1 00:00:08,130 --> 00:00:09,840 MARKUS KLUTE: Welcome back to 8.701. 2 00:00:09,840 --> 00:00:12,870 So in this lecture, we talk about nuclear fission. 3 00:00:12,870 --> 00:00:16,320 Already seen the process when we discussed 4 00:00:16,320 --> 00:00:19,680 empirical mass formula. 5 00:00:19,680 --> 00:00:22,350 Nuclear fission occurs in very heavy nuclei, 6 00:00:22,350 --> 00:00:26,620 as you can see in this plot here, fission processes, 7 00:00:26,620 --> 00:00:30,210 and this part of the spectrum. 8 00:00:30,210 --> 00:00:33,220 But what happens, and what can happen spontaneously, 9 00:00:33,220 --> 00:00:35,860 is that the parent nuclei just simply breaks up 10 00:00:35,860 --> 00:00:40,270 into daughter nuclei and maybe some additional neutrons. 11 00:00:40,270 --> 00:00:47,170 One example is the decay of uranium 238. 12 00:00:47,170 --> 00:00:49,360 One can also induce fission. 13 00:00:49,360 --> 00:00:53,710 Here, is a plot of the nuclear potential with the Coulomb 14 00:00:53,710 --> 00:00:54,880 [? law ?] here. 15 00:00:54,880 --> 00:00:58,990 And for example, you have this nuclei which sits here-- 16 00:00:58,990 --> 00:01:02,290 and this could be uranium 238-- 17 00:01:02,290 --> 00:01:07,370 and you are able to bring it above this activation 18 00:01:07,370 --> 00:01:08,920 and energy. 19 00:01:08,920 --> 00:01:13,600 Again, this can, in some nuclei, occur spontaneously, in others, 20 00:01:13,600 --> 00:01:14,800 it's being induced. 21 00:01:14,800 --> 00:01:17,320 And then you just break up the two, 22 00:01:17,320 --> 00:01:21,390 break up the nuclei into two daughter particles. 23 00:01:21,390 --> 00:01:23,462 So if you, for example, start with a neutron 24 00:01:23,462 --> 00:01:24,920 and you just bring it close-- let's 25 00:01:24,920 --> 00:01:30,240 say you bring a neutron close to uranium 235. 26 00:01:30,240 --> 00:01:32,870 This forms uranium 236. 27 00:01:32,870 --> 00:01:36,210 And the fact that the neutron is being absorbed excites, 28 00:01:36,210 --> 00:01:39,350 then, this zero-kinetic energy neutron 29 00:01:39,350 --> 00:01:42,860 excite the daughter compound nucleus. 30 00:01:42,860 --> 00:01:45,140 There's an excitation [INAUDIBLE] in this case, 31 00:01:45,140 --> 00:01:47,960 of 6.5 MeV. 32 00:01:47,960 --> 00:01:51,050 And because of that, it then quickly undergoes fission. 33 00:01:51,050 --> 00:01:55,250 So we basically add its thermal, or zero-kinetic energy neutron, 34 00:01:55,250 --> 00:01:59,900 and when it's being absorbed it immediately 35 00:01:59,900 --> 00:02:03,110 causes the fission process. 36 00:02:03,110 --> 00:02:06,080 The fission fragments then carry away some energy-- 37 00:02:06,080 --> 00:02:09,380 in this example, here, it's about 180 MeV-- 38 00:02:09,380 --> 00:02:11,700 and additional prompt neutrons. 39 00:02:11,700 --> 00:02:13,460 And so those additional prompt neutrons, 40 00:02:13,460 --> 00:02:17,270 depending on the specific decay process, 41 00:02:17,270 --> 00:02:19,760 the number can be varying between zero and six, 42 00:02:19,760 --> 00:02:24,820 and for uranium 235, the average number is 2.5. 43 00:02:24,820 --> 00:02:27,340 And then the fragments, they might 44 00:02:27,340 --> 00:02:30,320 undergo additional decay process, maybe better decays, 45 00:02:30,320 --> 00:02:32,570 alpha decays. 46 00:02:32,570 --> 00:02:35,230 And when they do that, they can also 47 00:02:35,230 --> 00:02:37,990 release additional neutrons. 48 00:02:37,990 --> 00:02:40,540 So interesting, now, is to see whether or not 49 00:02:40,540 --> 00:02:44,110 there can be a self-sustained reaction, a chain reaction. 