ORNL-1771 - Oak Ridge National Laboratory

ORNL-1771 - Oak Ridge National Laboratory ORNL-1771 - Oak Ridge National Laboratory

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The thermal-neutron flux (Fig. 13.2) was measured behind each of the three graphite slab thicknesses to a distance of 300 crn from the reactor face, Measurements were made with a 3-in. U235 fission chamber, an %in. BF, counter, and a 124-in. 1 BF, counter, foil data. and the data were normalized to indium Fast-neutron measurement5 (Fig. 13.3) were made with a three-section neutron dosimeter. Gamma-ray measurements (Fig. 13.4) were taken PERIOD ENDING SEPTEMBER 70, 7954 behind each of the three graphite slab thicknesses, both to determine the magnitude and relaxation lengths of the gamma-ray dose through graphite and to ensure that none of the neutron detectors was being used in a too high gamma-ray field, which would have caused their readings to be high. The fast-neutron spectrum from 1.3 to 10 Mev was measured with the BSF fast-neutron spe~trometer.~ A spectrum with reasonable statistics could be obtained only through the 1-ft graphite slab; the neutron intensities through the 2- and 3-ft sections were too low, The spectrum measured with the -. 3R. G. Cochran and K. Henry, A Protun Kecozl Type Fast-Neutron Spectrometer, ORNL- 1479 (April 2, 1953). 5 ..... !. I ..... 1 , Fig. 13.2. Thermal-Neutron Flux Measurements ose Measurements Be- Behind AGHT Graphite. 169

ANP QUARTERLY PROGRESS REPORJ 50-cC ION 41% ORNL-LR-DWG 2657 Fig. 13A, Gamma-Ray Dose Measurements hind AGHT Graphite. 1-ft graphite thickness between the reactor face and the end of the spectrometer collimator is shown in Fig. 13,5. The spectrum measured with the end of the collimator against the reactor face is also s t1own. Removal cross sections have been calculated for each thickness of graphite by use of a method suggested by E. P. Blizard.4 The resulting cross sections are 0.82 barn/atom for the 1-ft slab, 0.84 badatom for the 2-ft slab, and 0.80 barn/atom for the 3-ft slab. These removal cross sections are in goad agreement with measurements made on graphite at the LTSF. REACTOR AIR GLOW R. G. Cochraii T. A. Love K. M. Henry F. C. Maienschein R. W. Peelle Attempts to theoretically determine the amount of visible light which may surround a nuclear-powered airplane in flight have resulted in widely differing ~alues.~'~ Therefore an experiment was performed at the BSF to provide an experimental basis for future estimates. The end of an air-filled aluminum periscope tube was placed at the reactor face, and the amount of light produced in the tube was measured by a photomultiplier with spectral response similar to that of the average human eye. Other relative measurements were token with a photomultiplier which was sensitive chiefly in the blue and near- ultraviolet range. The latter measurements are plotted in Fig. 13.6 as functions of the air pressure in the tube. Measurements with argon in the tube demonstrate that nei ther the approximate amount of light produced nor the exact spectrum emitted is strongly dependent on the atomic number of the gas. It is also interesting to note that the light production in a given volume of air appears to have a maximum at a pressure corresponding to an altitude of about 30,000 ft. It is demonstrated in Figs. 13.7 and 13.8 that the air glow is largely caused by gamma radiation rather than by neutrons. Figure 13.7 shows the decay of the light plotted along with the decay of the reactor gamma ion chamber current just after reactor shutdown. The attenuation by water of the radiation which produces the air glow is shown in Fig. 13.8. This attenuation rather closely follows that of gamma rays. The photomultiplier was used to compare the quantity of light given off in the air-glow tube with that from a small tungsten lamp mounted at the reactor end of the ti~be, This comparison showed that 7.2 x lom5 lumen was given off by the glow for c1 reactor power of 100 kw and atmospheric pressure. Presumably, the amount of light should be proportional to the integral of the gamma-ray dose rate over the volume of the air in the measuring tube. 10 This integral was estimated to be 1.1 x 10 (r.cm3)/hr. Therefore the effective light production per unit V O ~ Lof J ~ air ~ is L : 6.5 x (Iumen/cm3)/(r/hr). If it is assumed that all the light is given off at 4E. P. Blizard, Procedure /or Obtaining E//ective Rernoval Cross Tertzons froin Lid Tank Data, QRNL CF-54-6-164 (June 22, 195.1)- 5T. A. Welton as quoted by C, E. Moore, Visual Detectability o/ Azrcralt at Night, LP.C-15, p 24 (Aug. 14, 1953). 6J. Ea Faulkner,_Vrsible 1.1ght Produced in Air Around Reactors, ORNL Lt -54-5-99 (to be issued).

