No abstract

Enter the individual's-. tith o f thc agrrirotbn. or entity 1e.e.. Dbtributbn) that the ED1 b king t~s m m a d m. e Enter the titi. of the organizdon o & i i ud tmanitthg tho EDT. 0 Enter EDTnumbrn which ml.t. m t h~ dd. b e i i truumtmd. EntertheRoi.ctlRogRmlD.putrmm/Divhbntt&orRDWRDOnm~orRol.ct Number. Work Ordrr Numb.r or OrgMizrthn Code. 6 Enter the nun of the individual id~ntifrsd u baing napondbh for wordh.tin(l dbporItbn o f the EDT. a Ent.r mlatad Rrsh.u O r d u (P.O.) Numkr. If adabk. e Enter sp.ci.l or additional w-ntn wnarning tnnsminrl. or 'by' m v d woda may bm entend. e Enter equipnnntlcomponent number o f affected item. If sppropdit.. 0 Enur spplicabb s y M m , b u i l d i i or f.cility nuder. If appropriate. Enter spacial or additbnal comments concsming transmind. 0 Enter applicable drawing numbar of major ssrsmbly, if appropriate. Enter applicabla psrmit or permit application number. If appropriate. 8 Enter t h~ dam a n r p o n w is nqu*bd from individuals idantifid in Bbck 17 (SignatumlDist~iburionl. @ Enter sequential numbor, beginning with 1, of the information Gstad on EDT. Enter the unique identification number assigned to tha document or drawing being trsnsmined. e Enter the sheet number of tha information baing transmittad. If no h t number. kaw blank. 0 Enter the revision number of the Information baing transmitted. tf no revision number, have blonk. Enter the title of the document or drawing or a b h f doauiption of 'tha subject if no titi. is identilid. 8 Enter the appropriate Approval Dssignator (Block 151. Also, M i a t e the appropriate approvals for each item listed. i .e., Sa. ESQ, etc. Enter the appropriate cod. to idantify ch. purpow of the data transmirul lame Bbck 18). 0 Enter the appropriate disposition code bee Block 161. @ Enter t h~ appropriate disposition coda 1. w Block 161. Numbor codes used in completion of Blacks 15 (GI, IH), and 11). and 17 (GI, IH) ISignatumlOistribution). 0 Enter the code of the mrwn for trunrmi-ltal (Block 16). e Enter the code forthe disposition IBbck 161. Enter the rignoturn of the individual comphtinp the Disposition 17 (H) and the Transdttd. @ Obtain appropriate ~ignatura(s1. 0 Enter dote signoturo u obtained. Enter MSIN. Noto: If DlroibvDbn Sheat h uwd. show entire dlmibutbn ltncludlng that indicated on Page 1 of tha EDTl on the D i d b u t i o n Sheet. 0 Enter the signature and date of the individual otiginating the EDT lentemd p r b r to transmittal t o Receiving Organb+tionl. tf the EDT originator is the cognbont engineer, sign both Blocks 17 ond 18. 0 Enter the signature and dote of the i d e n t i f d by the Receiving Orgmkation a~ authorized t o oppmw disporirion of the EDT and acceptonce of tho date trMtmittEd, as applicable. 0 Enter the signature and dote of the cognizant manager. (This 8 i g M t w is authorhation for mleose.] e Enter DOE opprovol (If mquired) by signature or conpol r~umbsrthatmcks the approval to a signaturn, ond indicate DOE action.-Astarirk denote the mquimd minimum itoms check by Configurntion Documentdon pMr to mb...

No abstract

An ongoing analysis (Cooper and Johnson) is examining the credibility of a published value for uranium corrosion in oxygenated water as a basis for estimating the area of the corroding K East fuel. Radiation-Induced Porosity Radiation-induced porosity is judged to have a minor effect on true surface area, because burnups on the failed N Reactor fuel are generally 3000 MWd/MT or below. Even on N Reactor fuel with the highest estimated burnups (-7000 MWd/MT), if porosity is significant, it will result in a narrow band of pits near the metal surfaces for fuel corroding from the ends, with most of the metal cross section substantially unaffected. Effects of Microcracks Reactions in tight microcracks in the metal are expected to be diffusion-limited; in that case, the cracks would not contribute substantially to true surface area. If the metal is segmented, the area increase could be significant when the segmented metal is exposed to reactants. Microcracks were not observed when a damaged K West fuel element was examined metallographically in a hot cell at a location approximately 12 in. (30 cm) from the damaged end. Cracks also were not observed by Swanson on elements that had survived discharge without breaching the cladding. On the other hand, Swanson (1988) reported that after the cladding was dissolved from a damaged N Reactor fuel element, a jumble of broken pieces was observed, rather than a solid cylinder of uranium. The element had corroded 12 years in water after reactor discharge. Swanson attributed the segmentation to reaction of the partially degraded uranium cylinder with the decladding solution (5M NH,F + 0.45 Ea NH,NO,). The reaction was proposed to involve hydrides that developed in uranium grain boundries.

No abstract