ORNL-4191 - the Molten Salt Energy Technologies Web Site

ather than just the core and to provide space to
store the spent reactor within the biological shielding
of the reactor cell. While this new design represents
the present status of graphite technology,
we believe that an improved graphite will be developed
within the next few years and that longer
core life or higher power density than used here
can be expected in the future.
Analysis of the thermal expansion stresses in
the various systems indicated that rather extensive
modifications were needed. Changes were therefore
made in the plant layouts, the equipment supports,
and in the arrangement of the salt piping,
with the result that the calculated stresses in the
vessel atta.chments, supports, and piping systems
now fall well within the acceptable values.
Calculations of the radiation flux levels at the
reactor cell walls allowed designs to be prepared
for the ihermal shielding used to protect the concrete
from excessive temperatures. Drawings were
also made for the general cell wall design, including
the closure blocks at the top, the cell
penetrations, etc.
Relatively few changes were required in the
MSBH flowsheet during i.he past period, but for
convenience it is presented again in Fig. 5.1.
The MSBR design study is expected to be compkte
within the next few months. The description,
cost, and performance data for the steam system
will probably need little change but will be updated
as required. The August 1966 design study
report on a 1000-Mw (electrical) molten-salt breeder
reactor power station (ORNL-3996) will be revised
to present firmer cost estimates based on the new
and more detaiied designs for the reactor plant.
5.2 CELL ARRANGEMENT
C. E. Bettis W. 'Terry
H. L. Watts
€1. A. Nelms
J. I?. Rose
C. W. Collins
W. E