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Principles of naval engineering - Historic Naval Ships Association

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PRINCIPLES OF NAVAL ENGINEERINGthe investigation <strong>of</strong> energy released in thisreaction we find:Mass <strong>of</strong> uranium-235 atom = 235. 0439Mass <strong>of</strong> neutron= 1. 00894Original mass= 236. 05284 amuMass <strong>of</strong> molybdenum-95atom= 94.9058Mass <strong>of</strong> lanthanum- 139atom= 138.9061Mass <strong>of</strong> 2 neutrons= 2.01788Total mass <strong>of</strong> fissionfragmentsMass defect = 236. 05284 -= 235. 82978235. 829780. 22306 amu/ fissionHence,0.22306 amu/fission x 931 Mev/amu207.7 Mev/fissionThus we find that from each fission approximately200 Mev <strong>of</strong> energy is released,most <strong>of</strong> which (about 80 percent) appearsimmediately as kinetic energy <strong>of</strong> the fissionfragments. As the fission fragments slow down,they collide with other atoms and molecules;this results in a transfer <strong>of</strong> velocity to thesurrounding particles. The increased molecularmotion is manifested as sensible heat. The remainingenergy is realized from the decay <strong>of</strong>fission fragments by beta particle and gammaray emission, kinetic energy <strong>of</strong> fission neutrons,and instantaneous gamma ray energy.In a nuclear reactor, the two neutronsliberated in the above reaction are available,under certain conditions, to fission other uraniumatoms and assist in maintaining the reactorcritical . A nuclear reactor is said to becritical if the neutron flux remains constant.Neutron flux is defined as the number <strong>of</strong>neutrons passing through unit area in unittime, A neutron flux <strong>of</strong> 10^3 neutrons persquare centimeter per second is not uncommon.If the neutron flux is decreasing, the reactoris said to be subcritical; conversely, a reactoris supercritical if the neutron flux is increasing.NEUTRON REACTIONSNeutrons may be classified by their energylevels. A fast neutron has an energy level <strong>of</strong>greater than 0.1 Mev, an intermediate neutronin the process <strong>of</strong> slowing down possesses anenergy level between 1 ev and 0.1 Mev, athermal neutron is in thermal equilibrium withits surroundings and has an energy level <strong>of</strong>less than 1 ev.Neutrons lose their kinetic energy by interactingwith atoms in the surrounding area.The probability <strong>of</strong> a neutron interacting withone atom is dependent upon the target areapresented by that atom for a neutron reaction.This target area (which is the probability <strong>of</strong> aneutron reaction occurring) is called crosssection . The unit <strong>of</strong> cross section measurementis barns. The size <strong>of</strong> a barn is 10""square centimeters. Four <strong>of</strong> the different crosssections that an element may have for neutronprocesses are as follows:Scattering cross section is a measure <strong>of</strong> theprobability <strong>of</strong> an elastic (billiard ball) coUisonwith a neutron. In this type <strong>of</strong> collision part <strong>of</strong>the kinetic energy <strong>of</strong> the neutron is imparted tothe atom and the neutron rebounds after collision.Neutrons are thermalized (reduced to anenergy level below 1 ev) by elastic collisions.Capture cross section is a measure <strong>of</strong> theprobability <strong>of</strong> the neutron being captured withoutcausing fission.Fission cross section is a measure <strong>of</strong> theprobability <strong>of</strong> fission <strong>of</strong> the atom after neutroncapture.Absorption cross section is a measure <strong>of</strong> theprobability that an atom will absorb a neutron.The absorption cross section is the sum <strong>of</strong> thecapture cross section and the fission crosssection.The cross section for any given elementmay vary with the energy level <strong>of</strong> the approachingneutron. In the case <strong>of</strong> uranium-235,the absorption cross section for a thermalneutron is 100 times the cross section for afast neutron.REACTOR PRINCIPLESA nuclear reactor must contain a criticalmass. A critical mass contains sufficient fissionablematerial to enable the reactor tomaintain a self-sustaining chain reaction, therebykeeping the reactor critical. A criticalmass is dependent upon the species <strong>of</strong> fissionablematerial, its concentration and puritythe geometry and size <strong>of</strong> the reactor, and thematter surrounding the fissionable material."For a thorough discussion <strong>of</strong> the aspects <strong>of</strong> reactordesign, see Samuel Glasstone, Sourcebook on AtomicEnergy (2d ed.; Princeton: D. Van Nostrand Company,Inc., 1958).620

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