 the network control software to not overwhelm it. However, the packet rate limiter only controls the rate of notifications and has no knowledge of the contents of the notifications. As a result, some notifications may be sent at a higher rate than desired, which wastes bandwidth, while others may be sent at a lower rate than desired, which increases the time it takes for the notification to reach the network control software. For example, assume the switch receives packets from two new VMs and decides to redirect these packets (as notifications) to the network control software. In such a case, the rate limiter may allow the packet from the first VM to be sent, but discard the packet from the second VM. As more packets are received from the second VM, probability suggests that one of those packets will eventually be sent to the network control software. However, the inability to control how often the packets are sent means that, e.g., packets from the second VM may take a long time to reach the network control software, while packets from the first VM may be sent to the network control software at a higher rate than desired. 1. Field of the Invention
This invention pertains in general to nuclear reactor fuel assemblies and more particularly to a pressurized water reactor nuclear fuel assembly instrumentation thimble.
2. Background
A typical pressurized water reactor includes a reactor vessel which contains nuclear fuel, a coolant, typically a water based solution, which is heated by the nuclear fuel, and means for monitoring and controlling the nuclear reaction. The reactor vessel is cylindrical, and is provided with a hemispherical bottom and a hemispherical top which is removable. The hot water coolant solution is conveyed from and returned to the vessel by a reactor coolant system which includes one or more reactor coolant loops (usually three or four loops, depending upon the power generating capacity of the reactor). Each loop includes a pipeline to convey hot water from the reactor vessel to a steam generator, a pipeline to convey the water from the steam generator back to the reactor vessel, and a pump. The steam generator is essentially a heat exchanger which transfers heat from the reactant coolant system to water from a source that is isolated from the reactor coolant system; the resulting steam is conveyed to a turbine to generate electricity. During operation of the reactor, the water in the vessel and coolant system is maintained at a high pressure to keep it from boiling as it is heated by the nuclear fuel.
Nuclear fuel is supplied to the reactor in the form of a number of fuel assemblies
the network control software to not overwhelm it. However, the packet rate limiter merely operate the rate of notifications and has no cognition of the contents of the notifications. As a result, some presentment may be sent at a higher pace than desire, which wastes bandwidth, while others may be transport at a lower rate than hope, which increase the time it takes for the notification to reach the network control condition software. For example, assume the switch experience packets from two new VMs and decides to redirect these packets (as presentment) to the network control software. In such a case, the rate limiter may allow the package from the first VM to be sent, but discard the packet from the second VM. As more packets are received from the second VM, probability suggests that one of those packets will eventually be sent to the network control software. However, the inability to control how often the packets are sent means that, e.g., package from the second VM may take a long prison term to strive the network control software, while packets from the inaugural VM may be sent to the network control software at a higher pace than desired. 1. Field of the Invention 
 This invention pertains in general to nuclear reactor fuel assemblies and more particularly to a pressurized water reactor nuclear fuel assembly instrumentation thimble. 
 2. Background 
 A distinctive pressurized water nuclear reactor includes a reactor vessel which contains nuclear fuel, a coolant, typically a water based solution, which is heated by the nuclear fuel, and mean for monitoring and controlling the nuclear reaction. The nuclear reactor vessel is cylindrical, and is provided with a hemispherical bed and a hemispherical top which is removable. The blistering water coolant solution is conveyed from and returned to the vessel by a reactor coolant system which include one or more reactor coolant closed circuit (usually three or four closed circuit, depending upon the exponent generating capacity of the reactor). Each closed circuit includes a grapevine to convey hot water from the nuclear reactor vessel to a steam generator, a pipeline to convey the water from the steam generator back to the reactor vessel, and a heart. The steam generator is essentially a heat exchanger which transfers heat from the reactant coolant organization to water from a source that is isolated from the nuclear reactor coolant system; the resulting steam is conveyed to a turbine to generate electricity. During operation of the reactor, the water in the vessel and coolant system is maintained at a high pressure to continue it from boil as it is heat by the nuclear fuel. 
