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STUDY OF ADVANCED SHIELDING MATERIALS
W. R. Burrus' J. M. Miller
W. J. McCoo12 D. R. Otis3
J, Smolen2
An extensive mockup experiment was initiated
in which combinations of advanced shielding ma-
terials, such as lithium hydride, depleted uranium,
zirconium, and tungsten, are being investigated.
These tests are important to the ANP program
because lead and water, the prototype shielding
materials used in most of the previous Lid Tank
Shielding Facility (LTSF) mockup tests, are not
optimum aircraft construction materials. In the
initial tests the shielding materials being studied
are combinations of lithium hydride and other
shielding materials immersed in transformer oil.
The particular configurations used have been those
of immediate interest in the GE-ANPD program, but
such general interest surrounds the use of these
materials that the more reliable data obtained thus
fqr are presented here. This report is preliminary,
however, in the sense that little analysis work has
been performed.
'On assignment from U. 5. Air Force.
'On assignment from Prott 8, Whitney Aircroft.
30n assignment from Convoir, Son Diego.
',&-in.-THICK AI PRESSURE PLATE
Y-in.-THICK A1 PLATE
/ /k-in.-THICK. 2f% ENRICHED UZ3' SOURCE
5.2. LID TANK SHIELDING FACILITY
R. W. Peelle
PERlOD ENDlNC JUNE 10, 1956
Thermal-neutron flux and gamma-ray tissue dose-
rate measurements have been made for configura-
tions involving combinatjons of zirconium, lead,
and depleted uranium with lithium hydride and
transformer oil. All the measurements were made
in the oil along the axis of symmetry of the LTSF
source plate. (Fast-neutron dose-rate traverses
were also mode, but experimental difficulties pre-
vent the publication of reliable data at this time.)
A typical configuration (No. 69-60) is shown in
Fig. 5.2.1. The various material combinations
studied differed only in the region to the right of
the line marked "beginning of configuration." The
parameters of all the configurations are given in
Table 5.2.1, and the known properties of the
vartous materials arp given in Table 5.2.2. The
lithium hydride is the only material that was
canned in an extraneous material.
All the radiation levels indicated in plots of the
data (Figs. 5.2.2 through 5.2.9) are quoted per watt
of effective source plate power, based on a total
power of 5.5 k0.5 w for the 28-in.-dia source plate.
A final evaluation of the effective power may ne-
cevsitate a small change in the resvlts presented
here. All the thermal-neutron fluxes reported are
equal to the neutron density times 2200 m/sec.
The decreasing magnitude of the slope of the
neutron traverses shown in Fig. 5.2.2 at large
2-01-007-69-272
Fig. 5.2.1. Typical Configuration for LTSF Mockup Tests of Advanced Shielding Materials.
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