ORNL-1771 - Oak Ridge National Laboratory

More documents

Recommendations

Info

2400 7000 1) r?lsb ORNL-LR--DWG 3087 0 40 20 30 40 50 GO 70 e0 90 FLOW XAlE (yoml Fig. 1.1. Data on Pump Speed YS Flow Rate Obtained During Water Test of ARE Fuel System. 1 no gllr ORNL -LR- DWG 3088 0 0 10 20 30 40 50 6!) 70 H!) FLOW RATE (ypni) Fig. 1.2. Data on Pressure Head from the Pump Suction to the Reactor Inlet vs the Flow Rate During Water Test of ARE Fuel System. By using a calibrated orifice installed tempo- rarily in the sodium bypass line around the reactor, it was possible to measure the flow rate while operating the sodium system with water. The pump speed was recorded and also the pressure head from the pump suction to the reactor outlet. The system characteristics with water, shown in Figs. 1.3 and 1.4, should be valid while operating with sodium as the fluid. During operation with sodium, the flow rate in each of the two loops will be measured with an electromagnetic flowmeter. The sum of the two flow rates should equal the total flow as obtained from the pump speed. 2400 e000 40c PERlOD ENDlNG SEPTEMBER 10, 7954 0 0 20 40 EO 80 100 120 140 160
ANP QUARTERLY PROGRESS REPORT the ARE building around th~se losotions, none of the parts necessnry for the loading and sampling operations have yet been installed. Testing of the equipment after installatian and before the filling operotion shoiJld require approximately one week. It is anticipated that ale pcrsonnel to he involved with the loading and sampling operation will be made thoroughly familiar with the equipment and its operation during this testing period. F U Et - CO NC E K T R A T E I NJ E C T If; NO Z 7 i.. F W. 6. Cobb w. R. Iduntley Air craft Weac for E ng i nee: i ng D i v I s ion Pests were rtiade on a resistance-heated fuel- concentrate injection nozzle to determine the effectiveness of the heating in thc region where the nozzle will enter the relatively cold pump tank cover plate. These tests showed that a ternperaturc of 1300°F could be maintoitred in the injection tube by using about 140 ~ m from p a high-current transformw, This nozzle test was considered satisfactory to meet the operating requirements for the ARE enrichment system. ARE UhlLCPsbDlNG EXPERIMENT J. Y. Estabiook Aircraft Reactor Fngineering Division The mockup of the ARE unloading apparatus was tested twice. In the first test the storage tank was filled with 950 Ib of NaZrF,, which was successfully unloaded in 90-lb increments into aluminum cans. In two cases, however, the Sottoitis of the aluminum cans meltcd and the fluoride mixture leaked out. Modifications made in the apparatus before the second test included improwenlents in the pouring spout, the level indicators, and the pressure measuring equipment. In addition, small amounts of the fluoride mixture \were frozen in the bottoms of the aluminum C Q ~ K to minimize the possibility of melting these containers. For the second test the apparatus WQS filled with 500 Ib of NaF-ZrF, (SO-SO mole %), arid this material was transferred at 1200 to 1250°F to the aluminum cans in 90- to 9O-lb incieansnts without difficulty. Attempfs to transfer at 1100 to 115OoF, however, led to occasional freezing at the pouring spout and indicated that ~mlep~s much more reliable ternpcsatwt B control could he effected, operation 0: this low teinperature could hoidly bc considered to be feasible. 