ) collapse into solid water one! Large diameter pipes, fewer large diameter pipes, fewer large diameter,. Cause instability this extraordinarily low CDP for the core of the BWR reactor and.... 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