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post irradiation examination wikipedia jump to content main menu main menu move to sidebar hide navigation main page contents current events random article about wikipedia contact us contribute help learn to edit community portal recent changes upload file special pages search search appearance donate create account log in personal tools donate create account log in contents move to sidebar hide top 1 fission gas release 2 fuel cracking 3 further reading 4 references 5 external links toggle the table of contents post irradiation examination 1 language العربية edit links article talk english read edit view history tools tools move to sidebar hide actions read edit view history general what links here related changes upload file permanent link page information cite this page get shortened url switch to legacy parser print export download as pdf printable version in other projects wikidata item appearance move to sidebar hide from wikipedia the free encyclopedia study of used nuclear materials post irradiation examination pie is the study of used nuclear materials such as nuclear fuel it has several purposes it is known that by examination of used fuel that the failure modes which occur during normal use and the manner in which the fuel will behave during an accident can be studied in addition information is gained which enables the users of fuel to assure themselves of its quality and it also assists in the development of new fuels after major accidents the core or what is left of it is normally subject to pie in order to find out what happened one site where pie is done is the itu which is the eu centre for the study of highly radioactive materials materials in a high radiation environment such as a reactor can undergo unique behaviors such as swelling 1 and non thermal creep if there are nuclear reactions within the material such as what happens in the fuel the stoichiometry will also change slowly over time these behaviors can lead to new material properties cracking and fission gas release fission gas release edit as the fuel is degraded or heated the more volatile fission products which are trapped within the uranium dioxide may become free 2 fuel cracking edit as the fuel expands on heating the core of the pellet expands more than the rim which may lead to cracking because of the thermal stress thus formed the fuel cracks the cracks tend to go from the centre to the edge in a star shaped pattern in order to better understand and control these changes in materials these behaviors are studied due to the intensely radioactive nature of the used fuel this is done in a hot cell a combination of nondestructive and destructive methods of pie are common in addition to the effects of radiation and the fission products on materials scientists also need to consider the temperature of materials in a reactor and in particular the fuel too high fuel temperatures can compromise the fuel and therefore it is important to control the temperature in order to control the fission chain reaction the temperature of the fuel varies as a function of the distance from the centre to the rim at distance x from the centre the temperature t x is described by the equation where ρ is the power density w m 3 and k f is the thermal conductivity t x t rim ρ r pellet 2 x 2 4 k f 1 to explain this for a series of fuel pellets being used with a rim temperature of 200 c typical for a bwr with different diameters and power densities of 250 wm 3 have been modeled using the above equation note that these fuel pellets are rather large it is normal to use oxide pellets which are about 10 mm in diameter temperature profile for a 20 mm diameter fuel pellet with a power density of 250 w per cubic meter note the central temperature is very different for the different fuel solids temperature profile for a 26 mm diameter fuel pellet with a power density of 250 w per cubic meter temperature profile for a 32 mm diameter fuel pellet with a power density of 250 w per cubic meter temperature profile for a 20 mm diameter fuel pellet with a power density of 500 w per cubic meter because the melting point of uranium dioxide is about 3300 k it is clear that uranium oxide fuel is overheating at the center temperature profile for a 20 mm diameter fuel pellet with a power density of 1000 w per cubic meter the fuels other than uranium dioxide are not compromised further reading edit radiochemistry and nuclear chemistry g choppin j o liljenzin and j rydberg 3rd ed 