1% AWE FUEL RECOVERY AND REPROCESSING D. E. Ferguson G. I. Cathers M. R. 5ennett Chemical Technology Division A fluoride-volatili?y method of processing AHE fuel, based on elemental fluorination of the molten NaF-Zi-F,-UF,, has been investigated becclt~se of its attiactiveness from the standpoint of cost, inventory of fissionable ninterial, waste di sposalr and safC;j” of operation. In preliminary more than 99.95% of the uranium tetrafluoride coiitoiaed in the fwel was converted to the volatile hexafluoride with c1 gross beta decontamination factor of 100 to 300. Resublimation of this uranium hexafluoride resulted in an over-all decontomination facto; of 4000 to 5000. Since in the absence of excess fluorine UF, is soluble in molten NaF-ZrF,, the resublimed product C accoiding .to the reaction’ G ~ be dissolved, probably UF, + NaF ---7‘ NaF.1!F6 ---+ NaFBUF, + F, . The fuel from an aircraft reactor would be re- processed in three steps: recovery of the uranium from the used fuel by fluorination, separation of the uranium hexafluoride from excess fluorine by trapping the uranium salt in a cold trap and re- subliming the UF, from it, and fabrication of a new reactor fused salt by absorbing tlie partially decon- tarninGted hJF, in molten NaF-ZrF,. Since uranium- zirconium and other alloys can be dissolved at reosonnhle rates by hydrofluorination in a fused salt of the No%-zrF,-KF type,5 this also provides a imethnd of processing heterogeneous reactor fuels. A decontamination factor of 4000 to 5000 is sufficient if the fuel is to be recycled directly to a $usad salt reactor, but, if the uranium is to be returned to a diffusion plant or to a heterogeneous reercqor, more decontaminatisn i 5 needed. In further experimeniol work, u decontamination factor of approximately 20,000 was obtained by scrublaing the fission-product fluorides from the ~~ . ~ ~~~ 2G. I. Cathers, Recouery atiJ Decontamination of Uraaium $om h‘used Fluoride Fuc!s by FIuorination, ORNL-17d9 (June 9, 19541, 3F. N. Biowdgr, G. I. Cathers, D. E. Furguson, and E. 0. Nuriiii, ANP Quar. Prog. Rep. Mar. 10, 1954, ORNb_-!692, p 42, ,H. Martin, A. Albers and H. P. Dust, Z. unorg. ZL allgem, Chern. 265, 128 (1951). 5R. E, LLeuze and C. E. Schilling, personal corn- municotion.
Page 2 and 3: Contract No. W-7405-eng-26 AIRCRAFT
Page 4 and 5: 1. G. M. Adamson 2. R. G. Affel 3.
Page 6 and 7: 197-198. Powerplant Laboratory (WAD
Page 8: FOREWORD This quarterly progress re
Page 11 and 12: PART II . MATERIALS RESEARCH 5 . CH
Page 13 and 14: Remote Metallography ..............
Page 15 and 16: ANP QUARTERLY PROGRE.S.5 REPORT ver
Page 17 and 18: AMP QUARTERLY PROGRESS REPORT A dev
Page 20: part I REACTOR THEORY, COMPONENT DE
Page 23: AMP QUARTERLY PROGRESS REPORT After
Page 27 and 28: ANP QUARTERLY PROGRESS REPORT 67 g
Page 29 and 30: ANP QUARTERLY PROGRESS REPORT appro
Page 31 and 32: ANP QUARTERLY PROGRESS REFORT be si
Page 33 and 34: ANP QUARTERLY PROGRESS REPORT TABLE
Page 35 and 36: ANP QUARTERLY PROGRESS REPORT - 22
Page 37 and 38: in the ZPU system, While this arran
Page 40 and 41: I ORNL-LR-DWG 3092 CALCULATIONS EXT
Page 42 and 43: Power level TABLE 2.6. COMPARISON O
Page 44 and 45: PERIOD ENDING SEPTEMBER JO, 1954 Fi
Page 46 and 47: I R j I Fig. 2.7. Surfaces of Beryl
Page 48 and 49: that will permit remote, momentary
Page 50 and 51: sump in that it must be sufficientl
Page 52 and 53: J Fig, 3.4. Inconel Forced-Circulat
Page 54 and 55: - PERIOD ENDING SEPTEMBER 10, 1954
Page 56 and 57: from 18 to 31 so that tests of long
Page 58 and 59: A A Fig. 4.1. First Reflector-Moder
