ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
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Part 2. MSBR Design and Development<br />
R B. Briggs<br />
The primary objective of <strong>the</strong> engineering design<br />
and development activities of <strong>the</strong> MSR program is<br />
to design a molten-salt breeder experiment (MSBE)<br />
and develop <strong>the</strong> components and systems for that<br />
reactor. The MSBE is proposed to be a model of a<br />
large power breeder reactor and to operate at a<br />
power level of about 150 Mw (<strong>the</strong>rmal).<br />
A reference design of ii 1000-M~ (electrical)<br />
molten-salt breeder reactor power plant is to provide<br />
<strong>the</strong> basis for most of <strong>the</strong> criteria and for much<br />
of lhe design of <strong>the</strong> MSBE. We have been spending<br />
mosi of our effort on <strong>the</strong> reference design. Several<br />
concepts were described in <strong>ORNL</strong>-4037, our<br />
progress report for <strong>the</strong> period ending August 1966,<br />
and in OKNL-3996, which was published in August<br />
1966. We selected <strong>the</strong> modular concept - four 250-<br />
Mw (electrical) reactors per 1000-Mw (electrical)<br />
station - that has fissile and fertile materials in<br />
separate streams as being <strong>the</strong> most promising for<br />
irnmediate development and have proceeded with<br />
moie detailed study of a plant based on that concept.<br />
Initial results of those studies were reported<br />
in <strong>ORNL</strong>-4119, our progress report for <strong>the</strong><br />
5.1 GENERAL<br />
E. S. Bettis R. C. Robertson<br />
The design program during <strong>the</strong> past period has<br />
primarily been directed toward refinement and<br />
modification of <strong>the</strong> previously reported concepts<br />
for <strong>the</strong> reactor and o<strong>the</strong>r major equipment and re-<br />
visions to <strong>the</strong> cell layouts and piping.<br />
5. Design<br />
E. s. Uettis<br />
63<br />
period ending February 1967. During this report<br />
period, we continued to examine <strong>the</strong> details of <strong>the</strong><br />
reference plant and its equipment. We also summarized<br />
<strong>the</strong> objectives and program for dcvelopment<br />
of <strong>the</strong> MSBE in OHNL-TM-1851.<br />
To date, <strong>the</strong> component and systems development<br />
activity has been concerned largely with support<br />
of <strong>the</strong> design and with planning. The development<br />
program was outlined in <strong>ORNL</strong>-TM-1855 and in<br />
ORN L-TRiI-1856. <strong>Salt</strong> circulation hops and o<strong>the</strong>r<br />
test facilities are being modified for tests of <strong>the</strong><br />
sodium fluoroborate coolant salt, models of graphite<br />
fuel cells for <strong>the</strong> reactor, and molten-salt bearings<br />
and o<strong>the</strong>r crucial components of <strong>the</strong> fuel circulation<br />
pump, Essentially no experimental work<br />
has been done yet.<br />
We plan to complete essential parts of <strong>the</strong> reference<br />
design during <strong>the</strong> next report period and to<br />
bpgin lo design <strong>the</strong> MSRE. Experimerital work<br />
will begin also hut will be limited to a Eew of <strong>the</strong><br />
more obvious important problems. Desiyg and<br />
development on a large scale are planned to start<br />
early in FY 1969.<br />
The major effort was redesign of <strong>the</strong> reactor to<br />
accommodate <strong>the</strong> new data on radiation effects in<br />
graphite. New approaches were tried to arrivc at<br />
a core design which could cornpcnsate for dimen-<br />
sional changes in <strong>the</strong> graphite, but it was finally<br />
decided to simply double <strong>the</strong> volume of <strong>the</strong> core<br />
to lower <strong>the</strong> power density from 40 to 20 kw/liter<br />
and <strong>the</strong>reby assure a stable core life of at least<br />
ten years. It was also decided to include pro-<br />
visions for replacing <strong>the</strong> complete reactor vessel