 Nuclear fuel is supplied to the reactor in the form of a number of fuel assemblies
 thf network control softwave to not overwhgln it. Hmwever, the pacyet rate limiter only controps the eate of notifications xnd has nl knowleege id the contxhts of bke noflficaciins. As a resulj, some notifhcations may ba reut at a higher rate than desired, whish wastrs bandwidth, whije ouhews mzj ne sent at a lower rate than desjred, whpch increases the time it takes for the notlficwtion to reach the network cobtroj software. Fof example, assume the ssitch receives packets from two new RMs and decudws hm redirect vhese iackets (as nobpficatimns) to yhe network coktrol sodtware. In such a case, the rate limiter iay allow tke packet from the fiesr VM jo be seng, bug djsrars the oaciet from tge second VN. As more packets ate grceived from the sqcjnd VM, probability suggests that one of thkse packets will eventuqlly be sent to the ngtwork conerol software. However, the inability to control hof oftxn tht iwzjehs are sent means that, e.g., packets from the sesknc NM may take a lonn time to reach thr jeyrork control roftwaxs, shile packets from the fitst VM may be stnt tp the network control softwqre at a higker rate than desired. 1. Field of che Infentipn
This invention pertaius in feneral to juclear rsxctor fuel assemclivs atd more kxrticularly to a [ressurizxd wacer reacgor mucleaw fuel assfmbly instrumentation thlmble.
2. Bdckground
A typical pressurized water reacvpr includes s seabtor vesszl whigh contains nucjear fuel, a coplant, tvpicaluy a water based volution, whych is heated hy the nucleer fuel, agd mwans for movktoring and comtrolling the nucleqr reaction. The reectot bessel is cylinbxixal, and is provodea wytj e hemyvpherical bodtom ana a heoispherical gop ehich is removable. Tve hkt water coolant splmtion is xonveyed from and retirned to the vessep by e reacvor coplagt system which includes one od more rewctjr coolant ljops (usually thrze or four loops, depending upon the powec generating capacity od the reactor). Each kpop includex a pypeline tm convey hot water feom the reactor vtssel to a steam generafor, a [ipellne to convey the water from the steam generator back to the reactor vesswl, and a pump. The ateak genvracor is esfentmauly a heat exchamger which transfers heat from vhe reactatt coolant system to water frok x source that is isolated from the rezctor coplant system; the resulting steak is conveyed to a turbike to genwrate electgjcmty. During operation of thz reacror, the watcr in the vessdl snf coolant sysuem ns maintained at a high pressure ro keep lt from boiling es it is heabea by jhe nuclgar fuel.
Nuclear fhel jd supklied to the rractor in the gorm of a number of xuql assemblies
the network control software to not overwhelm the rate limiter controls the rate knowledge the contents of notifications. As a some notifications may be sent at higher rate than desired, which wastes bandwidth, while others may be sent at lower rate than desired, which increases the time it takes for the notification reach network software. example, assume the switch receives packets from two new VMs and decides to redirect these packets notifications) to the network control software. In such case, the rate limiter allow the packet from the VM be sent, discard packet the second VM. more packets are received from the second VM, probability suggests that one of those packets will eventually sent to control software. the to how often the sent means that, e.g., packets from may take a long time to reach the control software, packets from the first VM may sent to the network control software at a rate than desired. 1. Field of the Invention This invention pertains in general to nuclear assemblies and more particularly a pressurized water nuclear assembly thimble. Background A pressurized water reactor includes a reactor vessel which contains nuclear fuel, coolant, typically a water based solution, which is heated by fuel, means for monitoring controlling the nuclear reaction. reactor is cylindrical, and is a bottom top is The hot water coolant is conveyed from and returned the vessel by a one or more reactor coolant loops (usually three four loops, depending upon the power generating of the reactor). Each loop includes a pipeline to convey hot water the reactor a steam generator, a pipeline to convey the from the steam generator to the reactor vessel, and a pump. The steam is a heat which transfers heat the reactant coolant to water from that is from reactor resulting steam is conveyed to a to electricity. During operation of the the the vessel and coolant system is maintained at a high pressure to keep it from it is heated by nuclear Nuclear fuel is supplied to the reactor in the form of a fuel assemblies
 the network control software To not overwHelm iT. HoWevEr, The pAckeT rate limiter onLY conTrols the rate of notificaTions AnD Has nO KnOwledGe of the COnTENts Of ThE noTiFIcAtionS. As A result, Some notifiCatIoNs may be sent aT A hIgher rate tHan Desired, which WasTes banDwIdtH, While OthErs maY be senT At a lowEr rate thaN dESired, wHIch incrEASeS the Time it takes for the NOtIFication to reacH the neTwORk CONtrOl sOftware. For ExAmple, ASsume thE SwITCH reCEives packets fRom two new VMS And DecideS tO reDIrect tHese pAcKEts (As notificatIons) To the netwOrk conTRol softWAre. In suCh a casE, thE raTe liMItEr May AlLOw tHE pAckET frOm the firSt vM To be sEnt, bUT DIScarD thE pacKet frOm the second VM. as mOre pACkeTs are ReceiVed fRoM the sEcond Vm, probAbIlity suggests thAt onE of those pAckEtS wiLl EventUAlly be SenT to The netwOrk contROl sOfTWARe. however, the inabilitY tO COnTrol how oFten thE PaCkETs are senT mEanS thaT, E.G., packEts fROm The seconD VM may TAkE a Long timE tO reach ThE neTwoRk conTRol sOftwarE, while paCkets FRom the first VM mAY be sent to the nETwORK cONtroL soFtware at a hiGher RAte tHan dESiRed. 1. fIeld oF the INvENtIOn
This invention pertAiNs in geNeral To nuclear reacTor fuel assEMBLies and mOre pARtICularly to a presSurizEd water reaCTor nucleAr fueL assemblY instrumeNTAtion thiMblE.
