ML19330B333
| ML19330B333 | |
| Person / Time | |
|---|---|
| Site: | University of Wisconsin |
| Issue date: | 07/11/1980 |
| From: | Cashwell R WISCONSIN, UNIV. OF, MADISON, WI |
| To: | |
| Shared Package | |
| ML19330B332 | List: |
| References | |
| NUDOCS 8007310405 | |
| Download: ML19330B333 (150) | |
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{{#Wiki_filter:. O ANNUAL OPERAT!"G REPORT FOR LICEi1SE R-7!! TO THE UNIT 8 STATES NUCLEAR REGULATORY CCFMISSI0ft s - l FoR i Fiscal YEAR 1979-1980 1 PREPARED BY: R. J. CASHWEU. DEPARTriFNT 0.: I!UCLEAR ENGINE RING 8007310705
I AfiNUAL REPORT A. SU$1ARY OF OPERATIONS
- 1. Instructional Use - U'.l-Madisor Formal Classes Three huclear Engineering Department classes make use of the reactor.
The 46 students enrolled.in NE 231 participated in a 2-hour laboratory ses-sion to introduce students to reactor behavior cha acteristics. Twelve hours of reactor operating time tere devoted to thi- session. tie 427 had an enrollment of 17 during the 2 semesters it was offered. Several of NE 427 experiments use materials that are activated in she reactor, while the experiment entitled " Radiation Survey" requires that students make measurements of radiation levels in and around the Reactor Laboratory. Since the irradiations for the students and the radiation survey take place during normal isotope production runs, no reactor time was devote'd exclu-sively to :E 427. The enrollment in TIE 523 was 22 as it was of fered in both semesters. A total of 94 J operating hours was devoted to the 3 experimenjs (" Critical Experiment", "Controi Element Calibration", and
" Pulsing") which require exclusive use of che reactor Each of these ex-periments was repeated 4 times during the year. Other laboratory sessions make use of ma terial that has been irradiated in the reactor (" Fast tieu-tron Flux tieasurements by Threshold Foil Techniques" and " Resonance Ab-sorpticn"). These latter 2 experiments nere repeated 3 times during the semester.
Individual 1 to 2 hour sest uns in the Reactor Laboratory are also held for other departm.ents rangi. ' con Integrated Liberal Studies to Physics. .
- 2. Reactor Sharina Program Use of the reactor by the group from the University of "innesota-Duluth (3 staff members and 2 graduate students) continued with the work expanding from neutron activation analysis identification of copper and
' tin artifacts to preliminary work on attempting similar identi fication of pottery arti facts. A group frca the University of !!isconsin-Stevens Point brought a class of 25 exceptional high school students for a reactor cpe -
ating deronstration during the su=er,while Professor Auchter from Carroll College brought his Advanced Physics class of 5 students for a 3-hour class on neutron activation analysis. L j
_2
- 3. Utili ty ' Personnel Training Five 2-week research reactor training programs were conducted- for potential operations personnel from Public Service Indiana (?iarbie Hill).
The 2-week program is identical to such programs held in the past, essen-tially comprising laboratory experience for a training program conducted by General Physics Corporation. ' total o f 30 students was a cquai r.ted with basic reactor operating characteristics ar.d operating techniques by operating the reactor through at least 10 startups. A similar program was conducted for 2 groups of shift technical ad-visor appointees from the Kewaunee Nuclear Plant. A gecup of 5 students who had recently been students in our tie 427 and ?!E a23 laboratcry courses attended a 1-week progran which avoided duplication of material covered in those courses. The other group of 6 individuals completed the usual
~
2-week program.
- 4. Sample Irradiation and ?:eutron Activation Analysis Services During the year, 6,376 samples were irradiated. 1145 of these sample
, irradiations were for 15 minutes or less, while the remainder accumulated 12,707.73 sample hours of irradiation. The irradiation work can be further classified into 1,034 irradiations and '96.9 irradiation space hours. Most of the samples irradiated were irradiat.ed by the laboratory's neutron acti-vation analysis service where sanples are submitted by outside users for subsequent sample preparation and analysis by instrumental neutran activa-tion analysis. In the listing that follows, those s',ples run as part of the neutron activation anal.ysis service are designated by the notatien ."AA. A listing of the users of the irradiation and neutron actization snal-ysis service follows. Information is given on the object of the research, personnel involved and sponsoring organization where kncun. { Biochemistry. '(NAA) 14 samples, 7 less than 15 minutes,19.25 sample 4 hours. Professor M. A. Stahmann and 1 graduate student. 7teasurements of , trace elements in plant material; specifically the effect of nutrients on growth and dev2lopment of edible mushrooms. Supported by UARF. BiochemistrZ. 4 samples,12 sanple hours. Pro fessor Orme-Johnson. Production of copper-54 for tracer studies. Carroll College. 2 samples, both less than 15-minute irradiaticas. Professor Auchter and 5 students. Irradiation for a neutron activation , analysis laboratory. L .
