<?xml version="1.0" encoding="UTF-8"?><!DOCTYPE article  PUBLIC "-//NLM//DTD Journal Publishing DTD v3.0 20080202//EN" "http://dtd.nlm.nih.gov/publishing/3.0/journalpublishing3.dtd"><article xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink" dtd-version="3.0" xml:lang="en" article-type="research article"><front><journal-meta><journal-id journal-id-type="publisher-id">AJCM</journal-id><journal-title-group><journal-title>American Journal of Computational Mathematics</journal-title></journal-title-group><issn pub-type="epub">2161-1203</issn><publisher><publisher-name>Scientific Research Publishing</publisher-name></publisher></journal-meta><article-meta><article-id pub-id-type="doi">10.4236/ajcm.2013.31002</article-id><article-id pub-id-type="publisher-id">AJCM-28991</article-id><article-categories><subj-group subj-group-type="heading"><subject>Articles</subject></subj-group><subj-group subj-group-type="Discipline-v2"><subject>Physics&amp;Mathematics</subject></subj-group></article-categories><title-group><article-title>
 
 
  Computational Results on Quadratic Functional Model for the Tokens of Nuclear Safety
 
</article-title></title-group><contrib-group><contrib contrib-type="author" xlink:type="simple"><name name-style="western"><surname>oseph</surname><given-names>Olorunju Omolehin</given-names></name><xref ref-type="aff" rid="aff1"><sup>1</sup></xref><xref ref-type="corresp" rid="cor1"><sup>*</sup></xref></contrib><contrib contrib-type="author" xlink:type="simple"><name name-style="western"><surname>Lukuman</surname><given-names>Aminu</given-names></name><xref ref-type="aff" rid="aff1"><sup>1</sup></xref><xref ref-type="corresp" rid="cor1"><sup>*</sup></xref></contrib><contrib contrib-type="author" xlink:type="simple"><name name-style="western"><surname>Kamilu</surname><given-names>Rauf</given-names></name><xref ref-type="aff" rid="aff1"><sup>1</sup></xref><xref ref-type="corresp" rid="cor1"><sup>*</sup></xref></contrib></contrib-group><aff id="aff1"><addr-line>Department of Mathematics, University of Ilorin, Ilorin, Nigeria</addr-line></aff><author-notes><corresp id="cor1">* E-mail:<email>omolehin_joseph@yahoo.com(OOO)</email>;<email>jubril_aminu@yahoo.co.uk(LA)</email>;<email>krauf@unilorin.edu.ng(KR)</email>;</corresp></author-notes><pub-date pub-type="epub"><day>26</day><month>03</month><year>2013</year></pub-date><volume>03</volume><issue>01</issue><fpage>6</fpage><lpage>15</lpage><history><date date-type="received"><day>August</day>	<month>2,</month>	<year>2012</year></date><date date-type="rev-recd"><day>October</day>	<month>15,</month>	<year>2012</year>	</date><date date-type="accepted"><day>November</day>	<month>25,</month>	<year>2012</year></date></history><permissions><copyright-statement>&#169; Copyright  2014 by authors and Scientific Research Publishing Inc. </copyright-statement><copyright-year>2014</copyright-year><license><license-p>This work is licensed under the Creative Commons Attribution International License (CC BY). http://creativecommons.org/licenses/by/4.0/</license-p></license></permissions><abstract><p>
 
 
   In this work, Nuclear Reactor safety was modeled inform of quadratic functional. The nuclear tokens are structured and used as elements of the control matrix operator in our quadratic functional. The numerical results obtained through Conjugate Gradient Method (CGM) algorithm identify the optimal level of safety required for Nuclear Reactor construction at any particular situation. 