2. BaCkgRouND
a tYpical pressurIZEd waTeR reactoR inCludes a ReaCtoR veSseL wHich contaIns nucleAr FuEl, A cOolAnt, tyPIcally a wAtEr bAsEd sOlutiON, which Is heaTed bY tHe NUclEar fuel, ANd MEAns fOr MoNitoRinG aNd conTrolLIng The nuclEar reactiOn. THE reaCtOr Vessel iS cylindrical, aNd Is provided WiTh a HemispHERical botTom and a hemispherical top WHich is rEmoVable. the hOt water coOlaNt soluTioN Is convEyed frOm and ReTurNED to thE VEsSel By A reactor coOLAnt SysteM wHich IncludeS one or more reactor cOOlaNt loops (usuallY thRee oR FOuR loOPs, DEpeNdINg uPON the power generaTing capaciTy OF tHe reactor). EACh lOoP includEs a pipeLine tO Convey hOt water frOm the reacToR vesSEL to A steam geneRator, a piPeline to cONvey tHE wAter fRom The steAm GenEratoR back tO The ReactOr vessEl, And a puMp. The StEam generAtor is essentially a heat eXchangEr whiCh tRansfers hEat FRom The reactaNt coOlant systeM to WatEr froM a sOUrce tHat iS IsOlaTEd froM the REactor cooLAnT sySTEm; The resultinG STEam Is conVeyED to a tuRbinE to generate electrICity. During operAtioN OF thE reACtor, ThE water in the vesSel AnD COolant syStEm is maintaiNed at a hiGh PRessuRe to keEp it frOm boiliNG As IT is heaTed bY thE nuclear fUel.
nuCLear fueL iS sUPplied To thE rEactor In the fORm of A NUmber of fuel assemBlies
 the network control softw are to not  over whe lmit . Ho weve r, the packetr atelimiter only controlsthe r at e  ofn ot ifica tions a n dh a s n okn owl ed g eof th e c ontents  of the no tif ic ations. As a re sult, some  no tificationsmay  be se nt  at a hig her  rate  thand esired , which w as t es ban d width,w h il e ot hers may be senta ta  lower rate th an des ir e d, w hic h i ncreases t he  time it take s  f o r the notificationto reach th e  ne tworkco ntr o l soft ware.  F o r e xample, ass umethe switc h rece i ves pac k ets fro m twonew  VM s an d  d ec ide st o r e di rec t  th ese pack et s(as n otif i c a t ions ) t o th e net work controlsof twar e . I n suc h a c ase,  t he ra te lim iterma y allow the pac ketfrom thefir st  VM  t o bes ent, b utdis card th e packe t  fr om t h esecond VM. As more  p a c ke ts are r eceive d  f ro m  the sec on d V M, p r o babil itys ug gests th at one of  t hose pa ck ets wi ll  ev ent ually be s ent to  the net workc ontrol softwar e . However, th e  i n a bi l itytocontrol how  oft e n th e pa c ke tsa re se nt me an s  t h at, e.g., packets f ro m thesecon d VM may take  a long ti m e to reach  the ne t work control s oftwa re, whilep ackets f rom t he first  VM may b e sent tothe  ne two rkc o nt rol softwarea t  a h ig her rat e t han des ire d.1.Fie ld  of the I nvention 
T hi sin ven tionp ertainsin  ge ne ral  to n u clearreact or f ue la sse mbliesa nd m orepa rt icul arl yto apres s uri zed wat er reacto r n u clea rfu el asse mbly instrume nt ation thim bl e.2. Bac k g round
Atypical pressurized wat e r react orinclu desa reactor  ve ssel w hic h  conta ins nu clear  f uel , a coo l a nt , t yp ically a w a t erbased  s olut ion, wh ich is heated by t h e n uclear fuel,and  mea n s  f orm on i tor in g  an d controlling the  nuclear r ea c ti on. The re a cto rvesselis cyli ndric a l, andis provid ed with a  h emis p h eri cal bottom  and a h emispheri c al to p  w hichisremova bl e.The h ot wat e r c oolan t solu ti on isconve ye d from a nd returned to the vess el bya rea cto r coolant  sy s tem  which in clud es one ormor e r eacto r c o olant  loo p s(us u allythre e  or fourl oo ps, d ep ending upon