ORNL-1771 - Oak Ridge National Laboratory

chrome V fuel elements have been completed.8
Examinations of two single-plate fuel elements9
and one two-stage multiple fuel plate test as-
sembly” were also completed. kork will continue
on both wire and multiple-plate elements.
Expansion of remote metollograpkic facilities is
proceeding.
F ISSION-FRAGM ENT ANN EALlNG STUDIES
M. J. Feldmon W. Parsley
Solid State Division
Because of interest in the possibility of the
removal of the radiation damage to fuel plates by
annealing, a preliminary study was undertaken.
The eight samples in Pratt 8, Whitney capsule
1-9 (four were small particle sire, (3-p UO, and
four were large particle size, 15- to 44-p UO,)
were selected for the study. One sample from each
group (large and small particle size) was examined
after the following treatment: (1) as irradiated,
(2) 900°F anneal for 24 hr, (3) 1100°F anneal for
24 hr, and (4) 1400°F anneal for 24 hr. A graph
showing the results of this preliminary study is
shown in Fig. 9.8. The conclusion drawn fron.
this initial study is that a portion of the neutron
damage to the samples has been annealed out.
Since the full annealing temperature for type 347
stainless steel is about 1800°F (for complete
removal of the effects of cold work), a complete
anneal for neutron damage at 1400°F bas not
expected. For the core, where the maior portion
of the damage is by fission fragments, it is felt
that the curve shows a reduction in hardness be-
cause of a partial anneal of the neutron darnage
with no reduction in the fragment damage. An
attempt will be made to determine the anneal nec-
essary to remove all the neutron damage from this
type of material and, if possible, the fission-
fragment annealing temperatures.
HIGH -T E MP E R AT U RE, SH 0 RT -T IM E, G RAIN-
GROWTH CHARACTERISTICS OF INCOMEL
M. J. Feldman W. Parsley
A. E. Richt
Solid Stat; Division
As an aid in the onolysis of the static corrosion
capsules, a study of the short-time, high-fempero-
ture, grain-growth characteristics of the lnconell
‘NI. J. Feldman et al., Metallogtuphical Analysis of
G.E. Wire Fuel Elemvnt No. 1, ORNL CF-54-4-8 (April
1, 1954).
PERlOD ENDlNG SEPTEMBER 10, ‘1954
stock used for the tests was made. information
is available in the literature on the usual times
and temperatures for lnconel grain growth, but
because of the nature of the experiment, with its
possibilities of local short-time hot spots in the
fuel, this study was iniliated. Figure 9.9 is a
graph of the data obtained. Of major interest were
the definite temperature dependence of the carbide
solubility and the extremely short times (relative
to the corrosion test times) at which large grains
could be produced. Details of the experiment have
been published.”
BNL NEUTRON SPECTRUM - RADIATION
DAMAGE STUDY
J. B. Trice P. M. Uthe
Solid State Division
f?. Bolt J. C. Carroll
N. Shiells
California Research Corporation
V. \Val sh
Brookhaven National Laboratory
A series of measurements were made in hole
E-25 of the Brookhaven reactor to determine neu-
tron flux energy distributions. The project was
a cooperative effort with California Research Cor-
poration and Brookhaven National Laboratory. In-
formation obtained from these measurements is to
be used to correlate neutron flux intensity and
energy distribution with radiation damage to cer-
tain lubricants and organic compounds that have
been irradiated in E-25 and exomined by CRC.
Data for the irradiated samples have been coded
for the ORACLE by the ORNL Mathematics Panel
so that the large number of arithmeticol compu-
tations usuolly required by o threshold detector
experiment can be performed in a shorter period
of time than is usual.
‘A. E. Richt and R. N. Ramsey, Metallographiral
Analysis of Single Plate Fuel Elements GE-ANP 30
and 3C, QRNL CF-54-3-42 (March 9, 1954).
’OM. J. Feldrncrn et al., MrtalIogtaphic Analysis of
Tnuv-Stage MTR Test Speczrpen CE-ANP-10, QRNL
CF-54-7-77 (July 9, 1954).
’M- J. Feldman et al., Fhort 7‘zme-High-Temperuture
Grain Growth Charucteristzr of litconel, ORNL CF-54-
6-70 (June 8, 1954).
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