Fundamentals Of Physics - Volume 1 Only
11th Edition
ISBN: 9781119306856
Author: Halliday
Publisher: WILEY
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Chapter 43, Problem 22P
To determine
To calculate:
the number of free neutrons present in a given reactor at any moment of time.
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A reactor operates at 400 MW with a neutron generation time of 30.0 ms. If its power increases for 5.00 min with a multiplication factor of 1.0003, what is the power output at the end of the 5.00 min?
The neutron generation time of a particular reactor is 1.3 ms.The reactor is generating energy at the rate of 1200.0 MW.To perform certain maintenance checks, the power level must temporarily be reduced to 350.00 MW. It is desired that the transition to the reduced power level take 2.6000 s. To what (constant) value should the multiplication factor be set to effect the transition in the desired time?
4. A multiplying medium has a neutron population of 1.0 x 1012 neutrons
per cubic centimeter at time t = 10 seconds. At time t = 35 seconds,
the neutron population is 6.3 x 104 neutrons per cubic centimeter.
(a) What is the period in this system?
(b) If the neutron lifetime is 0.02 seconds, what is the multiplication
factor in this medium?
Chapter 43 Solutions
Fundamentals Of Physics - Volume 1 Only
Ch. 43 - Prob. 1QCh. 43 - Prob. 2QCh. 43 - Prob. 3QCh. 43 - Prob. 4QCh. 43 - Prob. 5QCh. 43 - Prob. 6QCh. 43 - Prob. 7QCh. 43 - Which of these elements is not cooked up by...Ch. 43 - Prob. 9QCh. 43 - Prob. 10Q
Ch. 43 - Prob. 11QCh. 43 - Prob. 12QCh. 43 - Prob. 1PCh. 43 - Prob. 2PCh. 43 - Prob. 3PCh. 43 - Prob. 4PCh. 43 - Prob. 5PCh. 43 - Prob. 6PCh. 43 - Prob. 7PCh. 43 - Prob. 8PCh. 43 - Prob. 9PCh. 43 - Prob. 10PCh. 43 - Prob. 11PCh. 43 - Prob. 12PCh. 43 - Prob. 13PCh. 43 - Prob. 14PCh. 43 - Prob. 15PCh. 43 - Prob. 16PCh. 43 - Prob. 17PCh. 43 - Prob. 18PCh. 43 - Prob. 19PCh. 43 - Prob. 20PCh. 43 - Prob. 21PCh. 43 - Prob. 22PCh. 43 - Prob. 23PCh. 43 - Prob. 24PCh. 43 - SSM a A neutron of mass mn and kinetic energy K...Ch. 43 - Prob. 26PCh. 43 - Prob. 27PCh. 43 - Prob. 28PCh. 43 - Prob. 29PCh. 43 - Prob. 30PCh. 43 - Prob. 31PCh. 43 - Prob. 32PCh. 43 - Prob. 33PCh. 43 - Prob. 34PCh. 43 - Prob. 35PCh. 43 - Prob. 36PCh. 43 - Prob. 37PCh. 43 - Prob. 38PCh. 43 - Prob. 39PCh. 43 - Prob. 40PCh. 43 - Prob. 41PCh. 43 - Prob. 42PCh. 43 - Prob. 43PCh. 43 - Prob. 44PCh. 43 - Prob. 45PCh. 43 - Prob. 46PCh. 43 - SSM WWW Coal burns according to the reaction...Ch. 43 - Prob. 48PCh. 43 - Prob. 49PCh. 43 - Prob. 50PCh. 43 - Prob. 51PCh. 43 - Prob. 52PCh. 43 - Prob. 53PCh. 43 - Prob. 54PCh. 43 - Prob. 55PCh. 43 - Prob. 56PCh. 43 - Prob. 57PCh. 43 - Prob. 58P
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- (a) Calculate the energy released in the neutroninduced fission reaction n+239Pu96Sr+140Ba+4n, given m(96Sr)=95.921750u and m(140Ba)=139.910581u. (b) Confirm that the total number of nucleons and total charge are conserved in this reaction.arrow_forwardWhat is the dose in mSv for: (a) a 0.1 Gy xray? (b) 2.5 mGy of neutron exposure to the eye? (c) 1.5 mGy of exposure?arrow_forward(a) Calculate the energy released in the neutron- induced fission n+238U96Sr+140Xe+3n , given m(96Sr)=95.921750uand m(140Xe)=139.92164 . This result is about 6 MeV greater than the result for spontaneous fission. Why? Confirm that the total number of nucleons and total charge are conserved in this reaction.arrow_forward
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- For neutron moderation by helium, make a sketch showing the average energy of a beam of initial 2.0 MeV neutrons as a function of time, assuming the mean time between collisions is t. How long does it take for the neutrons to loose 50% of their energy? How long for 90%?arrow_forwardA large power reactor that has been in operation for some months is turned off, but residual activity in the core still produces 135 MW of power. If the average energy per decay of the fission products is 1.04 MeV, what is the core activity in units of curies?arrow_forwardHow many kilograms m of uranium-235 must completely fission spontaneously into 140Xe, 92Sr, and three neutrons to produce 1200 MW of power continuously for one year, assuming the fission reactions are 26% efficient? m = ? kgarrow_forward
- A fast reactor is fueled with plutonium 239Pu and has capture-to-fission ratio of 0.070. The fission recoverable energy from 239Pu is 210 MeV per fission. Calculate the plutonium consumption rates in g/MWd.arrow_forwardCharacteristic nuclear time is a useful but loosely defined quantity, taken to be the time required for a nucleon with a few million electron-volts of kinetic energy to travel a distance equal to the diameter of a middle-mass nuclide.What is the order of magnitude of this quantity? Consider 5 MeV neutrons traversing a nuclear diameter of 197Auarrow_forwardThe neutron generation time tgen in a particularreactor is 1.0 ms. If the reactor is operating at a power levelof 500 MW, about how many free neutrons are present in the reactorat any moment?arrow_forward
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