aN
Apr. 15, 1971
CHEMISTRY
Nuclear Fuel Services, Inc., West Valley, N, ¥.).
~p. Dep, NTIos.
21 Jan 1971.
Envirenmental monitoring, low level liquid effluents, stuck
wtheents, and periodic testing are reported. (M.C.G 3
seco
,DOUCKET-50201-62) WEST VALLEY REPROCESSIMG PLANT.
environmental sample Data.
(Division of Maieriang ,and! Licensing (AEC), Washincton, D. C,).
gL Aug £970,
i22p, Dep. NTIS,
Dura on radiation monitoring for the lirst three quarters ot
i963 are presented. Data for grass wy, 3, and y in plants, sels,
BEurermilk Creek, Cattaraugus Creek, drinking water, and holdup and burial lagoons are given. Tritium data are given for
driniieg water and tritium and *'Sr data are included for the
creeks and lagoons. (M..'.G.)
13081
(NP-18577)
INVESTIGATION OF REPROCESSING
INPUT MEASUREMENT USING TRACER TECHNIQUE, Bokelung, 7. (European Company for the Chemical Procersing of
iyridiited fuels, Mol (Belgium),
Dap, NTIS (U, 5S. Sales Only},
Oct 1970,
Sip,
(ER TR 2o6),
The quantities of uranium and/or piutonium fed mto a repro-
cessing plant are currently found by multiplying the dissolver solutien batch size (volume or weight) by the concentrations of these
siements as found by analyses of sampies taken from the batch.
an independent verification of the volume measurement using
tracer techniques is proposed. The basic concept is that of
isotope dilution mass spectrometry applied to the dissolver
soiution into which, at the outset, a known amount of ‘Li is mixed
as '‘recer. Samples of the solution are spiked with °Li, “U, and
py for mass spectrometry. The measured ratio ®Li/"Li verifies
the catch size (volume or weight}, whereas the concentration
ratios U/Li and Pu/Li give the quantities of these fissile matcrials,
(ke). ia the batch. The solution of the "Li spike is calibrated
againat a dilution of the "Li solution used to trace the disselver
solutiun; the batch size can thus be found merely as a ratio of
two Li/'Li ratios, thereby circumventing the complicated ab-
salute standardization of the ‘Li additive. The asscts of the Li
concen? are discussed in terms of process compatibility, analytical sensitivity, precision, and price. The chemical separation of
Li frsva the dissolver solution prior to its determination by masa
spectrometry is described. Results on simulated input solutions
show tne capability of the system under laboratory conditions to
be about 0.3% relative standard deviation. (auth)
13022
{(RLO-2225-T-11-1) DYNAMICS OF SOLVENT EXTRACTION SYSTEMS, Il], Progress Report No, 8, Octoher 1,
1969--September 30,1970. Babb, Albert L,; Garlid, Kermit L,
(Washington Univ., Seattie, Dept. of Nuclear Engineering),
Oct
19TU, Contract AT(45-1)-2225, 8383p. Dep. NTIS.
Controlled cycling operation of a pulsed, sieve-plate extraction
column was studied. The significance of design varizbles and
operating variables on extraction efficiency and columin throughout vas established. Random variations in organic phase holdup
were measured and analyzed. A computer model was developed
for desorlbing typical dynamic operation of extraction systems.
(M.O.G.)
13053
(WHAN-FR-33)
APPLICATION OF AQUEOUS FECH-
NOLOGY TO LMFBR SEPARATIONS PROCESSES.
PROGRAM
PLAN FOH TASK T-2: FUEL DISSOLUTION CHARACTERISTICS,
Lerch, R, £.
{WADCO Corp., Richland, Wash.),
Contract AT(45-1)-2170,
38p.
Dep, NTIS.
Dec 1970,
A devalopment program for investigating the effects of fuel
fabrication varlables and irradiation history on the dissulution
characteristics of LMFBR fuels in nitric acid ia outlined. Studies
Will inciusts moasurements on tho dissolubility and dissolution
Tate of various unirradiated and irradiated mixed plutonium -uraNium oxides ia nitric acid. An effort will be made to establish
how hisselubility and dissolution propertias vary with composition,
fabrication, and conditicns of breeder reactor exposure. Methods
MOY pregicting dissolubility and dissolutioi behavior of unirradiated and irratiated mixed oxide fuels from fabrication and irradiation Paranctors will be developed. Initial experiments were
mace te determine feasibility of the studies and to establish fractlonation yariablea to bo considered. (J.G.B.)
15034
loN EXCHANGE PROPERTIES OF CRYSTALLINE
ZMCONIUM PHOSFHATE.
H,
Harvie, Sylvia J.; Nancotlas, George
(Stata Univ. of Naw York, Buffalo).
32: 3943-37(Ue0 1970).