_ Chemistry. '(NM ) 21 samples,10.5 sanple nours. Grad student M. Louise Bleam continued the study on the binding of small cations to nucleic acids. Supported by NSF. Chemistry. (NAA) 64 samples, 35.5 sample hours. Professor J. C. Wright and 2 graduate students. NAA for erbiun and eurcpium in calciun flouride crystals . Chemical Engineering. (NAA) 34 samples,16 less than 15 minutes, 72 sample hours. Graduate student Woody Shifie-t used "AA services to measure chlorine concentrations in aluminum oxide and silica gel. Graduate student James Welch used NAA to determine elemental in-purity levels in agricultural soils. Consolidated Cigar Company,. (NAA) 38 sample,117 sample hours. , Measurement of bromine levels in tobacco. Dairy Science DepartTent. (NAA) 2,703 samples , 8,013 sanple hours. Professors L. Satter and N. Jorgensen, 3 graduate students. Use of stable tracers in feed to deternine digestibility, rumen turnover and rate of passage in dairy cattle. Supported by atch u Act, State Funds, and Gift Funds. Forest Products Labora tory. Staff member T. Jef fries and post-doc-toral student David Eaton analyzed ashed paper mill sludge for elenental cons ti tuen ts . Geology and Geophysics. (NAA) 16.sampies , 34.72 sample hours . Graduite Student Jeffrey T. Keith used NAA to determine diffusion direc-tion of 25 elements in a nagna chamber by analyzing sarples of volcanic tu f f. Sponsored by Noranda Explorations , Inc. , Denver, Colorado. Geology and Geopjhysics. (NAA) 50 samples, 23 less than 15 ninutes, 44 sample hours. Professor Campbell Craddock and I graduate student studied the concentrations of trace elements in basaltic rock. P es ea rch was supported by NSF. _ Globe Union, Inc. (NAA) 971 samples, 499 less than 15 minutes, 1147.75 sample hours. NAA . service used to determine impurity levels in lead and lead oxide which might have importance in batt'ery performance and failure: rate. Institute of Caper Chenistry.- (NAA) 216 samples, 24 less than 15 minutes, 249.6 sample hours. Initial study to determine saitability of
. various glass fibers for tracing flow through a reaction- vessel . -Also, activation of fibers for' use in tracing holdup and mixing of fibers in paper formulation.
, Kewaunee Nuclear Power Plant. (MAA) 29 sanples, 20 less than 15-minute irradiations.18 sample hours. Use of NAA 'to determine composition of yellow material found inside piping in the spent fuel pool of the power 4
-plant. Measurement of chlorine levels of oil-absorbing naterials.
Mechanical Engineering. 12 samples, all less than 15-minute irradia-tions. Professor Borman and graduate student Al Jessel used the reactor ir-radiation-services to produce Argon-?l gas for' use in studies of combustion process in deisel engines. Supported by 00E and Detroit Deisel-Allison Division of General Motors. Medicine. (NAA) 72 samples, 67 less than 15 ninutes, 4.13 sanple hcars. Professor R. Barreras and I sta ff member. Detaraination of rela-tive dissolution of aluminum and magnesiua hydroxide from nixed gels re-acting with acid and gistric juice in order to study the' efficiency of mixed antacids for human use. Supported by a gift frca the Lewis Howe Corpo ra tion . Medicine. 5 samples, all less than 15-minute irradiations. Pro fes-sor Stuart Updf %e and 2 additional sta ff members utilized tracers produced at the' Reactor Laboratory to measure catalytic ef fects in nembranes used
- in arti ficial kidneys. Supported by National Institutes of Health, i
Metallurgical and Mineral Engineerinc. (NAA) 2 samples, I saaple f hour. Professor Roger Boom anc i. graduate student. '!easurement of iron concentration in ore samples. Nuclear Encineering. Instructional. 195 samples, 81 less than 15 minutes, 343.9 sampic hours. ME courses 427 and c28 irradiations. Nuclear Engineering. 317 samples, 203 samples less than 15 ninutes, 159.7 sample hours. Irradiations in support of operator training courses, flux measurements, and development of standards and techniques in the neu-tron activation. analysis service. ! Nuclear Encineering. (NAA) 9 samples, all less than 15-minute ir- I radia tions . 1 grad student. Measurement of copper and palladium :encen-t trations in wire samples. Nuclear Medicine. 32 samples,10 less than 15-minute irradiations. 16.5 sample-hours. Professor Gatley, 2 additional sta ff members, 2 grad-uate students. Production of fluorine-13 and copper-64 for pharmaceutical use. Sponsored by Mational Cancer Institute, UW Graduate School, and Ulv School of Mecicine. 1 4 Physics and Nuclear Engineering. (NAA) 2 samples, both less than 15-minutes. Professors Kerst and Post together with graduate students working on the octopole used MAA serv'ce to determine the material being deposited on 3 glass rod in the plasma chanber. Research is supported by 00E.-
