ORNL-1771 - Oak Ridge National Laboratory

AMP QUARTERLY PROGRESS REPORT
A device for studying the ratcs 3f growth of
tube-wall deposits has heen successfully tested
with a simple heat transfer salt. Also, a hydso-
dynamic flow system for sti~dying ths r-flector-
maderated reactor flow structure has bseii tested.
A mcsthematical study of the ternperdure structure
in converging and in diverging channsl systems
that duct fluids with volumetric heat SOU~CCS and
a study of wall cooling requirements in circulating-
fuel reactors were made.
Radbatim Damage
Additional irradiations of lnconel CapsuOes containing
fluoride mixtures '?awe carried out ir-i the
MTR (Sec. 9). Only one capsule containing a
UF,-bearing fuel has been examined, a d it shows
no corrosion, in contrast to that found previously
with UF4-bearing fuels.
Inspection of the k.ITR in-pile loop, whish failed
prior to startup, disclosed that the failure was
caused by o break in the weld connecting the pump
discharge nipple to the fuel line. Design revisions
and refotaricatiow of some of the ports are in prog-
ress. De-velapmental work continued on a sniuller
loop for operation in UIP LITR &piece+
Detailed examination of an Incoilzl loop which
circulated sodium at high temperature in the ORNL
Graphite Reactor showed no evidence of radiation-
induced corros ion. Metal lograph i c exam i not i ons
were carried out in the hot cells oil irradiated fuel
plates for Pratt R Whitney Aircraft Division, und
studies were made on annealing-out of fission-
fragment darnage. Y!mk continued on examination
of wirc arid multiple-plate-type units for GE-ANP.
Analytical Studies of Reactor u?rla~erta!s
The primary analytical problem continues to be
the separation on$ determinntion of trivaIer3t and
tetravalent uraniiiiii in hoth NnF-ZrF, and NoF-
KF-l-iF-base furls (SX. 10). A successful POtentiornett-ic
fitration of UF, in m0li-n NaZrF,
with metallic zirconium was accompl ishcd by
means of polarized platinum c!cc:rodcs, '[he sclubillity
of UF, in NaAlC1, was determined to be
18 iiq/g at 200°C, in contrast to o solubility if
UF, of less than 1 mg/g. The:zfora molten
NaAICI, is expected to dissolve tetravalent ura-
nium selectively Crow the 4ue!s.
Calibration measurements have tisen cornplated
on the apparatus for thc determination nf oxygen
as metallic oxides in rractor fuels. I he reaction
4
,. ~
involves the hydsofluorination of the oxide and
mensuremant sf the increase in conductivity of
liquid MF as a function of the water formed. In-
vestigiaticns are being mode of the oxidation of
UF, id of UF, with oxygen at elevated tempesa-
tures,
An improved method for the determination of
lithium in NaF-KF-Li F-base fuels was developed.
Also, studies were mode of the solubilities of
potassium, rubidigsm, and cesium tetraphenyl-
borates in various organic solvents to uscertain
d ifferanti al so I ub i I i f ie s.
PART Ill. SHIELDING RESEARCH
Sh ia I Cli ng Analysis
Application of the Monte Carlo method to the
calculation of gamma-soy penetration of crew
shield sides has been worked out, and the method
appears to be quite satisfactory for this type of
problem (SEX- B 1). Considerable progress has been
made on understanding the Tower Shielding Fa-
cility (TSF) measurements of ground and air
scattering, Expressions have been derived which
describe the effect of ground interference with the
air-scattered flux, nwd thus it is now possible to
estimate ground-scattered radiation both at the
TSF and in an airplane at landing and takeoff.
Calculations have been set up for evaluating
multiply scattered radiation in air, The values
obtained WI II be of considerable importance in
studies of the highly asymnietsic but light shields
era1 current designs.
Lid Task Shialdisg Facility
Pieparations for a second series of shielding
tests for the reflector-moderated reactor at the
Lid Tunk Shielding Foci lify (LTSF) Rave included
the consiiuction of a large tank which will hold
all the components of the raiockups and the irradi-
ation of the LJF,C,F,, salution which may be
used to simulate the reactor fuel in mockup ex-
periments (Sec. 12). h4casurenients of the removal
cross section nf carbon made in a continuous
carbnr; m5dium hove resulted in a value of
-
ur = 0.750 ban. Ihis is to be compared with the
prca :ous VUIUS of 0.81 + 0.05 barn measured behind
0 solid slab of graphite. Thermal-neutron flux
ti~easursmcnts have been made beyond two configurations
of GF-ANP helical air ducts, a single
duct arid o tricngvlni array of three ducts. Measurements
beymd a 35-dt~cf array will begin soon.