05.08.2013 Views

ORNL-2106 - the Molten Salt Energy Technologies Web Site

ORNL-2106 - the Molten Salt Energy Technologies Web Site

ORNL-2106 - the Molten Salt Energy Technologies Web Site

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

ANP PROJECT PROGRESS REPORT<br />

transfer calculations of Robinson and Weekesl’<br />

were modified to apply to <strong>the</strong> presently planned<br />

position for <strong>the</strong> loop in <strong>the</strong> LlTR by using certain<br />

simplifying assumptions. The tip of <strong>the</strong> loop is<br />

to be 1.5 in. below <strong>the</strong> center line of <strong>the</strong> reactor.<br />

This is more than 4.5 in. below <strong>the</strong> position of<br />

maximum flux. The flux measured near <strong>the</strong> fuel<br />

tube in <strong>the</strong> previously operated loop” was taken<br />

as <strong>the</strong> depressed flux for that loop. it was assumed<br />

that <strong>the</strong> flux depression was <strong>the</strong> same for corre-<br />

sponding parts of <strong>the</strong> present loop. The difference<br />

in shape of <strong>the</strong> flux profile for <strong>the</strong> two loop po-<br />

sitions was ignored in calculating <strong>the</strong> fuel tube<br />

wal I temperature differential. Fi s sion-product<br />

poison contributions to <strong>the</strong> macroscopic cross<br />

section of <strong>the</strong> fuel were assumed to be negligible.<br />

12M. T. Robinson and D. W. Weekes, Design Calcu-<br />

lations for a Miniature Higb-Temperature In-Pile Circu-<br />

lating Fuel Loop, <strong>ORNL</strong>-1808 (Sept. 19, 1955).<br />

3<br />

-<br />

3<br />

0<br />

x 2<br />

B<br />

s<br />

J<br />

J<br />

w<br />

m<br />

3<br />

c<br />

J<br />

W<br />

3<br />

LL<br />

t’<br />

X<br />

3<br />

J<br />

LL<br />

240<br />

0 0<br />

The transmission coefficient for neutrons in <strong>the</strong><br />

fuel was determined from work reported by Holmes,13<br />

and it was used in conjunction with <strong>the</strong> flux distri-<br />

bution along <strong>the</strong> loop, as shown in Fig. 4.2.12,<br />

to determine <strong>the</strong> total loop power.<br />

Finally, to find <strong>the</strong> temperature differential<br />

through <strong>the</strong> lnconel fuel tube wall, <strong>the</strong> curves of<br />

heat transfer variations along <strong>the</strong> loop designated<br />

Mark Vlll in <strong>the</strong> work of Robinson and Weekesl’<br />

were modified for <strong>the</strong> higher total power of <strong>the</strong><br />

loop being investigated. A plot of <strong>the</strong> calculated<br />

temperature differential through <strong>the</strong> tube wal I vs<br />

<strong>the</strong> position on <strong>the</strong> loop for proposed operating<br />

conditions is presented in Fig. 4.2.13. The maxi-<br />

mum combined temperature corrections for all three<br />

errors totaled 3sOC.<br />

13D. K. Holmes, Problems of Neutron Population in<br />

Localized Absorbers, <strong>ORNL</strong> CF-56-1-141 (Jan. 27,<br />

1956).<br />

50 00 4 50 200<br />

DISTANCE ALONG LOOP FROM INLET TO COOLED SECTION (cm)<br />

W<br />

uwwmwub<br />

<strong>ORNL</strong>-LR-DWG 14747 .<br />

Fig. 42.12. Calculated Profile of Flux at Fuel Tube Surface Along <strong>the</strong> LlTR Vertical In-Pile Loop. .<br />

2 50<br />

a<br />

L

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!