 
</p></abstract><kwd-group><kwd>Control Operator; Nuclear Tokens; CGM Algorithm; Optimal</kwd></kwd-group></article-meta></front><body><sec id="s1"><title>1. Introduction</title><p>Nuclear reactors accidents occur when the coolant ceases to work, the reactor will be overheated and produced excess heat in form of steam. Most of the internal component of the reactors are made from zirconium in zircalloy cladding used in fuel rods oxidizes in reaction with steam to produce zirconium oxide and hydrogen [<xref ref-type="bibr" rid="scirp.28991-ref1">1</xref>]. When mixed with air, hydrogen is flammable and its detonation will destroy the containment structure which house the reactor. As a result of this, radiation is released to the surrounding causing environmental hazard [2-5]. This work derived the equations for the rate of heat of different reactors from energy balance equations. These equations are structured in parametric form to obtain the basis of the mathematical model solvable by the Conjugate Gradient Method (CGM) algorithm. The obtained numerical results generate the minimal disaster associated with nuclear reactors.</p></sec><sec id="s2"><title>2. Energy Balance</title><p>The following results were obtained through Energy Balance Equations. See [<xref ref-type="bibr" rid="scirp.28991-ref6">6</xref>]. For the purpose of our study, we shall arrange the equations in terms of the rate of heat.</p><sec id="s2_1"><title>2.1. The Energy Balance for Chemical Reactors</title><p>Let us consider arbitrary reactor volume element. From the conservation of energy for a reactor system we obtain the following:</p><disp-formula id="scirp.28991-formula48965"><label>(1)</label><graphic position="anchor" xlink:href="2-1100142\4e9d8d59-7ecc-4b9f-b07b-797516120850.jpg"  xlink:type="simple"/></disp-formula><p>Equation (1) can be represented mathematically as:</p><disp-formula id="scirp.28991-formula48966"><label>(2)</label><graphic position="anchor" xlink:href="2-1100142\b19d1076-3d19-4532-b1c1-513aa662b1ae.jpg"  xlink:type="simple"/></disp-formula><p>where <img src="2-1100142\c21992e7-26c0-4453-adeb-64f95717858a.jpg" /> means energy per unit mass, <img src="2-1100142\ea818922-b8a9-4ace-86b6-98a93527115c.jpg" />is the mass inflow, <img src="2-1100142\ba6ad6a7-e326-4bcd-93f7-7f06bf79eb0d.jpg" />is the mass outflow and <img src="2-1100142\e86ac706-cb92-4cb2-ba02-461c8018d462.jpg" /> is the rate of heat.</p><p>The total rate of work done on a reactor system is expressed as follows:</p><disp-formula id="scirp.28991-formula48967"><label>(3)</label><graphic position="anchor" xlink:href="2-1100142\18f1f4e3-4060-4eb3-98ab-f7c9e0de1dc5.jpg"  xlink:type="simple"/></disp-formula><p>where <img src="2-1100142\1c1236c8-88bc-45ea-8909-4a0ce66c30e5.jpg" /> = total rate of work done,</p><p><img src="2-1100142\5fac57d0-85f4-4566-bb4b-ffc49cb63e7b.jpg" />= rate of work done by flowstream</p><p><img src="2-1100142\a1b67bbf-7f24-4740-9511-4d3074d9c56b.jpg" />= rate of work done by shaft</p><p><img src="2-1100142\c3e64b28-6617-4b3f-8b72-30ca1edb87a3.jpg" />= rate of work done by boundary The Rate of work done Flowstream can be represented by <img src="2-1100142\48dd12c6-f6cc-4a3f-a5be-3244931f5e6a.jpg" /> such that</p><disp-formula id="scirp.28991-formula48968"><label>(4)</label><graphic position="anchor" xlink:href="2-1100142\8f447498-e032-4e53-beb9-be47b88ef4bf.jpg"  xlink:type="simple"/></disp-formula><p>where <img src="2-1100142\0c6c6327-d4a8-40d7-9918-6ea23f00f5c5.jpg" /> = area of reactor (inflow), <img src="2-1100142\59b126a7-a527-4f77-9491-d7960df64764.jpg" />= area of reactor (outflow), <img src="2-1100142\66aa22b5-aa39-407c-83a6-0330756e3bc9.jpg" />= inflow volume of reactor, <img src="2-1100142\885bf563-9ebe-4654-a88a-5a42874175c0.jpg" />= outflow volume of reactor, <img src="2-1100142\768698c9-b141-49fd-ac8e-dab4789b8099.jpg" />= inflow pressure, <img src="2-1100142\e704aa5c-e506-4f99-8bf4-c8e43d7f5405.jpg" />= outflow Pressure, <img src="2-1100142\1758bd14-954a-4d99-8880-ccc581ca36bc.jpg" />= flowrate (in), <img src="2-1100142\ec497d7a-af3a-44d3-9949-aeb051c35729.jpg" />= flowrate (out), m = mass <img src="2-1100142\a6907c65-6a7e-4379-a496-c3d1085d295a.jpg" /> = inflow density, <img src="2-1100142\fa18327c-0f18-4437-a226-d74727f8f58d.jpg" />= outflow density and <img src="2-1100142\ffb14ad0-60c3-4d5a-9777-61b6a63d5fda.jpg" /> = general density, also</p><disp-formula id="scirp.28991-formula48969"><label>(5)</label><graphic