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ORNL-2106 - the Molten Salt Energy Technologies Web Site

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ANP PROJECT PROGRESS REPORT<br />

5<br />

5<br />

2<br />

4ezmw<br />

<strong>ORNL</strong>-LR-DW I4917<br />

1<br />

0 0.04 0.08 a12 0.16 0.20 0.24<br />

THICKNESS OF LAYER (em)<br />

Fig. 1.2.2. Heating in Copper-Boron Layer By<br />

Alpha Particles from <strong>the</strong> B"(n,a)Li' Reaction.<br />

The heating from sources 10 to 14 was neg-<br />

lected. Their combined contributions to <strong>the</strong><br />

heating in <strong>the</strong> region being considered was<br />

estimated to be about 5% of <strong>the</strong> total heating.<br />

The fuel region of <strong>the</strong> core of <strong>the</strong> reactor was<br />

assumed to be a spherical shell 5.125 in. thick<br />

with an outside radius of 10.5 in.' This region<br />

was divided into13 spherical shells of thicknesses<br />

varying from 0.27 cm to 2 cm. The source strength<br />

(in watts/cm3) of <strong>the</strong> prompt gamma rays in each<br />

shell was assumed to be proportional to <strong>the</strong><br />

average fission power in each shell, which was<br />

calculated (from ref. 2) at <strong>the</strong> equatorial plane of<br />

'w. L. Scott, Jr., Dimensional Data for ART, <strong>ORNL</strong><br />

CF-56-1-186 (March 13, 1956).<br />

2A. M. Perry, Fission Power Distribution in <strong>the</strong> ART,<br />

<strong>ORNL</strong> CF-561-172 (Jan. 25, 1956).<br />

30<br />

<strong>the</strong> reactor. The source strength of <strong>the</strong> decay LJ<br />

gamma rays was assumed to be <strong>the</strong> same for each<br />

fuel shell.3<br />

The average source strength of gamma rays<br />

resulting from inelastic neutron scattering in <strong>the</strong><br />

fuel was calculated4 by using <strong>the</strong> output of<br />

multigroup calculations5 performed by <strong>the</strong> Curtiss-<br />

Wright Corp. on ART-type reactors with spherical<br />

t<br />

symmetry.6 The inelastic cross sections used<br />

for <strong>the</strong> fuel were those reported in ref. 3. This<br />

calculation had been performed before all <strong>the</strong><br />

data in <strong>the</strong> latter reference had been accumulated,<br />

so it was assumed that, for each inelastic<br />

collision, one-half <strong>the</strong> average neutron energy in<br />

each energy group was given off as I-MeV gamma<br />

radiation. Calculations made by using <strong>the</strong> more<br />

recent data indicate that <strong>the</strong> source strength<br />

used was too high by about 50%. The total heating<br />

values given in Fig. 1.2.1 may <strong>the</strong>refore be about<br />

5% too high. This error is partially compensated<br />

for, however, by <strong>the</strong> neglect of sources 10 through<br />

14.<br />

The prompt and decay gamma-ray spectra7<br />

were divided into four energy groups with average<br />

energies for each group of 0.5, 1, 2, and 4 Mev.<br />

The last four groups listed in ref. 3 were combined<br />

into one group with an average energy of 4 Mev.<br />

The heating at <strong>the</strong> various places described in<br />

Fig. 1.2.1 was calculated by summing <strong>the</strong> contributions<br />

from each energy group from every fuel<br />

shell.<br />

It was assumed for <strong>the</strong> calculations that each<br />

fuel shell was replaced by an infinitely thin<br />

spherical-she1 I source embedded in an infinite<br />

homogeneous medium so that <strong>the</strong> standard transformation<br />

from a spherical-shell source to two<br />

L<br />

infinite-plane sources would apply, that is, so<br />

that <strong>the</strong> heating at R, h(R), would be given by<br />

(1) h(R) = _L. [ H(R - Y) - H(R + Y) ,<br />

R 1<br />

3H. W. Bertini et al., Basic Gamma-Ray Data for<br />

ART Heat Deposition Calculations, <strong>ORNL</strong>-2113<br />

(in press).<br />

4Calculatio~ir performed by R. B. Stevenson, Pratt 8,<br />

Whitney Aircraft, private communication to H. W.<br />

Bertini.<br />

'S. Strauch, Curtirs-Wright Corp., private communi-<br />

cation to H. W. Bertini.<br />

6H. Reere, Jr., S. Strauch, and J. Michalcozo,<br />

Geometry Study far an ANP Circulating Fuel Reactor,<br />

WAD1901 (Sept. 1, 1954).<br />

7H. W. Bertini, C. M. Copenhaver, and R. B. 2<br />

Stevenson, ANP Quar. Prog. Rep. March 10. 1956.<br />

<strong>ORNL</strong>-2061, P 35.<br />

c<br />

*

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