Radiolocy-Human Oncology. (NAA) 7 samples , 3.5 sample hours. Pro-fessor A. Wiley and 1l graduate stadent. Detection and monitoring of heavy elements in human tumors. Supported by private patient donations, Univer-sity Radiotherapy Associates R 3 D Funds, and flational Cancer !nstitute. Soils Department. 387 samples, 93 less than 15 minutes ,1183 sample hours. Professor Philip Helske, I additional staff member, 5 graduate stu-dents and 1 undergraduate student. Trace element studies of soil and fly ash by neutron activation analysis. Supported by Environmental Protection Agency. Soils Deparcaent. Neutron activation analysis of sotis, rocks, nin-erals, and biological materials to understand the behavior of elenents i 2 natural systems. I staff member, i post doctoral fellow, 3 graduate stu-dents, and I undergraduate student. Supported by Environmental Protection Agency, Hatch Act, Wisconsin Power 5 Light, Madison Gas & Electric, Uiscon-sin Public Service Corporation, U.S. Army Cold Regions Research and Engi-neering Laboratory, Department of Energy, and "iational Science Foundation. Universg o f tiinnesota-Duluth. (NAA) (Reactor Sharing Progran) 313 saaples, 592 sanple hours. Professor George Rapp, 2 additiona' staff
- nembers and a number of graduate students continued to be involved in studies of trace element concentrations in artifacts, both metallic and ceramic, as a neans o f identifying comon origin of these materials. Sup-ported by the Department of Energy. '
University of Wisconsin-Oshkosh. ('lAA ) 55 samples, 33 less than 15 minutes , 50 sample hours. Professor Jack Propp,1 additional staff rem-ber, and 3 students are involved in determination of heavy metal content in !
. river sediments above and below the City of Appleton. Supported by National l Science Foundation.
U.S. Department of Acriculture, Beltsville, MO. (NAA) 513 samples 27 less than 15 minutes, 297 sample hours. Use of stable tracers in study-ing utilization and turnover rates of animal feeds. Water Chenistrz. (NAA) 107 samples, 214 sampic hours. "easurerent j of arsenic, iron, and chromium content in sediment samples. 5 Chances in Person _nel, Facility, and Procedures Changes reportable under 10 CFR 50.59 are indicated in Section E of this report. The refueling of the reactor to a full FL!P fuel core was com-pieted during the year, and a document detailing the test prograa verifying the core operating characteristics (about 120 hours of reactor operating
' time) is attached.
No changes in personnel occurred during the year.
- 6. Results of Surveillance Tests Surveillance tests and inspections during the year revealed no safety-related defects. Operating personnel performance evaluations under the Operator Proficiency "aintenance Program showed no deficiencies on writt?n or oral examinations.
During inspection of fuel elements, rust aas detected on the unmachined surfaces of several of the newer FLIP fuel elements. The problem was inves-tigated by the fuel manufacturer and by the Reactor Sa fety Committee member specializing in metallurgy. Both investigations concluded that the ust was a result of improper passivation of the element top end fittings and that the presence of the rust did not preclude continued operation or make fuel leaks more likely. The portions c f the end fittings that had surface layers removed showed no rust, and only machined portions are associated with joining the fitting to the clad or with allowing differential expan-sion of the fitting with the bundle end fittings. No corrective action was considered warranted by either review. Loading to an all FLIP cperational core was cenpleted during the year. A documen" entitled " Core Test Program - All FLIP Core" is appended _a this i report. Additional testing of the core af ter more than 500 MW-Hours of opera-
- tion showec an increase in core excess reactivity of 0.025 ak/k, as expected for an all . .IP core.