position="anchor" xlink:href="2-1100142\22abcb58-aafe-488f-a5e7-fdeec1123b14.jpg"  xlink:type="simple"/></disp-formula><p>Substituting (5) in (4) and using the result in (3), we obtain</p><disp-formula id="scirp.28991-formula48970"><label>(6)</label><graphic position="anchor" xlink:href="2-1100142\728714c0-05c1-4d00-a4f5-7b77c59bfeb4.jpg"  xlink:type="simple"/></disp-formula><p>The energy terms of total energy composed in Internal U, Kinetic K and Potential energy <img src="2-1100142\5003311b-9388-4f21-9c25-9d3e64dc56e5.jpg" /> is expressed as:</p><disp-formula id="scirp.28991-formula48971"><label>(7)</label><graphic position="anchor" xlink:href="2-1100142\2d6372fd-7a40-4f64-a57d-51e29d5c6bb9.jpg"  xlink:type="simple"/></disp-formula><p>Substituting (7) in (2), we obtain</p><disp-formula id="scirp.28991-formula48972"><label>(8)</label><graphic position="anchor" xlink:href="2-1100142\c190ad9d-fc6b-4431-8d81-d6d382f1d8aa.jpg"  xlink:type="simple"/></disp-formula><p>but in chemical reactors, only the internal energy is considered with the enthalphy <img src="2-1100142\0b2070ca-7f86-471c-8557-49b47a32d2b8.jpg" /> per unit mass, hence 8 becomes</p><disp-formula id="scirp.28991-formula48973"><label>(9)</label><graphic position="anchor" xlink:href="2-1100142\b2441417-c402-4d29-9160-f57e3415ca4c.jpg"  xlink:type="simple"/></disp-formula></sec><sec id="s2_2"><title>2.2. The Batch Reactor</title><p>The batch reactors have no flowstream (i.e. <img src="2-1100142\7ee9a4d6-1920-4d2b-943c-5317cdace30e.jpg" />). Therefore, Equation (9) in terms of rate of heat becomes</p><disp-formula id="scirp.28991-formula48974"><label>(10)</label><graphic position="anchor" xlink:href="2-1100142\c158296a-39b4-47b6-bbdd-27a78382b58d.jpg"  xlink:type="simple"/></disp-formula><p>Neglecting the work done by stirrer because the mixture is not highly viscous, so the stirring operation do not draw significant power, (10) yield</p><disp-formula id="scirp.28991-formula48975"><label>(11)</label><graphic position="anchor" xlink:href="2-1100142\f8bcb3c4-08fc-44cc-8b37-b4efd6979179.jpg"  xlink:type="simple"/></disp-formula><p>and we know that<img src="2-1100142\4bc35815-c5d1-4247-b476-f2f41179260a.jpg" />, hence (11) becomes</p><disp-formula id="scirp.28991-formula48976"><label>(12)</label><graphic position="anchor" xlink:href="2-1100142\2be931af-f719-4f81-8043-c21f90202ee4.jpg"  xlink:type="simple"/></disp-formula><p>For Batch reactor in terms of enthalpy, we have</p><disp-formula id="scirp.28991-formula48977"><label>(13)</label><graphic position="anchor" xlink:href="2-1100142\e43c89aa-3615-47ff-a984-1a1650da3233.jpg"  xlink:type="simple"/></disp-formula><p>Taking the differential of (13) for <img src="2-1100142\187e2b1f-1edf-40f5-beaf-8948063fee61.jpg" /> and substituting in (12), we obtain</p><disp-formula id="scirp.28991-formula48978"><label>(14)</label><graphic position="anchor" xlink:href="2-1100142\0c587e64-1e7d-407f-a8e1-82e11977d010.jpg"  xlink:type="simple"/></disp-formula><p>We now consider enthalpy as a function of temperature T, pressure P and number of moles n<sub>j</sub>, and express its differentials as</p><disp-formula id="scirp.28991-formula48979"><label>(15)</label><graphic position="anchor" xlink:href="2-1100142\b7d61d32-8a0a-4a6a-a600-c92d8780bdfe.jpg"  xlink:type="simple"/></disp-formula><p>The first partial derivative is the definitions of the heat capacity, <img src="2-1100142\d4758972-480f-4248-be8f-a70c73705aa4.jpg" />, that is</p><disp-formula id="scirp.28991-formula48980"><label>(16)</label><graphic position="anchor" xlink:href="2-1100142\85857225-b133-4725-b258-ad1ced38ef01.jpg"  xlink:type="simple"/></disp-formula><p>The second partial derivative can be expressed as</p><disp-formula id="scirp.28991-formula48981"><label>(17)</label><graphic position="anchor" xlink:href="2-1100142\574f61d8-009f-494b-9258-8a13523852a2.jpg"  xlink:type="simple"/></disp-formula><p>where <img src="2-1100142\c8bc623b-6e94-4705-a473-60af2486e438.jpg" /> is the coefficient of expansion of mixture.