ANP QUARTERLY PROGRESS REPORJ<br />

50-cC ION<br />

41%<br />

<strong>ORNL</strong>-LR-DWG 2657<br />

Fig. 13A, Gamma-Ray Dose Measurements<br />

hind AGHT Graphite.<br />

1-ft graphite thickness between the reactor face<br />

and the end of the spectrometer collimator is shown<br />

in Fig. 13,5. The spectrum measured with the end<br />

of the collimator against the reactor face is also<br />

s t1own.<br />

Removal cross sections have been calculated for<br />

each thickness of graphite by use of a method<br />

suggested by E. P. Blizard.4 The resulting cross<br />

sections are 0.82 barn/atom for the 1-ft slab,<br />

0.84 badatom for the 2-ft slab, and 0.80 barn/atom<br />

for the 3-ft slab. These removal cross sections are<br />

in goad agreement with measurements made on<br />

graphite at the LTSF.<br />

REACTOR AIR GLOW<br />

R. G. Cochraii T. A. Love<br />

K. M. Henry F. C. Maienschein<br />

R. W. Peelle<br />

Attempts to theoretically determine the amount of<br />

visible light which may surround a nuclear-powered<br />

airplane in flight have resulted in widely differing<br />

~alues.~'~ Therefore an experiment was performed<br />

at the BSF to provide an experimental basis for<br />

future estimates.<br />

The end of an air-filled aluminum periscope tube<br />

was placed at the reactor face, and the amount of<br />

light produced in the tube was measured by a<br />

photomultiplier with spectral response similar<br />

to that of the average human eye. Other relative<br />

measurements were token with a photomultiplier<br />

which was sensitive chiefly in the blue and near-<br />

ultraviolet range. The latter measurements are<br />

plotted in Fig. 13.6 as functions of the air pressure<br />

in the tube. Measurements with argon in the tube<br />

demonstrate that nei ther the approximate amount of<br />

light produced nor the exact spectrum emitted is<br />

strongly dependent on the atomic number of the<br />

gas. It is also interesting to note that the light<br />

production in a given volume of air appears to have<br />

a maximum at a pressure corresponding to an<br />

altitude of about 30,000 ft.<br />

It is demonstrated in Figs. 13.7 and 13.8 that<br />

the air glow is largely caused by gamma radiation<br />

rather than by neutrons. Figure 13.7 shows the<br />

decay of the light plotted along with the decay of<br />

the reactor gamma ion chamber current just after<br />

reactor shutdown. The attenuation by water of<br />

the radiation which produces the air glow is shown<br />

in Fig. 13.8. This attenuation rather closely<br />

follows that of gamma rays.<br />

The photomultiplier was used to compare the<br />

quantity of light given off in the air-glow tube with<br />

that from a small tungsten lamp mounted at the<br />

reactor end of the ti~be, This comparison showed<br />

that 7.2 x lom5 lumen was given off by the glow<br />

for c1 reactor power of 100 kw and atmospheric<br />

pressure. Presumably, the amount of light should<br />

be proportional to the integral of the gamma-ray<br />

dose rate over the volume of the air in the measuring<br />

tube.<br />

10<br />

This integral was estimated to be 1.1 x 10<br />

(r.cm3)/hr. Therefore the effective light production<br />

per unit V O ~ Lof J ~ air ~ is<br />

L : 6.5 x (Iumen/cm3)/(r/hr).<br />

If it is assumed that all the light is given off at<br />

4E. P. Blizard, Procedure /or Obtaining E//ective<br />

Rernoval Cross Tertzons froin Lid Tank Data, QRNL<br />

CF-54-6-164 (June 22, 195.1)-<br />

5T. A. Welton as quoted by C, E. Moore, Visual<br />

Detectability o/ Azrcralt at Night, LP.C-15, p 24 (Aug.<br />

14, 1953).<br />

6J. Ea Faulkner,_Vrsible 1.1ght Produced in Air Around<br />

Reactors, <strong>ORNL</strong> Lt -54-5-99 (to be issued).

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