om 424 MOCKET-§0201-2% west VALLEY REPROCESSING PLANT}, Envircamesntal Report No, « clear Fuel Services, tee., Woat Valley,WoT) 7 Dep, CFSTI. 1988, OfeO May 1980. ip. M28 (DOC KET-$0201-$4) [WEST VALLEY REPROC ESEING PLANT]. Exrviroamental Report No, 5, July-December 1988. (Nuclear Fuel Services, Ino.. Weet Valley, N. YJ. § May 1089. 20p. Dep. CFST1. 94% (DOCK2T-50201-25) [WEST VALLEY REPROCESSING PLANT}. Environmental Report No. 6, Ji lune 1969, (Nuclear Fuel Services, luc., Weet Valley. N. YJ. 1 Dec 1989. 125. Dep. CFSTtI. 427 (EUR-4401) ZETA POTENTIAL CONTROL APPLIED TO THE TREATMENT OF RADIOACTIVE EFFLUENT. Gillot-Stokkink. A. J.; Lopes Cardozo, R. (European Atomic Energy Community. Ispra (italy), Joint Nuclear Research Conter). 3 Sep 1969. 46p. Dep, CFSTI U.S, Sales Only). Stadtes were carried out to improve working conditions in the decontamination plant for radioactive effluent at Ispra. This plas operates by a ecevenging-flocculation proceas. The generally applied but unprecise ‘beaker teate’’ used for sedimentation oontrol were completed by preciae meesurements of the surface charge or zeta potential of the radioactive sludge suspensions, ‘This allowed the exact cholos of appropriate resctants and dose ratea for optimum Mocculaiion in the case of each type of effluent to be treated, Zeta potential measuremonts were performed with a commercialized device calledZete-meter,”’ comprising a Riddick-type electrophoresia cell. The use of @ cationic polyelec~, trolyte flocoutant, such ta the Purtfloe C $1 of Dow Chemicals, gave very satiafying results. Ite application ia the decontamination plant produced excellent and stable settling conditions, which resulted in doubling the previously obtained process rutes. (auth) vars FUELS. Vel, 24, Ne. 6 NUCLEAR SCIENCE ABSTRACTS (EURAEC-2088) Fins) Report. REPROCRSSING OF IRRADIATED (Centre d'Etude de I’ Nucle: & Apr 1969. Contracts 006-68-7-RCIB; 016~ 66-1-RAPB. Liep. (RUR~4009). Dep. CFSTT. Work performed under United Statee~Euratom Joint Research and Development Program. Highlights from basic and conceptual studies and cold and hot technology expariments are presented, The reection mechanism of CIF, and CIF with UO,—Pu0; mixtures was investigated as a function of ‘omperature snd gas and fuel composition. The de~creasing sphere mode) can be applied to the CIF; which aleo takes place at high speed even with (U -Pu)O, solid solutions, The monofluoride (CIF) on the contrary can be considered as & selective fluorinating agent for UF,, but its lower reactivity requires much higher reaction temperatures (450°C). Cold technology problems on chemical decladding of stainleas steel canned UO, fuel using HF + O are briefly mestioned. Results from the volatilization of UF, in fluidized packed-bed reactors are listed. The reaction rates and efficiencies in large columne of various fluorinating gases (CIF;, CIF, Fy, HF ¢ Oy) are discussed and compared. UF, volatilization rates with CIF, on UO, ~PuQy pellets, are discussed elong with simaltuneous removal of Pu either by volatilization of PuF, with F, or by elutriation of Pu containing fines, Conceptual design work was devoted essentially to the etudy of mechanical decanning. (aath} (EURATOM) 9a? €@N-1314) CHEMICAL TECHNCLOGY BRANCH ANNUAL REPORT, FISCAL YEAR 1969, Bower, J. R. ad.) (Idaho Nuclear Corp,, Idaho Falls), Oct 1969. Contract AT~ ws 8 rowult af thy experience sized on (be rua, other moditiestions ate eatively being considered 9: the ICPP. (outh) east @PRS-49539) PROSPECTS FOR TREATING WATER FROM NUCLEAR ELecrmctPOWER STATIONS WITH PULVERIZKD FONITES, 3 Subbotina, N. P.: Kopyiov, A. * Traasiated from Al, Euerg. oases at:s-bases), &. An abatract of this paper, the origtasl leageage, appeared aa MBA 23: 40634, “22 (KFK-004) DETERMINATION OF IN-PROCESS IN- VENTORY IN A REPROCESSING PLANT BY MEANS OF ISOTOPE ANALYSIS, Winter, H.; Avenhsus, R,; Gupta, D.; Katz, F.; Kraemer, R, palaeinensaeopiroe