</p><p>The final partial derivatives are the partial molar enthalpies, <img src="2-1100142\1078d48d-d9a8-49c9-ada4-776fa1c2eb40.jpg" /></p><disp-formula id="scirp.28991-formula48982"><label>(18)</label><graphic position="anchor" xlink:href="2-1100142\ce7c5ab2-77a6-4496-973e-8844d48502c8.jpg"  xlink:type="simple"/></disp-formula><p>Substituting (16), (17) and (18) in (15) and using the result in (14), we obtain</p><disp-formula id="scirp.28991-formula48983"><label>(19)</label><graphic position="anchor" xlink:href="2-1100142\bfae9aa7-0ea2-4b0f-acf6-fd0b14fd77f1.jpg"  xlink:type="simple"/></disp-formula><p>But the material balance for batch reactor is</p><disp-formula id="scirp.28991-formula48984"><label>(20)</label><graphic position="anchor" xlink:href="2-1100142\8797d809-7108-4a58-920e-f3c475180e90.jpg"  xlink:type="simple"/></disp-formula><p>where <img src="2-1100142\7be022d6-3c2d-4791-aa9f-1d3e2842b513.jpg" /> is the stoichiometric coefficient for species j and reaction i, <img src="2-1100142\eba337d0-01b7-4594-a800-5958d40306b5.jpg" />is the production rate for jth species and <img src="2-1100142\b9cb2e96-f75c-4fd9-a6d3-9f9fb471a766.jpg" /> is the reaction rate for ith reaction.</p><p>And the heat of reaction is</p><disp-formula id="scirp.28991-formula48985"><label>(21)</label><graphic position="anchor" xlink:href="2-1100142\e8804976-9a98-4be6-a528-79b5ba260bcb.jpg"  xlink:type="simple"/></disp-formula><p>Substituting (20) and (21) in (19) we obtain</p><disp-formula id="scirp.28991-formula48986"><label>(22)</label><graphic position="anchor" xlink:href="2-1100142\380d6a82-610e-49f3-ad84-14f0bc86a797.jpg"  xlink:type="simple"/></disp-formula><p>The constant-pressure batch reactor is the incompressible-fluid and for <img src="2-1100142\5c22297b-6ce8-40bd-bcf0-8335d6556917.jpg" /> then Equation (22), becomes</p><disp-formula id="scirp.28991-formula48987"><label>(23)</label><graphic position="anchor" xlink:href="2-1100142\ec350fce-889b-487a-9ee0-518af3278dd5.jpg"  xlink:type="simple"/></disp-formula><p>If the heat removal is manipulated to maintain constant reactor temperature, the time derivative in Equation (23) vanishes leaving</p><disp-formula id="scirp.28991-formula48988"><label>(24)</label><graphic position="anchor" xlink:href="2-1100142\53885a56-84ab-4dcb-90bf-437da4d393a8.jpg"  xlink:type="simple"/></disp-formula><p>When C<sub>A</sub> = concentration of species A, k = reaction rate constant, <img src="2-1100142\6e7c244f-8f82-4e00-8203-00b2af5651b1.jpg" />and <img src="2-1100142\593ebd32-fa67-448a-8bdd-951ca1e5ee35.jpg" /> is the enthalpy change on reaction then Equation (24) becomes</p><disp-formula id="scirp.28991-formula48989"><label>(25)</label><graphic position="anchor" xlink:href="2-1100142\5f0e4ef8-58f3-4ccf-99e1-251bb2105fd0.jpg"  xlink:type="simple"/></disp-formula><p>For the constant-volume batch reactor, we considered the pressure as function of temperature, volume and number of moles, and also expressed its differentials as:</p><disp-formula id="scirp.28991-formula48990"><label>(26)</label><graphic position="anchor" xlink:href="2-1100142\8fcf0a8a-21f7-42ab-b221-ae791267eac9.jpg"  xlink:type="simple"/></disp-formula><p>For reactor operation at constant volume, <img src="2-1100142\715cbc19-6bae-45f6-9d68-6a1286fa19a8.jpg" />and forming time derivatives, just as we did in (15) to (17) and substituting into Equation (19) gives</p><disp-formula id="scirp.28991-formula48991"><label>(27)</label><graphic position="anchor" xlink:href="2-1100142\f1dbd805-b335-46ed-89f6-9ed2669528bb.jpg"  xlink:type="simple"/></disp-formula><p>Note that the first term in brackets is the total constant-volume heat capacitythat is <img src="2-1100142\363122a1-d265-4100-b3ea-aceec3635748.jpg" /> &#160;&#160;&#160;(28)</p><p>Substitution (28) and the material balance in (20), yields the rate of heat for the energy balance of the Constant-Volume batch Reactor. That is</p><disp-formula id="scirp.28991-formula48992"><label>(29)</label><graphic position="anchor" xlink:href="2-1100142\fb5cc855-3417-46e1-8325-d91e7ddd39e2.jpg"  xlink:type="simple"/></disp-formula><p>If we consider a constant volume-ideal gas, where <img src="2-1100142\29aa587a-a7e9-421f-8755-b2affe54a627.jpg" /> and<img src="2-1100142\4e8bf971-1a83-4e89-85ee-1d7176d247f3.jpg" />. Substituting these into (29) gives</p><disp-formula id="scirp.28991-formula48993"><label>(30)</label><graphic position="anchor" xlink:href="2-1100142\258b000d-d05d-437a-a0dc-7a32d2ae4395.jpg"  xlink:type="simple"/></disp-formula><p>where</p><disp-formula id="scirp.28991-formula48994"><label>(31)</label><graphic position="anchor" xlink:href="2-1100142\c071a08c-9838-49a2-b37d-bbe0d6e71bb2.jpg"  xlink:type="simple"/></disp-formula></sec><sec id="s2_3"><title>2.3. The Continuous Stirred Tank Reactor (CSTR)</title><p>In order to describe the dynamic