ORNL-1771 - Oak Ridge National Laboratory

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TIME (rnin) PERIOD ENDING SEPTEMBER 10, 7954 m ORNL-LR-DWG 266i 0 10 20 30 40 50 60 70 DISTANCE FROM HtACTOR (cml Fig. 13.7. Decay of Air Glow and Reactor Gamma Fig. 13.8. Attenuation in Water of Radiation Rays. Causing Air Glow. of light. This large uncertainty is primarily at- tributable to the low sensitivity of the eye-equiva- lent photomultiplier. A more detailed discussion of these preliminary values will be given in a forthcoming report. 8 FUEL ACTIVATION METHOD FOR POWER DETERMINATION OF THE ARE E. B. Johnson When the ARE goes into operation, many measure- ments of its performance will be made. Among them will be the power level at which it operates, which will be measured in more than one way. A method suggested by J. L. Meem is based on the measurement of the relative activity of fuel samples exposed in the ARE and in a known flux in another reactor (BSR). An experiment has been initiated at .the BSF to implement this suggestion. 8F. C. Maienschein et al., iMeusurc7nents o/ u l?t?acto~- Induced Air Glow, ORNL CF-54-9-1 (to be issued). The activity resulting from the irradiation of fissionable material is not easy to predict because of the large number of isotopes for which calculations would be required. However, for identical flux, exposure time, and waiting period after exposure, the specific activity of two samples should be the same. Furthermore, at low neutron fluxes the activity should be proportional to the flux. It is contemplated that the ARE will be operated at a nominal power level of approximately 1 w for 1 hr, that it will then be shut down, and that a sample of the irradiated fuel will be withdrawn for counting and analyzing. The ARE experimental progrom will then proceed as scheduled. A decay curve will be run on this fuel sample from the ARE and compared with the decoy curve obtained on a similar fuel capsule irradiated for the same length of time in the BSR in 01 known neutron flux of about the same magnitude. From the relative activity of the two samples, the operating power of the ARE 173
ANP QUARTERLY PROGRESS REPORT can be determined readily. For the power comparison it will be necessary to know the uranium content of the sample and of the ARE, as well as the energy per fissione9 A small correction will 9J. L, Meein, L. B. Hollond, and G. M. McCummon, Detemznatzon of the Pouer o/ the Bulk Yhzeldrng Reactor - Par! 111. Measurement of the knergy Released per Fzsszon, ORNL-1537 (Feb. 15, 195.2). 174 be necessary for the local depression of flux by the uranium sample. This factor has been estirtiated by W. K. Ergen to be 0.80. Details for the appli- cation of this method are given in a separate report. 10 ''E. R. Johnson, Fuel Actzvatzori Methods for Power Determination o/ the ARE, ORNL CF-54-7-11 (in press).
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Contract No. W-7405-eng-26 AIRCRAFT
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1. G. M. Adamson 2. R. G. Affel 3.
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197-198. Powerplant Laboratory (WAD
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FOREWORD This quarterly progress re
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PART II . MATERIALS RESEARCH 5 . CH
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Remote Metallography ..............
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ANP QUARTERLY PROGRE.S.5 REPORT ver
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AMP QUARTERLY PROGRESS REPORT A dev
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part I REACTOR THEORY, COMPONENT DE
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AMP QUARTERLY PROGRESS REPORT After
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in the ZPU system, While this arran
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I ORNL-LR-DWG 3092 CALCULATIONS EXT
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Power level TABLE 2.6. COMPARISON O
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PERIOD ENDING SEPTEMBER JO, 1954 Fi
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I R j I Fig. 2.7. Surfaces of Beryl
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that will permit remote, momentary
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sump in that it must be sufficientl
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J Fig, 3.4. Inconel Forced-Circulat
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- PERIOD ENDING SEPTEMBER 10, 1954
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from 18 to 31 so that tests of long
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A A Fig. 4.1. First Reflector-Moder
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with and without 0.OZin.-thick cadm
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Part II MATERIALS RESEARCH
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Page 167 and 168: zirconium or aluminum complex, or l
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Page 194: part IV APPENDIX
Page 197: REPORT NO. ~~-54-a-10 C F-54-6-4 CF
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