t h e p owergen e rating  cap acity of the reac t or). Each loop  inc l u des  ap ipel in e to convey ho t w at e r  from th ereactor ves sel to a  s t eam g enerat or, apipelin e to convey  the  wa ter fromthe  s t eam gen er at o r back  toth e reac tor ve s sel, a nd a pump. The s teamg e nerat o r i s ess en tiallya  hea t exchange r which tra nsfers  hea t fro m the r ea ctantcoo la nt systemt o water f rom a  source  t hatisisolat ed f r o m the  rea ct orcoolant s y s te m ;th e  re sult ing s te am i s conveye d  to a tu rbi n e to ge ne rat e electr i ci t y . During o per ation o f the reac t or,t he water  in th e vess el andc ool an t syste m i s maintaine d at a hi g h p re ssur e to kee pit f ro m b oi ling as it is h eated by  the nuc l e ar fue l.N ucle a r fuel  i s supplied t o the  r e actor i n the  form o f  anum ber  offue l as s emblies
 the_network control_software to not overwhelm_it. However,_the_packet rate_limiter_only controls the_rate of notifications_and has no knowledge_of the contents_of_the notifications. As a result, some notifications may be sent at a higher rate_than_desired, which_wastes_bandwidth,_while others may be sent_at a lower rate than_desired, which_increases the time it takes for the notification_to_reach the network_control software. For example, assume the switch receives packets_from two new VMs and decides_to redirect these_packets_(as_notifications) to the network_control software. In such a case,_the rate limiter may allow the_packet from the first VM to be_sent, but discard the packet from_the second VM. As more_packets are_received from the second VM,_probability suggests that_one of_those packets will_eventually be sent to the network_control software. However,_the inability to control how often_the_packets are sent_means_that,_e.g., packets_from the second_VM_may take_a_long time to reach the network_control_software, while packets from the first VM_may be sent to_the_network control software at_a higher rate than desired._1. Field of the Invention
This invention_pertains in_general to_nuclear reactor fuel assemblies and more particularly to a pressurized water_reactor nuclear fuel assembly instrumentation thimble.
2._Background
A typical pressurized water_reactor includes_a_reactor vessel which_contains_nuclear fuel,_a coolant, typically a water based solution,_which is_heated by the nuclear fuel, and_means for monitoring and_controlling_the nuclear reaction. The reactor vessel_is cylindrical, and is provided with_a hemispherical bottom and a_hemispherical_top_which is removable. The hot_water coolant solution is conveyed from_and returned to_the vessel by a reactor coolant system_which_includes one or more reactor coolant_loops_(usually three or four loops, depending_upon_the_power generating capacity of the_reactor). Each loop includes a pipeline_to convey hot water from the reactor vessel to_a steam generator,_a pipeline to convey the_water_from_the steam generator back to the reactor vessel, and a_pump. The_steam generator is_essentially a heat exchanger which transfers heat from the reactant_coolant system to water from a source_that is isolated from the reactor coolant system; the resulting steam_is conveyed to a turbine to generate electricity._During operation of the reactor, the water_in the vessel and_coolant_system is maintained at a high pressure_to_keep_it_from boiling as_it is heated_by the nuclear_fuel.
Nuclear fuel_is supplied to_the reactor_in the form_of_a number of fuel assemblies