operation of a CSTR, the energy balance equation must be developed. The CSTR has flowstream, hence using the Equations (8)</p><disp-formula id="scirp.28991-formula48995"><label>(32)</label><graphic position="anchor" xlink:href="2-1100142\438a7bf1-5a65-4c04-91c9-69ee46c8c335.jpg"  xlink:type="simple"/></disp-formula><p>As in (9) only the internal energy is considered. The out flow stream is flowing out of a well-mixed reactor, thus, the CSTR rate of heat equation using (32) is</p><disp-formula id="scirp.28991-formula48996"><label>(33)</label><graphic position="anchor" xlink:href="2-1100142\b4534d2e-d0eb-493c-bd20-36f61e719848.jpg"  xlink:type="simple"/></disp-formula><p>where <img src="2-1100142\c4302e17-0177-4ade-a94a-bb895eb7c50e.jpg" /> = volumetric flow rate, <img src="2-1100142\979e0f2b-1694-4c4a-a067-fce385ce4f8a.jpg" />= flow density, <img src="2-1100142\1058fe24-d5bd-4055-8bdc-a18b1dae0bb3.jpg" />= flow enthalpy, <img src="2-1100142\5bdc21c6-6e1e-4d41-965b-8fda0ec2df52.jpg" />= flow concentration with component j and Q = flow rate.</p><p>As before, if sharf work is neglected for the CSTR, Equation (33) becomes</p><disp-formula id="scirp.28991-formula48997"><label>(34)</label><graphic position="anchor" xlink:href="2-1100142\fc68ac2f-e7e1-4785-bc78-2ecc63d4d81b.jpg"  xlink:type="simple"/></disp-formula><p>and if the enthalpy is considered, we obtain</p><disp-formula id="scirp.28991-formula48998"><label>(35)</label><graphic position="anchor" xlink:href="2-1100142\c5384c4b-fb54-4f3e-8684-2081ab097907.jpg"  xlink:type="simple"/></disp-formula><p>We consider the change in enthalpy of the continuous stirred tank reactor (CSTR) as a function of temperature, pressure and number of moles, and express its differentials as</p><disp-formula id="scirp.28991-formula48999"><label>(36)</label><graphic position="anchor" xlink:href="2-1100142\29cec335-73cc-4e97-8ce2-d2d009a6ce3e.jpg"  xlink:type="simple"/></disp-formula><p>and substituting into Equation (35) gives</p><disp-formula id="scirp.28991-formula49000"><label>(37)</label><graphic position="anchor" xlink:href="2-1100142\7c46da2c-8786-47c0-9b43-a440c4f98310.jpg"  xlink:type="simple"/></disp-formula><p>The material balance for the CSTR is</p><disp-formula id="scirp.28991-formula49001"><label>(38)</label><graphic position="anchor" xlink:href="2-1100142\abc1f737-11a2-4f4d-af86-a6614929cf91.jpg"  xlink:type="simple"/></disp-formula><p>After substituting (38) in (37) and re-arrangement yields</p><disp-formula id="scirp.28991-formula49002"><label>(39)</label><graphic position="anchor" xlink:href="2-1100142\aedb5163-46e6-4043-a7fb-05d29719430a.jpg"  xlink:type="simple"/></disp-formula><p>The equation of rate of heat for constant-pressure in CSTR that is Incompressible-fluid and its mean in Equation (39) is <img src="2-1100142\06bc2477-eaf3-4e4d-8db2-10ab958ad49b.jpg" /> and hence we have</p><disp-formula id="scirp.28991-formula49003"><label>(40)</label><graphic position="anchor" xlink:href="2-1100142\a566403c-2972-4ede-9f9c-b4534d410062.jpg"  xlink:type="simple"/></disp-formula><p>From Equation (40), we obtained the equation of rate of heat for constant-volume in CSTR as follows:</p><disp-formula id="scirp.28991-formula49004"><label>(41)</label><graphic position="anchor" xlink:href="2-1100142\783e12c7-9e10-4096-bc52-fa5c81615c73.jpg"  xlink:type="simple"/></disp-formula><p>Also, from Equation (41), the equation of rate of heat for ideal gas is:</p><disp-formula id="scirp.28991-formula49005"><label>(42)</label><graphic position="anchor" xlink:href="2-1100142\6f4c43cc-da9e-4043-a3c1-50118b9095e0.jpg"  xlink:type="simple"/></disp-formula><p>For steady state constant, we have</p><p><img src="2-1100142\b8156300-3d67-4b6a-b2cc-41402d2da369.jpg" />, <img src="2-1100142\d9af8b81-322a-42a4-84f7-bcad2eade047.jpg" />and <img src="2-1100142\a1c6a579-16a2-45e0-8413-1fe4a8e65246.jpg" /> &#160;&#160;(43)</p><p>If we re-arrange Equation (39) in the form</p><disp-formula id="scirp.28991-formula49006"><label>(44)</label><graphic position="anchor" xlink:href="2-1100142\70960832-c961-4572-9a31-72385aaa78ee.jpg"  xlink:type="simple"/></disp-formula><p>By setting the Right hand side of (44) equals zero and substituting (43) in the result gives</p><disp-formula id="scirp.28991-formula49007"><label>(45)</label><graphic position="anchor" xlink:href="2-1100142\a6e8ff14-419d-4876-928c-6e01b8b19312.jpg"  xlink:type="simple"/></disp-formula><p>The heat removal rate of CSTR