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ORNL-1816 - the Molten Salt Energy Technologies Web Site

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15. TOWER SHIELDING FACILITY<br />

C. E. Clifford<br />

T. V. Blosser<br />

J. L. Hull<br />

L, B. Holland<br />

F. N. Watson<br />

Physics Division<br />

D. L. Gilliland, General Electric Company<br />

M. F. Valerino, NACA, Cleveland<br />

J. Van Hoomi ssen, Boeing Airplane Company<br />

-ANP R-1 divided shield mockup<br />

ements of <strong>the</strong> radiation around<br />

<strong>the</strong> reactor shield in <strong>the</strong> Tower Shielding Facility<br />

(TSF) reactor handling pool. The experimentation<br />

thus far has also included <strong>the</strong>rmal-neutron flux and<br />

some aamma-ray dose rate measurements in <strong>the</strong><br />

ated a horizontal distance of<br />

shield. This work was in-<br />

of two and one-half weeks so<br />

e TSF could participate in an Air Force<br />

in which a group of monkeys were exposed<br />

massive neutron radiation doses. The work on<br />

<strong>the</strong> G-E experiment has now been resumed.<br />

Analyses of some aspects of <strong>the</strong> TSF data have<br />

been completed and are presented in Sec. 12,<br />

“Sh i el di n g An al y s i s. ”<br />

TSF EXPERIMENT WITH THE MOCKUP OF<br />

THE GE-ANP R-1 SHIELD DESIGN<br />

T. V. Blosser<br />

D. L, Gilliland<br />

J. Van Hoomissen<br />

F. N. Watson<br />

The mockup of <strong>the</strong> GE-ANP R-1 reactor shield<br />

design (Fig. 15.1) is being used at <strong>the</strong> TSF for a<br />

series of measurements. Fast-neutron and gamma-<br />

ray dose rates were measured around <strong>the</strong> reactor<br />

shield section while it was submerged in water in<br />

<strong>the</strong> reactor handling pool. In addition, <strong>the</strong>rmalneutron<br />

flux and gamma-ray dose rate measurements<br />

have been made in <strong>the</strong> detector tank located a<br />

fixed horizontal distance from <strong>the</strong> reactor shield.<br />

The reactor loading for this experiment (Fig.<br />

15.2) was a 5 x 7 fuel element array which gave a<br />

etrical power distribution throughout <strong>the</strong> retor.<br />

In order to avoid excess reactivity, a fuel<br />

t was removed from <strong>the</strong> center of each of<br />

-element faces. The measurements<br />

t <strong>the</strong> points indicated in Fiq. 15.1<br />

ulk Shielding Facility Tests on<br />

ShieldMockup, <strong>ORNL</strong> CF-54-8-94<br />

ANP Quar. Prog. Rep. Mar. 10,<br />

-<br />

were compared with similar measurements made<br />

earlier at <strong>the</strong> BSF.’<br />

In general, <strong>the</strong> BSF and TSF data were in agree-<br />

ment, as is indicated in Figs. 15.3 and 15.4. How-<br />

ever, <strong>the</strong>y were not in complete agreement, largely<br />

because of differences in <strong>the</strong> experimental setups<br />

at <strong>the</strong> two facilities. For example, while <strong>the</strong> TSF<br />

had a symmetrical power density distribution, <strong>the</strong><br />

fuel element loading at <strong>the</strong> BSF gave an asym-<br />

metrical distribution which had a maximum 8.1 cm<br />

from <strong>the</strong> center line of <strong>the</strong> reactor grid. Also,<br />

only compartments A and D contained borated water<br />

at <strong>the</strong> BSF, whereas at <strong>the</strong> TSF all compartments<br />

contained borated water for <strong>the</strong> first in-pool meas-<br />

urements. Later, plain water was used in Com-<br />

portment D. The BSF boration was 1.1 wt %, while<br />

<strong>the</strong> TSF boration was 0.85 wt %. For <strong>the</strong> measure-<br />

ments off <strong>the</strong> rear section at <strong>the</strong> BSF, no lead or<br />

iron side shielding was present, while at <strong>the</strong> TSF<br />

<strong>the</strong> side shielding shown in Fig. 15.1 was in<br />

position, For <strong>the</strong> measurements off <strong>the</strong> front and<br />

side sections, <strong>the</strong> side shield at <strong>the</strong> BSF had a<br />

total of 1 in. less steel than <strong>the</strong> side shield at <strong>the</strong><br />

TSF.<br />

Measurements of <strong>the</strong> neutrons scattered into <strong>the</strong><br />

side of <strong>the</strong> detector tank (located a horizontal<br />

distance of 70.8 ft from <strong>the</strong> G-E reactor shield)<br />

were made as a function of altitude. The flux<br />

(Fig. 15.5) is a slowly varying function of <strong>the</strong><br />

altitude, and it exhibits a peak at about 35 ft.<br />

A decrease of about 6% in <strong>the</strong> readings between<br />

150 and 200 ft indicates that <strong>the</strong> ground-scattered<br />

neutrons are still observable at <strong>the</strong>se altitudes for<br />

this particular reactor-shield combination. The<br />

shape of <strong>the</strong> curve is quite different from that ob-<br />

tained in <strong>the</strong> differential shielding experiments<br />

with <strong>the</strong> water tank,:! because <strong>the</strong> G-E shield<br />

2C. E. Clifford et aL, Preliminary Study of Fast Neutron<br />

Ground and Air Scattering at <strong>the</strong> Tower Shielding Facility,<br />

<strong>ORNL</strong> CF-54-8-95 (Aug. 23, 19541.

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