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4 W 160 140 I20 100 80 60 40 20 0 160 140 120 100 80 60 40 20 0 y, HORIZONTAL DISTANCE FROM SOURCE AXlS (Cm) -20 -40 -60 -80 -100 -120 -140 -160 F a ui Fig. 6. 10. Gamma-Isodose Neasurements Around G-E Inlet Air Duct hlockup. N li 0 "
ANP PROJECT QUARTERLY PROGRESS REPORT gamma shield. Center-line traverses were made as the shielding slabs were successively removed. The results appear in Fig. 6.11. INDUCED ACTIVITY AROUND A DUCT An experiment has been performed in the Lid Tank Facility with the primary object of determining the order of magnitude of the induced radioactivity to be expected outside the air ducts in the GE-ANP initial engine shield. In addition, itwas desired to estimate the value of thin boron shields in lowering this activity, to investigate the utility of RF3-counter measurements in predicting activation, and to determine the effect of borating the shield water around the ducts. The mockup of the G-E outlet air duct that had been previously tested(3) was modified by the addition of a tank so that borated water could be placed around the duct. Figure 6.12 shows the configuration. The outside of this tank simulated the outside of the design shield. Measurements were made at the end and the side of the duct, as indicated in Fig. 6.12. Two types of measurements were undertaken: samples of cobalt and manganese were exposed and their activities measured, and traverses were made with a RF, counter. In all cases, various thermal-neutron shields were i~sed, and the results were com- pared with unshielded measurements. Data were obtained with both pure and borated water around the duct. The induced activities under various conditions are tabulated in Table 6.2, and the results of the counter traverses are presented graphically in Figs. 6.13, 6.14, 6.15, and 6.16. Figure 6.17 depicts the results of center- line traverses with no duct in the tank but with various thermal shields around the counter, (3)ANP Quar. Prog. Rep. June IO, 1952. ORNL- 1294, p. 72. 74 Since the activation measurements were of an exploratory nature, a com- plete investigation olall combinations of parameters was not attempted. The samples were prepared hurriedly, and therefore errors of 30% are to he expected from differences in the geometry of exposure and counting. In the low flux available in this experiment, the cobalt did not become radio- active enough to afford an accurate measurement of its activity. The various ratios of counting rates are given in Tables 6.3, 6.4, and 6.5, which show, respectively, the effect of thermal shields, acomparison between the counting rates at the side and end of the duct, and the effect of borating the shield water. It is apparent that a thin boron layer is far more effective in shielding the boron counter than in shielding either manganese or cobalt. This is to be expected, since an important part of the activation of the latter is due to resonance absorption at epithermal energies where the boron cross section is relatively low. The variously shielded detectors are sensitive to different neutron energies , and there fore an indication of the comparative neutron spectra at the side and the end of the duct can be obtained by comparing the counting rates under these conditions. When the expected experimental errors are con- sidered, there does not seem to be evidence of significant differences in thc spectra at these two positions. With pure water in the tank, there are more epi thermal neutrons than thermal ncutrons; or loobing at the situation from the opposite viewpoint, the ducts increased the thermal flux. Under these conditions, a conservative estimate can be made of the expected activation around a ducted shield from the readings of aBF, counter, provided an experimental comparison has been made at some point without ducts. It was at first a surprise to find that adding boron to the shield water
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Reports previously issued in this s
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e e e PAGE Moore Nullmatic pressure
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.. CrF. .Na. CrFd .Li. CrF6 .......
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PAGE Melting point of 60% Pd-40% Ni
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ANP PROJECT QUARTERLY PROGRESS REPO
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AYP PROJECT QUARTERLY PROGRESS REPO
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in the hot condition corresponds to
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c-' w FILL TANKS LINE VOLUME APPROX
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the disintegration rates and energi
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2. EXPERIMENTAL REACTOR ENGINEERING
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design of the first combination sea
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the construction of the shaft and r
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ANP PROJECT QUARTEHLY PROGRESS REPO
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ANF PROJECT QUARTERLY PROGRESS REPO
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ANP PRQ JECT QUARTERLY PROGRESS RQE
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134 = e . , n N N N - Y) o m -J .m
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constituent was found in this loop.
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(mil SId: 3 6 10 15 20 25 30 Extern
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ANP PROJECT QUARTERLY PRQGIXSS HEPO
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ANP PROJECT QUARTERLY PRQGRESS REPO
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ANP lJHO JECT QUARTERLY PHOGRESS RE
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ANP PROJECT QUARTElilLY PROGRESS RE
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BRAZING ALLOY Nic robr az 60% Mn-40
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ANP PROJECT QUARTERLY PIJQGRESS REP
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ANP PRQJECT QUAMTERLY PWOd;l"aESS R
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on air radiations and simulated fla
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184 Fie. 13.6. Pyrex Thermal Convec
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ANP PROJECT QU.4RTEtlLY I'ROGRESS R
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SUMMARY AND INTRODUCTION The list o
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CF-52-11-85 ORNL- 1 43 3 OWL- 137 2
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H. Seal and Pump Development PERIOD
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12. 13. 14. 15. 16. 1.7. 18. 19. Pr
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i 3. U0,-NaOH Slurry Loop 4. Operat
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7. Fuel Spherical Particle Producti
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