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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

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