required bringing CSTR reactor out-flow stream from final temperature T<sub>f</sub> to temperature T and is given (from 45) by</p><disp-formula id="scirp.28991-formula49008"><label>(46)</label><graphic position="anchor" xlink:href="2-1100142\05122072-6570-472b-9d2d-0400d48976e1.jpg"  xlink:type="simple"/></disp-formula></sec><sec id="s2_4"><title>2.4. The Semi-Batch Reactor</title><p>The development of the semi-batch reactor energy balance follows directly from the CSTR energy balance derivation of the rate of heat by setting Q = 0. The main results in this paper are therefore summarized below:</p><p>Neglecting the Kinetic Energy in Equation (33) of the CSTR, when Q = 0, we obtain</p><disp-formula id="scirp.28991-formula49009"><label>(47)</label><graphic position="anchor" xlink:href="2-1100142\40028407-245e-49f5-a5ad-e265f1e6ffe7.jpg"  xlink:type="simple"/></disp-formula><p>Also, by neglecting the Sharf work and consider the Enthalpy when Q = 0 in (34) and (35) yields</p><disp-formula id="scirp.28991-formula49010"><label>(48)</label><graphic position="anchor" xlink:href="2-1100142\4704acb3-a42a-47b9-a900-274e9d340686.jpg"  xlink:type="simple"/></disp-formula><p>and if the enthalpy is used, we obtain</p><disp-formula id="scirp.28991-formula49011"><label>(49)</label><graphic position="anchor" xlink:href="2-1100142\b4538222-c88b-4353-8c0c-6e6b565c0793.jpg"  xlink:type="simple"/></disp-formula><p>By setting Q = 0 in Equations (37) and (39) respectively, we have the enthalpy change of semi-batch reactor as</p><disp-formula id="scirp.28991-formula49012"><label>(50)</label><graphic position="anchor" xlink:href="2-1100142\6df25f23-d871-4e33-b9ff-18ba21b8658c.jpg"  xlink:type="simple"/></disp-formula><p>and</p><disp-formula id="scirp.28991-formula49013"><label>(51)</label><graphic position="anchor" xlink:href="2-1100142\aaf3ed1b-14ff-4c6f-b910-11499ef3a628.jpg"  xlink:type="simple"/></disp-formula><p>The constant pressure semi-batch reactor is the incompressible-fluid batch reactor and in Equation (51)</p><p>when<img src="2-1100142\dd7f30e7-92ba-4b2a-8949-44bf304937cf.jpg" />, we obtain</p><disp-formula id="scirp.28991-formula49014"><label>(52)</label><graphic position="anchor" xlink:href="2-1100142\939a2f82-8b65-45d6-9f25-133d72aa4ec8.jpg"  xlink:type="simple"/></disp-formula><p>For steady state semi-batch reactor when <img src="2-1100142\a0f58e2f-3c60-4d47-94a8-06050044a9ea.jpg" /> is constant, we have</p><disp-formula id="scirp.28991-formula49015"><label>(53)</label><graphic position="anchor" xlink:href="2-1100142\ccf8fef0-b158-4cf2-8f6f-c1092695a976.jpg"  xlink:type="simple"/></disp-formula><p>The equation is derived from the energy balance equation for Plug-flow reactor (PFR) single phase for rate of heat, and is given by:</p><disp-formula id="scirp.28991-formula49016"><label>(54)</label><graphic position="anchor" xlink:href="2-1100142\a463c2c8-7779-4e3d-be82-eedd6a07d88e.jpg"  xlink:type="simple"/></disp-formula><p>Neglecting pressure drop or ideal gas for PFR and from (54), for an Ideal gas <img src="2-1100142\40678aab-c946-42d0-a929-e45ba24cab6d.jpg" /> we have</p><disp-formula id="scirp.28991-formula49017"><label>(55)</label><graphic position="anchor" xlink:href="2-1100142\b8d8830e-0d0e-46da-996c-6a8389a7b072.jpg"  xlink:type="simple"/></disp-formula><p>The rate of heat equation of PFR for Incompressible fluid is obtain by setting <img src="2-1100142\eed7fc4e-1422-49be-bc85-9c427f90626d.jpg" /> in Equation (54)</p><disp-formula id="scirp.28991-formula49018"><label>(56)</label><graphic position="anchor" xlink:href="2-1100142\d2c8e4cb-9732-48a3-a19b-c66d38c94190.jpg"  xlink:type="simple"/></disp-formula><p>The remaining six existing equations related to the rate of heat of a reactor for temperature of heat transfer medium <img src="2-1100142\ffe77907-c3ed-4694-a907-9f2ee83d1fbe.jpg" /> are as stated below:</p><disp-formula id="scirp.28991-formula49019"><label>(57)</label><graphic position="anchor" xlink:href="2-1100142\9918468e-8c82-4c3f-8383-a09756448e1e.jpg"  xlink:type="simple"/></disp-formula><disp-formula id="scirp.28991-formula49020"><label>(58)</label><graphic position="anchor" xlink:href="2-1100142\82c035a2-1a77-49c9-afcd-c93513e0269d.jpg"  xlink:type="simple"/></disp-formula><disp-formula id="scirp.28991-formula49021"><label>(59)</label><graphic position="anchor" xlink:href="2-1100142\ff2cf0ff-bcd4-4b43-bd40-b5b33511b444.jpg"  xlink:type="simple"/></disp-formula><disp-formula