05.08.2013 Views

ORNL-1816 - the Molten Salt Energy Technologies Web Site

ORNL-1816 - the Molten Salt Energy Technologies Web Site

ORNL-1816 - 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 QUARTERLY PROGRESS REPORT<br />

- .-<br />

B<br />

5<br />

\<br />

- :<br />

W<br />

3<br />

B<br />

z<br />

8<br />

3<br />

W z<br />

Li<br />

e<br />

W<br />

0<br />

m<br />

a<br />

4<br />

a<br />

L<br />

lo-’<br />

10-2<br />

m W<br />

bEeRK<br />

2-01 -056- 3-T4A<br />

10-3 IO-^ I<br />

10-4 1cr5 g<br />

10-7<br />

0 10 20 30 40 50 60 70<br />

DISTANCE FROM SHIELD SURFACE (crn)<br />

e<br />

0<br />

.F<br />

s<br />

- ‘E<br />

a<br />

W m<br />

8<br />

z 0<br />

+<br />

10-6 $<br />

Fig. 15.3. Fast-Neutron Dose Rate Measure-<br />

ments in Water Near GE-ANP R-1 Mockup.<br />

160<br />

!i<br />

s<br />

+ z<br />

B<br />

IL<br />

-<br />

10-1 2-01-056-3-T3A<br />

5<br />

5<br />

2<br />

(0-6<br />

0 10 20 30 40 50 60 70<br />

DISTANCE FROM SHIELD SURFACE (cm)<br />

Fig. 15.4. Gamma-Ray Dose Rate Measurements<br />

in Water Near GE-ANP R-1 Mockup.<br />

mockup emits neutrons in a direction more favorable<br />

for ground scattering. The intensity from <strong>the</strong> G-E<br />

shield peaks at about 55 and 120 deg from <strong>the</strong><br />

reactor-detector center line and is symmetrical<br />

about <strong>the</strong> reactor-detector axis.<br />

Measurements were also made of <strong>the</strong> <strong>the</strong>rmal-<br />

neutron flux and <strong>the</strong> gamma-ray dose rates within<br />

<strong>the</strong> detector tank at an altitude of 195 ft. The<br />

G-E reactor shield was a horizontal distance of<br />

64 ft from <strong>the</strong> detector tank, and, for <strong>the</strong>se meas-<br />

urements, five 1-in.-thick lead slabs were installed<br />

1 ft from <strong>the</strong> rear face (reactor side) of <strong>the</strong> tank.<br />

The lead slabs simulated <strong>the</strong> shielding in <strong>the</strong> crew<br />

compartment.<br />

A knowledge of <strong>the</strong> <strong>the</strong>rmal-neutron flux di stri-<br />

bution in <strong>the</strong> detector tank is useful in extending<br />

<strong>the</strong> fast-neutron dose rate measurements into<br />

regions where <strong>the</strong> intensity is too low to be meas-<br />

ured with <strong>the</strong> dosimeter. This distribution is also<br />

necessary for predicting <strong>the</strong> capture gamma-ray<br />

intensity to be expected in <strong>the</strong> crew shield. The<br />

‘ r<br />

-<br />

i -<br />

d

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

Saved successfully!

Ooh no, something went wrong!