ORNL-1771 - Oak Ridge National Laboratory

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io3 5 .--w 2 _J U 0 0 >- " 2 2 40 t " m a v $ 5 -J LL z s? I- 3 W z 2 !J a E CL W I !- 10 w s I- d _J W E 5 2 PERIOD ENDING SEPTEMBER 10, 1954 _1 <strong>ORNL</strong>-LR-DWG ~~ 2772 - ........ __ ....... _._ .- I ............ . h = VARIABLE 0 = 330 deg d = 64 ft a = -90 deg __ p = 45.2 cm I ,Ti ......._I . ._._I_- ................... ~. ~. .- - . ._- CENTER OF TRIPLET BF, CHAMBER AT: - x = VARIABLE y = 79.6crn I = 0.0 cm 1 V----r---t---t . . ................... .................... ! - 75 - 65 - 55 -45 -35 1 .--__ CURVE 1 2 3 4 .. 5 . 6 7 ~ _ _ _ _ 8 ................ 9 ALTITUDE 50 ft -~ 96 ft 197 ft 0 ft ........ ......... ---I -. ..... - ........... ................... .- ..................... x, HORIZONTAL DISTANCE FROM d AXIS TO DETECTOR CENTER (cm) Fig. 14.2. Attenuation of Scattered Neutron Flux in Detector Tank at Various Altitudes. ....... 177
ANP QUARTERLY PROGRESS REPORT 0 30 beg d-zdft p = a5 2 cm a = 30 aeg CFNTCR OF -RIPLEI BF3 CHAbABCR AT x = SEE 4B7b In IRCN @ALL A- x= -" 5 ern' y= 79 6 cm 1-@3cm I La-- -~ 1 - 0 24 48 75 96 I20 44@ 168 192 h AlTlTUDE (ftl fig. 14.3. Variation of Scattered taeka~ari Flux with Altitude. TSH. Thermocouple measurements of the bulk water temperature in the 12-ft-dia renctor tank are made while the water is being stirred suf- ficiently to ensure that no significant difference in temperature exists throughout the tank. The rate of temperature rise of the water when the reactor is started is then proportional to the power of the reactor. Small corrections must be made for the power input due to the mixing and for the heat loss. This procedure was first used for a 5 by 6 fuel element loading in the TSR. The reactor tank wos lowered into the drained handling pool, and four mixers were placed nt various positions within the tank. The turbulence created by the mixers was sufficient for thorough mixing of the water, but the power added by the mixers was not enough to give a measurable increase of the water temperature. Before the reactor was started, the temper- 1 78 ature remained constan1 for more than 1 hr with the mixers running. Some heat insulation was obtained by creating, with a double layer of canvas, a dead-air space above the water and nrnund the reactor tank. The temperature rise during a reactor run was measured by 12 thermocouples placed in the tank. The thermocouples had previously been caJ itrated at temperatures of 0, 25, and 50°C and agreed to within 0.1"C. The first run of the experiment was started at 24"C, and the total temperature rise was approximately 14°C. The experiment was repented at a higher temperature level but with the same heat input and total terriperature rise. The initial temperature far this run was approximately 15°C above the ambient temperature, and the rise was ngain 14°C. The cooling rate ot the conclusion of this run was 6.3°C/hr. In a third run the initial temperature was brought 15°C below the ambient by cooling the reactor tank with ice before the run. The results of the three runs were consistent to within 1%. A detailed report of this experiment is being prepared.2 GE-ANP R-1 DIVIDED-SHIELD MOCKUP TESTS r. v. ~i~~~~~ D. I. Giliiland J. Van Hoomissen F. N. Wfiiitsnn Tests on the Gk-ANP R-l divided-shield mockup (Figs. 14.4 and 14.5) will begin with traverses around the reactor-shield section in the handling pool for compat ison with measurements made cat the PI SF.^ hSensur=metits will then be made in the LSF detector tank, which will be situated 84 ft from the reactor shield at an altitude @f 195 ft. It is nnticipated that the datector tank will be replaced by the crew-compartment iflockup in mid- September, - 2C. E. Clifford et al., Cuiorirneinc Powel- I)etermz- nation o/ the Tower Shielding Reaclor, <strong>ORNL</strong> CF-54-8- 105 (to be issued). '!-+. E. tiungerford, Uuik Shielding Fnrilzty Tests on the GE-ANP R-1 Divided Shzeid Mochup, OKNI. CF-54-8- 94 (to be issued).
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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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ANP QUARTERLY PROGRESS REPORT the A
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ANP QUARTERLY PROGRESS REPORT appro
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ANP QUARTERLY PROGRESS REFORT be si
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ANP QUARTERLY PROGRESS REPORT TABLE
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ANP QUARTERLY PROGRESS REPORT - 22
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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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- 40 32 c 3 24 A F! P ._r >- k > ir
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with and without 0.OZin.-thick cadm
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Part II MATERIALS RESEARCH
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ANP QUARTERLY PROGRESS REPORr propo
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P,NP QUARTERLY PROGRESS REPOK'I ___
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ANP QUARTERLY PROGRESS REPORT Fig.
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ANP QUARTERLY PROGRESS REKIRT TABLE
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ANP QUARTERLY PROGRESS REPORi Fig.
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ANP QUARTERLY PROGRESS REPORT Ceram
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A N P Q UA R I-EKIY PRO G R ESS R E
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ANP QUARTERLY PROGRESS REPORT UNCL
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ANP QUARTERLY PROGRESS REPORT lncon
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Page 167 and 168: zirconium or aluminum complex, or l
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Page 197: REPORT NO. ~~-54-a-10 C F-54-6-4 CF
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