id="scirp.28991-formula49022"><label>(60)</label><graphic position="anchor" xlink:href="2-1100142\6eddb793-3161-4e7a-9938-b84f2e372f2f.jpg"  xlink:type="simple"/></disp-formula><disp-formula id="scirp.28991-formula49023"><label>(61)</label><graphic position="anchor" xlink:href="2-1100142\5dd6652e-dfad-4008-a115-ebe0f4dc301c.jpg"  xlink:type="simple"/></disp-formula><disp-formula id="scirp.28991-formula49024"><label>(62)</label><graphic position="anchor" xlink:href="2-1100142\7402169d-b75f-4497-be91-e18d1d33e992.jpg"  xlink:type="simple"/></disp-formula><p>The equations derived above from the energy balance equation of chemical reactors [<xref ref-type="bibr" rid="scirp.28991-ref7">7</xref>] are thirty; namely: (10), (12), (14), (19), (22)-(25), (29), (30), (33)-(35), (37), (39)-(42) and (45)-(56). These equations with the six existing equations, namely (57)-(62), were structured into mathematical model in form of quadratic functional. The model with some given existing nuclear tokens were solved by the Conjugate Gradient Method algorithm, with MATLAB as a support soft-ware.</p></sec></sec><sec id="s3"><title>3. The Gradient Method (CGM) Algorithm</title><p>The CGM algorithm was originally developed by Hestenes and Stiefel [<xref ref-type="bibr" rid="scirp.28991-ref8">8</xref>] to minimize and solve problems in quadratic functional of the form:</p><disp-formula id="scirp.28991-formula49025"><label>(3.0.1)</label><graphic position="anchor" xlink:href="2-1100142\7cd08eaf-22f2-4320-b9fc-23946c95968a.jpg"  xlink:type="simple"/></disp-formula><p>where f<sub>0</sub>, is a constant in H, x is a vector in H. A is a positive definite, symmetric and constant matrix operator.</p><p>It has a well worked out theory with an elegant convergence profile. No approximation is used in the proving its convergency.</p><sec id="s3_1"><title>3.1. Property of Conjugate Gradient Method (CGM) Algorithm</title><p>Some of the several properties of CGM are:</p><p>1) It has a quadratic convergence property that is for a quadratic functional on an n-dimensional Hilbert space, it converges in at most n steps.</p><p>2) It requires a relatively small increase in computer time per iteration and memory space.</p><p>3) It has a well worked out theory.</p></sec><sec id="s3_2"><title>3.2. Algorithm</title><p>The first element of the descent sequence <img src="2-1100142\1423aa1c-6b5e-4763-a950-b88ced4a1f09.jpg" /> is simply guessed. The remaining members of the sequence are then found as follows:</p><disp-formula id="scirp.28991-formula49026"><label>(3.2.1)</label><graphic position="anchor" xlink:href="2-1100142\444dce6b-d379-4d5e-9b74-19fbe4bf3ff8.jpg"  xlink:type="simple"/></disp-formula><p><img src="2-1100142\4ea20c36-19d5-47e7-9b7a-919973f0d520.jpg" /><img src="2-1100142\ac05ddfa-a6cf-42b2-a817-37ee532de81e.jpg" /> (3.2.2)</p><disp-formula id="scirp.28991-formula49027"><label>(3.2.3)</label><graphic position="anchor" xlink:href="2-1100142\5f3483d6-2fbb-45f4-a060-2d26ad9f8cf8.jpg"  xlink:type="simple"/></disp-formula><p><img src="2-1100142\74161d2a-f099-48f2-bed6-3ed7cabd3930.jpg" /><img src="2-1100142\c60162df-f87d-498b-880c-f5196f46dd66.jpg" /> (3.2.4)</p><p>where g<sub>i</sub> is the gradient at the ith element of the descent sequence X<sub>i</sub>.</p><p>It has been proved that the algorithm converges at most, in n iteration in a well posed problem and the convergence rate is given as:</p><disp-formula id="scirp.28991-formula49028"><label>(3.2.5)</label><graphic position="anchor" xlink:href="2-1100142\007c96fe-7ab0-4457-b6a9-50ed68a5f23f.jpg"  xlink:type="simple"/></disp-formula><p>where m and M are smallest and spectrums of matrix A respectively. That is, for an n dimensional problem, the algorithm will converge in at most n iterations [<xref ref-type="bibr" rid="scirp.28991-ref9">9</xref>].</p></sec></sec><sec id="s4"><title>4. Computational Results</title><p>Our model is:</p><disp-formula id="scirp.28991-formula49029"><label>(4.0.1)</label><graphic position="anchor" xlink:href="2-1100142\80a971e1-86a4-46bd-a364-a46cdef0b215.jpg"  xlink:type="simple"/></disp-formula><p>where <img src="2-1100142\4252c383-cf33-416b-b550-49e659c86a0b.jpg" /> i.e., <img src="2-1100142\b62a60a5-3ec1-4ef4-926c-8aca6de83258.jpg" />, <img src="2-1100142\a4711982-e32d-45bc-8f42-f3b948561a32.jpg" />, <img src="2-1100142\b2053c55-6178-45ec-ae3a-3103ade453fb.jpg" />and</p><p><img src="2-1100142\c8f3aaf0-fec1-4b78-ac88-6d53480a2318.jpg" /></p><p>where <img src="2-1100142\ca59cfc1-f130-490b-8dc6-81336bd5dcfa.jpg" /> = values of the rate of heat,<img src="2-1100142\9939c4f1-5e65-45d7-8ff6-f1a862fa46d6.jpg" />; and<img src="2-1100142\4bb2f8ee-c658-4f25-9d9f-d2b6b95890f9.jpg" />.