2002 butterworth heinemann isbn 0 7506 7463 6 references edit armin f lietzke simplified analysis of nuclear fuel pin swelling nasa tn d 5609 1970 j y colle j p hiernaut d papaioannou c ronchi a sasahara journal of nuclear materials 2006 348 229 external links edit iaea international atomic energy agency post irradiation examination facilities database v t e nuclear technology outline science chemistry engineering physics atomic nucleus fission fusion radiation ionizing braking fuel tritium deuterium helium 3 fertile material fissile material isotope separation nuclear material uranium enriched depleted plutonium thorium neutron activation capture poison cross section generator radiation wigner effect reflector temperature thermal fast fusion power by country power plant economics accidents and incidents policy fusion radioisotope thermoelectric rtg mmrtg propulsion rocket safety and security nuclear meltdown medicine imaging autoradiograph radball scintigraphy single photon emission spect positron emission tomography pet therapy fast neutron neutron capture therapy of cancer targeted alpha particle proton beam tomotherapy brachytherapy radiosurgery radiopharmacology processing atomic gardening electron beam processing food irradiation gemstone irradiation weapons topics arms race delivery design disarmament ethics explosion effects history proliferation testing high altitude underground warfare yield tnte lists states with nuclear weapons historical stockpiles and tests tests tests in the united states wmd treaties weapon free zones weapons waste products actinide reprocessed uranium reactor grade plutonium minor actinide activation fission llfp actinide chemistry disposal fuel cycle high level hlw low level llw nuclear decommissioning repository reprocessing spent fuel pool cask transmutation debate nuclear power nuclear weapons blue ribbon commission on america s nuclear future anti nuclear movement uranium mining nuclear power phase out nuclear reactors fission moderator light water aqueous homogeneous boiling bwr bwrx 300 abwr esbwr kerena natural fission pressurized ap1000 apr 1400 apr apwr atmea1 cap1400 cpr 1000 epr hualong one acpr1000 acp1000 vver ritm 200 klt 40 ok 150 ok 900 ok 650 kn 3 vm ipwr 900 many others supercritical scwr heavy water by coolant d 2 o pressurized candu candu 6 candu 9 ec6 afcr acr 1000 cvtr iphwr iphwr 220 iphwr 540 iphwr 700 phwr kwu mzfr r3 r4 marviken h 2 o hwlwr atr hw blwr 250 steam generating sghwr ahwr organic wr 1 co 2 hwgcr el 4 kkn ks 150 lucens graphite by coolant water lwgr h 2 o am 1 amb x egp 6 rbmk mker gas co 2 uranium naturel graphite gaz ungg magnox advanced gas cooled agr he gtmhr mhr t uhtrex vhtr htgr pbr pbmr avr htr 10 htr pm thtr 300 pmr molten salt fluorides fuji msr liquid fluoride thorium reactor lftr molten salt reactor experiment msre integral molten salt reactor imsr tmsr 500 tmsr lf1 none fast neutron breeder fbr integral ifr liquid metal cooled lmfr ok 550 bm 40a vt 1 small sealed transportable autonomous sstar traveling wave twr energy multiplier module em2 reduced moderation rmwr fast breeder test reactor fbtr dual fluid reactor dfr generation iv sodium sfr bn 350 bn 600 bn 800 bn 1200 cfr 600 phénix superphénix pfbr fbr 600 cefr pfr prism lead brest 300 helium gas gfr stable salt reactor ssr others heat pipe cooled organic cooled omre arbus piqua aircraft reactor experiment fusion by confinement magnetic field reversed configuration levitated dipole reversed field pinch spheromak stellarator tokamak inertial bubble acoustic fusor electrostatic laser driven magnetized target z pinch other dense plasma focus migma muon catalyzed polywell pyroelectric nuclear technology portal category commons retrieved from https en wikipedia org w index php title post_irradiation_examination oldid 1162921980 categories nuclear materials nuclear reprocessing nuclear technology nuclear chemistry radioactive waste actinides hidden categories articles with short description short description matches wikidata this page was last edited on 1 july 2023 at 22 30 utc page was rendered with parsoid text is available under the creative commons attribution sharealike 4 0 license additional terms may apply by using this site you agree to the terms of use and privacy policy wikipedia is a registered trademark of the wikimedia foundation inc a non profit organization privacy policy about wikipedia disclaimers contact wikipedia legal safety contacts code of conduct developers 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