Karlarube (West Germany}. Inatitut fuer Angew sndte Reaktorphysik). Jal 1969. éép. Dep. CFSTI (VU, S, Sales Only). A method of independent determination of in-process taventory In a reprocesalng plant la discussed, The method is based on men: mead surement of different fissile isotope concentrations in the input and output batches of a reprocessing plant, Topics covered incluse: principle of process inventary determination by iectope analyses, analysis of a typical reprocesaing plant, simulation of a reprocess~ te yeraioa in the case of inventorydeterminations by tracer methods, andditlerenoee in lactopto composition of faal from one reactor. OL0.G.] 2 (L1B-Trans-224) D,O SUPPLY BY THE BYDROGEN- Lange, G.; Sohindewolfe, U, Translated by Peter J. F. Newton Research E: An abatract of this paper, prepared trom the original language, appeared as NSA 23: 26347. 9434 (NYO-4057-1) SEPARATION OF KRYPTON AND XENON FROM REACTOR ATMOSPHERES BY SELECTIVE PERMEATION, Progresa Report, Jasuery 1-December 32, 1969. Stern, S.A. Gyracase Uniy., N.Y. Dept. of Chemical Eagi- neering tad Matallurgy). Contract AT(0-1)-4057. 22p. Dep. FST, Studies are being made to develop an efficient process for re-« moving Fare eae fiaelon products from nuclear reactor stmo- pheres by ue sean ee Ghroagh nonporouspolymerte _ merabranen for the cemeral of Krtad Roe Nealon erheeta te tatng investigated. (M-C.G) 9435 CORNL-TM-2412(Ft.4)) DESIGN CONSIDERATIONS OF REACTOR CONTAINMENT SPRAY SYSTEMS. PART IV. CALCULATION OF IODINE-WATER PARTITION COEFFICIENTS. Paraly,L. F. (Oak National Lab., Tenn). Jaa 1970. Contract W-7408-eng-26. 50p. Dep, CPST!. Procedures for calculating the pertition coefficient of iodine between water and air from solubility, vapor pressure, and hydrolysis equilibrium data are described. Reeults are presanted in tabular form covering the pH range 5.0 to 9.5, the temperature range 25 to 150°C, and dissolved iodine concentrations ranging from aaturated solutions down to 10 mote/liter. (auth) as (ORNL-TM-2792) THORIUM FUEL CYCLE DEVELOPMENT PROGRESS REPORT NO.5, DECEMBER 1969. uk Ridge National Lab., Tenm.), Jan 1970. Contract W-740-eng-36, 0-1-1250, 2103p. Dep. CFSTI. Reasearch progrese is reported on performance of ICPP fuel recovery processes, fluidized-bed Genltration of ICPP product, fuele repr for ERR-1 fuel, zirconium axide fuel provees, operating¢experience in the kiaho Waste Calcining Facility, etorage of solid weste, calcination using in-bed combustion of fuel for beating, waste manegement stadioa, LOFT assistance and other reactor technology support programs. (M4.C.G) 38 fN-1820) URANIUM RECOVERY FROM ALUMINUM A'LOYED FURL [CPP RUN NO. 88. Beadtrees. C. L.; Manile, A.J. (daha Nuclear Corp.. Idaho Falls). Oct 1968. Contrast ATQD-1)-1790, Sip. Owp, CrSTi, About 677 hg of highly eariched urtntum were recovered from aluminum slioy ad fuels during Bum No, 28 m the Idaho Chemical Processing Plant, Overall prodwot recovery ots greater than 4497 percest and all product eastly mee required apectfloetions The fees ory of recevering sapruniom at lc] P wae agats oemoee erred sy rewaeing (88 af the negtunfure in the secund cycle ratfiinste genrcetad during the campeign Presran mitts setines tr thw extra thom wvater ee Lette re + mesing cA TP alge mM ee Mx (ORNL-TM-2646) THORIUM PUBL CYCLE DEVELOPMENT PROGRESS REPORT NO. 8, JANUARY 1970, (Oak Ridge Natiooel Lab, Tem). Contract W~7408-ang-28, Dep. CFSTz Research and development2are reported on head-ord repro~ lag. O4.C.0.) 8 (ORNL-tr-1881) and Y rep PROCKEDURK FOR PRELIMINARY DECONTAMINATION OF NUCLEAR FUELS TO BE PROCESSED. Bathe, Werner; V: Rubert, Translated ty R, Gregg Mexefield (Oak Badge Xa’ Lanb,, Temn,)}, tram German Pataet 3,104,003, @ Dep Cram. A= abetrsct of thie paper, prepered frase the origins! langage, appeared ag NSA 19- 20004. ye tRFBA1416) PREPARATION OF HIGHLY PURF NEPTUNTIUM OXIDE, Canaare, &tltam V2 Procter, Stephen G.