Page 60 and 61: - 40 32 c 3 24 A F! P ._r >- k > ir
Page 62 and 63: with and without 0.OZin.-thick cadm
Page 64: Part II MATERIALS RESEARCH
Page 67 and 68: ANP QUARTERLY PROGRESS REPORr propo
Page 69 and 70: ANP QUARTERLY PROGRESS REPORT appar
Page 71 and 72: ANP QUARTERLY PROGRESS REPORT urani
Page 73 and 74: ANP QUARTERLY PROGRESS REPORT seems
Page 75 and 76:
ANP QUARTERLY PROGRESS REPORT ~~ -
Page 77 and 78:
AN P QUARTER 1Y PROGRESS R EPOR J T
Page 79 and 80:
ANP QUARTERLY PROGRESS REPORT of 0.
Page 81 and 82:
ANP QUARTERLY PROGRESS REPORT q0-2
Page 83 and 84:
4NP QUARTERLY PROGRESS REPORT on d
Page 85 and 86:
ANP QUARTERLY PROGRESS R €PO RT P
Page 87 and 88:
ANP QUARTERLY PROGRESS REPORT ammet
Page 89 and 90:
ANP QUARTERLY PROGRESS REPORT catho
Page 91 and 92:
P,NP QUARTERLY PROGRESS REPOK'I ___
Page 93 and 94:
ANP QUARTERLY PROGRESS REPORT CH EM
Page 95 and 96:
ANP QUARTERLY PROGRESS REPORT A pla
Page 97 and 98:
ANP QUARTERLY PROGRESS REPORT Fig.
Page 99 and 100:
ANP QUARTERLY PROGRESS REKIRT TABLE
Page 101 and 102:
ANP QUARTERLY PROGRESS REPORT TABLE
Page 103 and 104:
ANP QUARTERLY PROGRESS REPORi Fig.
Page 105 and 106:
Page 107 and 108:
ANP QUARTERLY PROGRESS REPORT Ceram
Page 109 and 110:
A N P Q UA R I-EKIY PRO G R ESS R E
Page 111 and 112:
ANP QUARTERLY PROGRESS REPOR7 Effec
Page 113 and 114:
Page 115 and 116:
ANP QUARTERLY PROGRfSS REPORT Flamm
Page 117 and 118:
AMP QUARTERLY PROGRESS REPORT of tw
Page 119 and 120:
ANP QUARTERLY PROGRESS REPORT The e
Page 121 and 122:
ANP QUARTERLY PROGRESS REPOR7 trans
Page 123 and 124:
AM? QUARTERLY PROGRESS REPORT at pr
Page 125 and 126:
AMP QUARTERLY PROGRESS REPORT studi
Page 127 and 128:
ANP QUARTERLY PROGRESS REPORT The m
Page 129 and 130:
ANP QUARTfRLY PROGHESS REPORT As be
Page 131 and 132:
ANP QUARTERLY PROGRESS REPORr Devel
Page 133 and 134:
ANP QUARTERLY PROGRESS REPORT UNCL
Page 135 and 136:
ANP QUARTERLY PROGRESS REPORi UNCLA
Page 137 and 138:
ANP QUARTERLY PROGRESS REPORT lncon
Page 139 and 140:
Page 141 and 142:
ANP QUARTERLY PROGRESS R€PORT 450
Page 143 and 144:
Page 145 and 146:
132 ANP
Page 147 and 148:
ANP QUr4RTERLY PROGRESS REPORT Addi
Page 149 and 150:
ANP QUARTERLY PROGRESS REPORT mater
Page 151 and 152:
ANP QUARTERLY PROGRESS REPORT 138 (
Page 153 and 154:
Page 155 and 156:
ANP QUARTERLY PROGRESS REPORT The c
Page 157 and 158:
ANP QUARTERLY PROGRESS REPORT oxide
Page 159 and 160:
ANP QUARTERLY PROGRESS REPORT - n 6
Page 161 and 162:
ANP QUARTERLY PROGRESS REPORT 10. A
Page 163 and 164:
ANP QUARTERLY PROGRESS REPORT Oxide
Page 165 and 166:
ANP QUARTERLY PROGRESS REPORT and U
Page 167 and 168:
zirconium or aluminum complex, or l
Page 170 and 171:
11. SHIELDING ANALYSIS J. E. Faulkn
Page 172 and 173:
form in terms of the Spence functio
Page 174 and 175:
these integral 5 become Let and the
Page 176 and 177:
PERIOD ENDING SEPTEMBER IO, 7954 Al
Page 178 and 179:
0 20 40 60 80 IO0 120 140 160 I, Di
Page 180 and 181:
... Two configurations, a single du
Page 182 and 183:
The thermal-neutron flux (Fig. 13.2
Page 184 and 185:
E-7 1 O6 I 5 - - L I ___- 2 f o5 2
Page 186 and 187:
TIME (rnin) PERIOD ENDING SEPTEMBER
Page 188 and 189:
. - ., . ....._____... - PERiOD END
Page 190 and 191:
io3 5 .--w 2 _J U 0 0 >- " 2 2 40 t
Page 192 and 193:
PERIOD ENDING SEPTEMBER 10, 1954 Fi
Page 194:
part IV APPENDIX
Page 197:
REPORT NO. ~~-54-a-10 C F-54-6-4 CF
show all

ORNL-1771 - Oak Ridge National Laboratory

Create successful ePaper yourself

Delete template?

Save as template?