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the disintegration rates and energies involved, are tabulated in Table 1.1. It w i l l be noted that after 8500 min of holdup, corresponding to a discharge rate of 20.8 cm3/min through each restrictor, the ground tolerance w i l l not be exceeded. Normal Discharge from the Surge Tank. The maximum pressure within the surge tank is limited by a 5-psig pressure regulator in the gas supply system. The maximum discharge rate from the surge tank is limited by a nourdon restrictor to 20 cm’/min with a 5-psi pressure differential. A t this flow rate through each of two restrictors, the holdup volume of the system is such that it w i l l allow sufficient decay time, as required by the above calculation, to permit the discharge of the off-gas directly up the stack. The change of effective energy owing to the persistence of the longer lived isotopes has been ac- counted for when ground concentration of this gas is considered. Gas Vented from the Fuel Dump Tank During Dumping. In considering waste gases from the surge tanks, it has been assumed that all gaseous products escape into the surge tanks during operation. Actually, it is expected that some portion of the fission- product gases w i l l remain in the fuel and that some fraction of this portion PERIOD EIVDING DECEMBER 10, 1952 w i l l be released when the fuel is admitted to the radioactive-fuel dump tank. When fuel is admitted to the fuel dump tank, it is expected that helium w i l l be displaced at a rate of the order of 5 cfm. This helium, after passing through the NaK scrubber and the first holdup tank, w i l l be admitted to the monitors. Should the monitors sense excess activity, the stack valve w i l l prevent discharge, and the vacuum pumps w i l l permit recirculation through the holdup tanks and monitors. The recirculation should homogenize the gases and ensure that the monitor is sensing a repre- sentative sample. When the gases have decayed sufficiently to permit release, the moni tor -co nt ro 1 led interlock wi 11 open the stack valve. REACTOR CONTROL SYSTEM E. P. Epler Research Director’s Division The high-temperature fission chamber, without UZ3’ plating, has completed 1000 hours at 800°F. The temperature will now be raised at the rate of 50°F per week to determine the hi gh - temp e r at u r e c h a r ac t e r i s t i c s of the fvIgO;SiO, insulator. The fission chambers to be used for the ARE startup are scheduled for delivery February 1, 1953, and w i l l be tested at 800°F. TABLE 1.1. ACTIVITY OF XENON AND KliYPTON AS A FUNCTION OF HOLDUP TIME _._.__I HOLDUP TIME _____ Days Minutes x 720 1 1, 440 2 2,880 1 Calculated MPC 344 2 110 2. 45 39. 6 3.51 (MeV) 0. 41 0.34 0. 237 91 SINTEGRATION RATE (dps) I____.-__ 9. 15 5.88 x lox5 4.22 x DECAY POWER MPC IN AIR Watts MeV/ sec . (UC/ .In3) _._I__ 600 3.75 x 1015 3.9 x io-6 3 20 2.00 x l0lS 4.71 x 10-6 160 1.00 X lo1’ 6.75 X I 3 3.320 28. 5 3.94 0.211 3.79 x 128 8.00 7. 58 x 5 7 7,200 10,080 6.91 3.02 ~ ___ 4. 54 0. 183 4. 54 0. 183 ~ 1.84 x 1. 13 X lo*’ 54 33 3.38 x 1015 8.74 x io-6 2.06 x 10’’ 18.74 X IO-‘ __ 15
ANP PROJECT QUARTERLY PROGRESS REPORT The first production model of the The wiring diagram for the control servo amplifier has been tested with system has been completed and working the ORNL Power Plant Simulator, and drawings for the relay panels, con- it proved to be satisfactory. This sole, and chamber installation have test was made with the actual com- .heen issued to the field. ponents, or duplicates, to be used in the ARE. A memorandum describing the (7)E. R. Mnnn. J. J. Stone, end S. H. Hanover, on-off Servo for the ARE is being An On-Off Servo for the ARB, ORNL CF-52-11-228 (to prepared. ( ') be published). 16
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Page 6: Reports previously issued in this s
Page 9 and 10: e e e PAGE Moore Nullmatic pressure
Page 11 and 12: .. CrF. .Na. CrFd .Li. CrF6 .......
Page 13 and 14: PAGE Melting point of 60% Pd-40% Ni
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Page 32 and 33: 2. EXPERIMENTAL REACTOR ENGINEERING
Page 34 and 35: design of the first combination sea
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Page 56 and 57: In the theory of power oscillations
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Page 60 and 61: and The assumed boundary conditions
Page 62 and 63: where N, = number of atoms per cubi
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Page 66 and 67: MSTANCE FROM REACTOR AXIS (in) Pmrm
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AN€' PROJECT QUARTERLY PROGRESS R
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68 ANP PROJECT QUARTERLY PROGRESS R
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ANP PROJECT QUARTERLY PROGRESS REPO
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- *0° 1 BO 440 120 , '0° i 80 , I
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84 1 E 0 d a 1 Y d .4 rl h u C d d
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the last quarterly report,(') has b
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Design of the tower configuration a
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d 1 I 2 . k IJJ 10 c -- ___li i____
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person received about four times th
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ANP PROJECT QUARTERLY PROGRESS REPQ
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ANP PROJECT QUAIRTEHLY PROGRESS REP
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AIYP PROJECT QUARTERLY PKQGRESS REP
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ANP PROJECT QUAHTERLY PROGRESS REPO
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ANP PR0,jlECT QUARTERLY PROGRESS RE
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ANP PROJECT QUAR'FEHLY PROGRESS REP
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ANP PROJECT QIJARTERX,Y PRQCRESS RE
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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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AhP PROJECT QUARTERLY PHOGRESS REPO
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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 PRQJECT QUARTERLY PROGRESS REPO
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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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