</p><p>Numerical values are now calculated for our parameters or tokens. In all cases our initial guess is 0 vector that is <img src="2-1100142\cc9ffeab-8483-46b6-9960-b15d45755e1f.jpg" /> and the results are as shown below:</p><sec id="s5_0_1"><title>Problem 1 (For arbitrary tokens)</title><p><img src="2-1100142\d196433b-8a0a-4bc9-867e-2689f0022ef0.jpg" /></p></sec><sec id="s5_0_2"><title>Problem 2 (For arbitrary tokens)</title><p><img src="2-1100142\9623b2a9-c58c-4b4b-9461-d88c7ea9cea3.jpg" /></p></sec><sec id="s5_0_3"><title>Problem 3 (For nuclear tokens)</title><p><img src="2-1100142\0a522a65-da38-4e05-ba1e-230030ba0704.jpg" /></p></sec><sec id="s5_0_4"><title>Problem 4 (For nuclear tokens)</title><p><img src="2-1100142\e2864733-aba8-44a2-8dc2-bf79d62e9c15.jpg" /></p></sec><sec id="s5_1"><title>4.1. Tables of Results</title><p>The following tables are <xref ref-type="table" rid="table1">Table 1</xref> for Problem 1, <xref ref-type="table" rid="table2">Table 2</xref> for problem 2, <xref ref-type="table" rid="table3">Table 3</xref> for problem 3 and <xref ref-type="table" rid="table4">Table 4</xref> for problem 4 respectively.</p></sec><sec id="s5_2"><title>4.2. Discussion of Results</title><p>The initial nuclear tokens used in problems 1 and 2 to represent the vectors and control operators of the quadratic model were arbitrary. Our results clearly shown that arbitrary composition of nuclear tokens will not guarantee safety. This is evidence from Tables 1 and 2 (non convergence) which did not satisfied the properties of the CGM algorithm. See [<xref ref-type="bibr" rid="scirp.28991-ref10">10</xref>].</p><p>After restructuring, nuclear tokens were used as the vectors and control operators of the quadratic model to generate problems 3 and 4 and were solved using the CGM algorithm. We were able to get two results that converge (Tables 3 and 4). The convergency satisfied the properties of the CGM algorithm, which shows good results. See [<xref ref-type="bibr" rid="scirp.28991-ref11">11</xref>] and [<xref ref-type="bibr" rid="scirp.28991-ref12">12</xref>].</p></sec></sec><sec id="s6"><title>5. Conclusions</title><p>The nuclear reactors tokens are the main components that make up the reactors, example of the components are Internal energy, Reactor volume, Molar mass and so on, which produces the rate of heat of the reactor that causes</p><p><xref ref-type="table" rid="table1">Table 1</xref>. Generated from problem 1.</p><p><img src="2-1100142\9cc30c0b-222c-4bd3-bd9b-fd58c94e6d00.jpg" /></p><p>Continued</p><p><img src="2-1100142\e7b70126-14e9-4670-814f-b64bcfbb425e.jpg" /></p><p><xref ref-type="table" rid="table2">Table 2</xref>. Generated from problem 2.</p><p><img src="2-1100142\5cc61f58-a4b4-4476-87ac-965604e9cea7.jpg" /></p><p>Continued</p><p><img src="2-1100142\51043eb5-e641-4fbe-afb0-18a359f08a07.jpg" /></p><p><xref ref-type="table" rid="table3">Table 3</xref>. Generated from problem 3.</p><p><img src="2-1100142\0f3a96f4-ad27-4b25-a3d5-29b5b72d3e1d.jpg" /></p><p>Continued</p><p><img src="2-1100142\36413160-3f1f-421a-b2a0-457d21d05d94.jpg" /></p><p><xref ref-type="table" rid="table4">Table 4</xref>. Generated from problem 4.</p><p><img src="2-1100142\876650c6-ec85-4a1b-8c62-a872064ebcee.jpg" /></p><p>Continued</p><p><img src="2-1100142\bb779ee8-7a4d-48ae-8f2e-637106c64a14.jpg" /></p><p>the accidents. See [13-20].</p><p>Our results clearly indicate that if the nuclear tokens are used for the structured model, which are used for the construction of nuclear reactors, then the nuclear safety will be maximized while the disaster will be minimized.</p></sec><sec id="s7"><title>REFERENCES</title></sec><sec id="s8"><title>NOTES</title></sec></body><back><ref-list><title>References</title><ref id="scirp.28991-ref1"><label>1</label><mixed-citation publication-type="other" xlink:type="simple">Nuclear Energy Agency, “Nuclear Fuel Behaviour in Loss-of-Coolant-Accident (LOCA) Conditions,” 2009, p. 141. http://wwwoecd-nea.org/nsd/reports/2009/nea6846-LOCA.pdf</mixed-citation></ref><ref id="scirp.28991-ref2"><label>2</label><mixed-citation publication-type="other" xlink:type="simple">A. C. 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