B. Rouben McMaster University 4D03/6D03 Nuclear Reactor Analysis 2016 Sept.-Dec. Assignment 6 Assigned 2016/11/09 Due by 2016/11/16 11:00 am 6 Problems (only 5 to be marked) Total: 48 marks 1. [Not for marking] A 235U-fuelled reactor originally operating at a constant power of 0.5 milliwatt is placed on a constant positive reactor period. It reaches its full power of 90 megawatt within 4 hours and 23 minutes. What was the reactor period? (b) Starting from full power, the same reactor was then subjected to a reactor period of -1.5 minutes. When will the power reach 2 W? Solution: Powert P0et / T (a) where P0 initial power and T reactor period ( from definition of period ) (a ) Here P0 0.001 W When t 4h 23 min 263 min, Power (t ) 90MW 90 M W 0.001 W * e 263 min/ T T 263 min 90 *106 W ln 0.001 W 263 min 10.43 min 25.223 (b) Here P0 90 MW , T 1.5 min, and P(t ) 2 W t 2 W 90 M W exp 1.5 min 2W t 1.5 min * ln 26.4 min 6 90 *10 W 2. [10 marks] Consider a homogeneous, bare cylindrical reactor with diameter 6.1 m and height 6.6 m. In 1 energy group its average properties are: = 2.39, f = 0.00125 cm-1, a = 0.00312 cm-1, D=0.98 cm. [Note: neglect the extrapolation distance.] If the 1-group neutron speed is 2,255 m/s, calculate the neutron generation time and the prompt-neutron lifetime l*. [You will need to calculate keff for the reactor.] If there were no delayed neutrons, what would be the reactor period? Solution: 2 2 2.405 3.1415 5 2 B2 8.483 *10 cm 305 660 f 2.39 * 0.00125 k eff 0.9327 2 DB a 0.98 * 8.483 *10 5 0.00312 1 1 1 1 0.00722 k eff 0.9327 1 1 0.00148 s f 2.39 * 0.00125 cm 1 * 2255 m / s * 1 1 0.00138 s 5 DB a 0.98 * 8.483 *10 0.00312 cm 1 * 2255 m / s 2 If there were no delayed neutrons, the flux or power would evolve as t 0.00722 t e e 0.00148 e 48.63t , where t is in sec onds keff 1 (or , equivalently , it will evolve as e * t e 0.93271 t 0.00138s e 48.63t ) Without delayed neutrons, we would therefore have Re actor period 1 s 0.0206 s negative period , sin ce 0 . 48.63 3. [10 pts: 2 each for a) and c), 3 each for b) and d)] The average following values are given for a certain critical reactor: p = 2.23 d = 0.014 f = 0.004 cm-1 = 2.3 km/s There is one group of delayed-neutron precursors, with = 0.12 s-1. This reactor is suddenly subjected to a reactivity insertion of 100 pcm. a) Calculate the delayed-neutron fraction. Solution: p d 2.23 0.014 2.244 d 0.014 0.00624 2.244 b) Calculate the approximate exponents in the exponential terms for the evolution of the power. Solution: 100 pcm 1 mk 0.001 Delayed neutron fraction 1 0.12 s 1 * 0.001 0.00012 s 1 0.0229 s 1 0.00624 0.001 0.00524 Neutron generation time 2 1 1 4.844 *10 4 s 1 1 f 1 2.244 * 0.004 cm * 230,000 cm.s 0.001 0.00624 10.82 s 1 4.844 *10 4 s Note huge difference in order of magnitude between 1 and 2 . c) Calculate the approximate power at 10 s (taking initial power equal to unity). Solution: 1t 2t Power t e e 1.191e 0.0229*10 0.191e 10.82*10 The 2nd exp onential is totally negligible Power 10 s 1.191e 0.229 1.59 d) What would the power at 10 s have been without delayed neutrons? Solution: Without delayed neutrons, Powert e t Power10 s e 0.001*10 s 4.844*10 4 s Hallelujah for delayed neutrons! e 20.64 9.2 *108 !!! 4. [8 pts: 4 for a), 4 for b)] Consider a reactor with 1 delayed-neutron-precursor group, with = 0.02 s-1. The reactor shutdown system can insert -80 mk essentially instantaneously. Following the actuation of the shutdown system, it is found that the reactor is on a stable period of -52 s. a) Evaluate the delayed-neutron fraction. Solution: 1 The stable period 52 s 1 0.080 0.02 s 1 * ( 0.080) 52 s 52 * 0.0016 0.080 0.0832 0.080 0.0032 b) If the reactor started at neutron power of 730 MW, what is the neutron power 5 s after actuation of the shutdown system? Solution: Following the decay of the exp onential with exp onent 2 , the equation for the (relative) power is t Pt e P0 P5s 0.0032 e P0 0.0032 0.080 0.02 s 1 *(0.080) *5 s 0.0032 0.080 0.008 0.0032 0.0832 e 0.0832 0.0384615 e 0.0961538 0.0384615 * 0.908324 0.0349 [ 3.49%] P5s 0.0349 * 730 MW 25.5 MW 5. [8 pts: 4 for a), 4 for b)] Consider a reactor with 1 delayed-neutron-precursor group, with a delayed-neutron fraction of 0.0056 and = 0.05 s-1. The reactor is running in steady-state critical at a neutron power of 1 (arbitrary units), when an unknown perturbation suddenly inserts some positive reactivity, and the neutron power jumps to a value of 1.1. a) What was the reactivity inserted by the perturbation? Solution: U sin g the prompt jump approximation : 0.0056 1 .1 1 .1 0.0056 0.0056 0.0056 0.000509 0.51 mk 1 .1 b) If the perturbation is not countered, when will the neutron power reach 1.3? Solution: The evolution of the power is P t e t 1.1e 0.05 s 1 *( 0.000509) t(s) 0.0056 0.000509 1.1e 0.00500t The time at which the power reaches 1.3 satisfies 1.3 1.1 e 0.005t 1.3 0.005t ln 1.1 0.005t ln 1.1818 t 0.167054 s 33.41 s 0.005 6. [12 marks} A reactor has 1 precursor of delayed neutrons. The precursor has half-life 96 s. The reactor is in steady state at a power of 1.000 (arbitrary units). Then, starting at t = 0, an instantaneous reactivity was inserted and kept constant. The power increased and was found to be 1.823 at t = 5s. If the reactivity insertion had been only 1/3 of the value it was in the description above, what value would the power have reached at t = 5 s? Solution: The decay cons tan t of the precursor group is given by ln 2 0.00722 028 s 1 96 s By t 5s we know we can ignore the 2 term, and we can write P (t ) P (0) * e t i.e., P5s 1.823 1 * e 0.00722028s 1 * *5 s Note that the right hand side can be written in terms of sin gle var iable , say x 0.036101x 1 In terms of x, 1.823 e 1 x 1 x This is a transcendental equation and can be solved by trial and error or by Newton' s method. I found x 0.435934. Now u sin g 1 / 3 of this value, i.e., x 0.145311, we find P (5s ) 1.1772
© Copyright 2026 Paperzz