J, Inorg. Nucl, Chem,;
Eouiiiurium and linetic studics were made at 25°C of the exchasse of iSiium, palum, petassium, calelum, and strontium
LY on crvstaHline civconium phosphoric. The results are conStitoat yw cu the cadetence of several dictlnet crystalline phasea
Of ts aecal forma, As wag found for the semicrystalline mateTIM Lye Lrepertion of crystalline circcnium phosphate are to
1273
some cxtent dependent on the method of preparation of the particular form. wauth (UK
13085
CONTRIBUTION TO THE ELEMENTARY INTEGRA=
TION OF VON LESE AR TRANSPORT EQUATIONS IN [ISOTOPE
SPPARATIOCL.. PARTI. Zicger, K. (Institut fuer Stabile Isolupe, Leipzig). isutopenpraxis; 6: 316-18(Sep 1970), (In German),
A large ciages ol ..otope separation procedures can be deseribed untformiy by Cohen’s transport equations. In the simplest
case au system of two lirst order partial differential equations of
the hyperbolic type exist. This nonlinear system is reduced by a
suitable substituron t. a tinear differential equation of second
order, Then problem formulations are confined, for which not
only the differential equation but also the boundary and initial
conditions are Jinear after the reduction, (auth)
13086
INN ESTIGATION OF SPONTANEOUS SILVER PRECIPITATION ON VOWDERY PLATINUM IN NITRIC SOLUTIONS,
Toth, G,; Puessy, FE, inst. for Isotope, Budapest). Isotopenpraxis; 6: 307-9(5ep 1°70). (In German),
It was found thut silver ions precipitate on hydrogenated platinum powder, while with mitrie acid concentration between 5 and
0.901 N the muximum precipitated quantity does not come up to
the value cycling the monomolecular layer. Though the values
obtained through measuring with regard to the dependence of the
precipitation upon concentration formally seem to cover the
Langmuir equation, the values determined by means of this equation showed some dependence on pH values, and did not correspond with the SET surface. Spontaneous silver precipitation on
platinum powder can be used for the separation of radioactive
silver isotopes. (auth)
13087
\soAINISSEMENT ET DECHETS RADIOACTIFS.
(Antipollution und Radioactive Wastes). Rodier, Jean; Vernhes,
Claude. Paris; Duned (1970). 127p.
The dangers connected with radioactive wastes and their administrative consequences are examined. Radioactive wastes and
their different treatments are classified and their conditioning and
finai disposal discussed. The cost of administrating radioactive
wastes ib estimatcd, (France)
13088
CHEMICAL SEPARATION OF RUTHERFORDIUM.
Silva, Ru: tlarris, J.: Nurmia, M.; Eskola, K.: Ghiorso, 4. (Law-
rence Radiation Lab, Berkeley, Calif.).
Inorg. Nucl. Chem,
Lett.; 6: 871-7(Dec 1970}.
.
Element 104 is expected to fall into group IVB, i.e., to be ekahafnium. It is predicted to have a valence and ionic radius similar to Zr anid Hf and to exhibit similar chemical properties.
Previous studics with actinide elements showed that cation exchange columns using chelating agents as eluants could provide
rapid chemical separations on ane atom at a time and yield
sources suitable for alpha energy analysis. These methods were
developed further in order to test the above predictions. The behavior of the activity assigned to element 104 with mass 261 was
found to be entircly different from trivalent and divalent actinide
elements but similar to Hf and Zr as predicted. (UK)
13089
POTENTIAL CHLORIDE ELECTROLYTES FOR RE~
COVERING THE METALS Ti, Zr, AND Hf BY FUSED SALT
ELECTROLYSIS,
Flengas, S, N.; Pint, P.
Can, Met, Quart; 8:
(Univ. of Toronto).
151-66(Apr-Jun 1969),
The properties of potential electrolytes for recovery of Ti. Zr,
and Hf by a fused sait electrolytic process employing solutions of
TiCh, 2@rcl,, and HEC], in alkali and alkaline earth chloride melts
are discussed in terms of thermal stability. Pressure—tempernture relationships for these aystems are analyzed, and methods
for calculating activities of complex ionic speries in solution are
presented. (auth) (Canada)
13090
PROCEDURE FOR RECOVERY OFFISSILE MATERIALS IN CHEMICAL DECLADDING SOLUTIONS, Faugeras,
Pierre; Kikindai, Tivadar (to Commissariat a l’'Energie Atomique). French Patent 1,586,431. 12 Jan 1970. Filed 20 Aug
1968. (In French).
A deciadding solution, cbtained from the dilute nitric acid
attack of metal cladding, ia subjected to a selective crystallization of the salts present in order to ellmtnate the crystals of
cladding metal nitrate, the soluble nitrates of flasile materials
being Jett in solution, The solution collected, after elimination of
the crystals, is sent to the unit where the rods of fissile material
are dissolved after dectadding. (auth) (France)
73091
ION-EXCHANGE SELECTIVITY OF THE SYNTHETIC
ZEOLITE LINDE A IN ANHYDROUS AND MIXED MEDIA, Barrett, lt, .; Marinsky, J. A, (Stata Univ, of New York, Buffalo).
Contract AT(S0-1)-2269. J. Phys. Chem.; 75: &5-9(7 Jan 1971).
The selecuvity coefficients for the ion exchange of cesium with