50 00:02:44,110 --> 00:02:46,690 And whether or not this occurs depends on the number 51 00:02:46,690 --> 00:02:49,480 of neutrons being emitted. 52 00:02:49,480 --> 00:02:51,580 So if the number of neutrons produced 53 00:02:51,580 --> 00:02:55,570 in the n plus first stage of the fission process 54 00:02:55,570 --> 00:02:58,000 is greater than the number of neutrons produced in the nth 55 00:02:58,000 --> 00:03:01,720 stage of the process, the process 56 00:03:01,720 --> 00:03:03,760 is either critical or super critical, 57 00:03:03,760 --> 00:03:06,490 which means that it is able to, because it produces more 58 00:03:06,490 --> 00:03:08,110 neutrons and it needs to continue 59 00:03:08,110 --> 00:03:11,920 to have a fission process, it will add or create 60 00:03:11,920 --> 00:03:12,910 a chain reaction. 61 00:03:12,910 --> 00:03:17,800 If the number is less than 1, the process will die out. 62 00:03:17,800 --> 00:03:22,480 And this is exactly what's used in nuclear fission reactors. 63 00:03:22,480 --> 00:03:28,060 There's several types of reactors available. 64 00:03:28,060 --> 00:03:29,710 The example I want to discuss here 65 00:03:29,710 --> 00:03:32,860 very briefly is the one of a thermal reactor which 66 00:03:32,860 --> 00:03:36,730 uses uranium as fuel and low-energy neutrons 67 00:03:36,730 --> 00:03:40,260 to establish the chain reaction, as we just discussed. 68 00:03:40,260 --> 00:03:42,200 And so this is a sketch here. 69 00:03:42,200 --> 00:03:44,610 And the sketch has three different elements. 70 00:03:44,610 --> 00:03:46,520 The first one is a fuel element. 71 00:03:46,520 --> 00:03:51,140 The fuel element can be naturally-occurring uranium. 72 00:03:51,140 --> 00:03:53,960 And then, we have a moderator material. 73 00:03:53,960 --> 00:03:56,540 And the purpose of the moderator material 74 00:03:56,540 --> 00:03:59,580 is to slow the neutrons down. 75 00:03:59,580 --> 00:04:04,040 So if you really start from naturally-occurring uranium, 76 00:04:04,040 --> 00:04:12,710 you might have to find some sort of material which 77 00:04:12,710 --> 00:04:15,620 allows you to efficiently slow down the neutrons 78 00:04:15,620 --> 00:04:19,820 when they're being emitted in the fusion process. 79 00:04:19,820 --> 00:04:22,280 And this could be, so-called, heavy water, 80 00:04:22,280 --> 00:04:27,550 where the hydrogen in water is replaced in part 81 00:04:27,550 --> 00:04:30,590 that leaves this deuterium. 82 00:04:30,590 --> 00:04:33,630 But there's other examples for this as well. 83 00:04:33,630 --> 00:04:37,130 And then, you have those very important retractable rods. 84 00:04:42,210 --> 00:04:44,820 They are materials which have a large cross-section 85 00:04:44,820 --> 00:04:46,800 to capture neutrons. 86 00:04:46,800 --> 00:04:51,300 And so what you can do with them by mechanically adding them 87 00:04:51,300 --> 00:04:54,930 or removing them from this environment, 88 00:04:54,930 --> 00:04:58,410 is you can remove additional neutrons. 89 00:04:58,410 --> 00:05:03,570 So what you're trying to do is control this number k here, 90 00:05:03,570 --> 00:05:06,930 control whether or not there's enough neutrons available 91 00:05:06,930 --> 00:05:09,960 in order to sustain the chain reaction. 92 00:05:09,960 --> 00:05:14,490 And then, the excess energy is converted in heat. 93 00:05:14,490 --> 00:05:16,890 You can, for example, heat up water and then just 94 00:05:16,890 --> 00:05:20,810 have a turbine run in order to produce energy.