B. OPERATI"G STATISTICS AND FUEL EXPOSURE The fuel exposure and operating data below are given for the previous fiscal year and for the total time since conversion to TRIGA fuel Since several mixed fuel cores were operated before reaching the present opera-tional core (23 FLIP bundles and 12 graphite reflectors) a breakdown is l also given showing total operation for all TR!GA cores used. Core or Cperative Period Sta rtup,s Critical 'dours MU Hours Pulses i FY 79-80 322 980.61 619.52 74 i Total--All Triga Cores 2387 8092.48 5699.35 laac ' i Total--Present 23 Bundle All FLIP Core - First Critical- 7-31-79 5 916.70 559.57 74 Interin 21 Sundle All FLIP Core - First Critical 6-15-79 96.03 87,46 0 15 Sundle FLIP - 10 Bundie Standard Core - First Critical 1-3-78 696.95 15.99 137 9 Bundle FLIP - 16 Suncle Standard Core - First Critical 3-4-74 1575.30 49.54 283
TRIGA core operating data'(continued) Critical Hours MU Hours Pulses All Standard Fuel Core - First Critical 11-14-67 4807.50 3479.00 941 C. EffERGENCY SHUTDOUNS AND IMADVERTEMT SCRAMS There were no emergency shutdowns during the year. There were 34 inad-I vertent shutdowns distributed as indicated below. 17 trainee operator error trips: 9/24/79, 10/4/79, 10/18/79, 10/22/79, 12/3/79, 12/3/79, 1/17/30, 1/21/80, 3/5/30, 4/4/80, 4/11/80, 4/16/80, t/17/SO, 4/18/30, 5/12/80. These trips resul ted fron impropor range switching on the safety channels as power was increased or decreased. Trip occurs at 1255 of range in any range, and changing range switches at inappropriate times or in the trong direction causes a trip. 12/7/79 trainee received period trip from excessive rod withdrawal . 6 high vol tage power supply mal func tions. Period trips 7/24/79, 3/1/79,10/a/79,10/4/79,11/1/79. High voltage failure trip S/3/79. The several trips in this series resulted from acmentary variations in the positive high voltage power supply to the detectors. The power sup-ply never could be made to fail while on the bench or while diagnostic equipment was attached. ?!ajor systen conponents were replaced one at a I time to isolate the component causing the failure (detector, Log-M period Amplifier, high voltage power supply, current limiting relays in high vol-tage power supply,vacuun tubes). When the problem was finally localized to the power supply, all high voltage capacitors were replaced. Finally, the intermittent failure was eliminated by replacing the solid state high voltage rectifier in the power supply. Since the power supply is more than 20 years old, it is scheduled to be replaced when an appropriate substitute is obtained. 2' period trips from actual short period. During reactivity measurenents to determine worth' of large reactivity worth samples, the worth of a cadmium-filled sample had been determined to be .269"p. The trips resulted from attempts to determine whether the auto-matic control system could cope with removal of such a sample in I23-R10 core. It can if the samples return by the usual mechanism of turning off i 't
-c - - -
l 1 1 flow to the jet pump which pulls the sample down into irradiation position, l but it cannot if the samples are pulled out with a retrieval dei / ice provided for non-bouyant samples. In the cperational core presently in use (I23-R12), the worth of the sample is 0.14 and the automatic control systen can compen-sate for sample removal by either means. i l 1 fuse holder failure. Fuse F3 holder indicated a bicwn fuse. The fuse was found to be good, but the holder could give interaittent open indication. The fuse holder was l replaced 9/25/79. 1 period trip from cable being humoed. Coaxial cables to the Log-N CIC were in the open at the pool top before the detector was relocated. ! i When at low power,an operator bumped one of the cables to the detector and , j a period trip occurred. 11/1/79. l The detector has been relocated and accessible cable runs are in metal l 1 conduit. See the section of this report on facility changes. , l 7 trips from switching transients in I.og-N Period Channel . These trips occurred af ter pulsing operation or scon a fter pre- l startup ct}ecklist interlock checks. 1/29/80, 2/1/80, . l/30, 3/3/80, 3/13/30, 4/10/80, 4/14/80. After extensive checking for poor connectors or ground loops in re-located Log-:1 CIC the detector was replaced. The problem persisted on oc-casion and was eventually determined to be an indirect result of the greatly decreased gamma radiation level at the new position of the Log-i detector. Procedures required that the compensating voltage be set before each startup from source range (a necessity at the previous location). At the new loca-tion the detec'.or current was essentially zero when the reactor was shut down (no substantial full power operation within 24 hours) regardless of compensating vol tage. With extr2mely low compensating voltages applied, switching transients appeared to plac) charge on the cables which resulted in period spikes. The startup procedure nas redified to require that the compensating voltage remain at a preset level, and this change eliminated the problem. D. MAINTENANCE OPERATIONS-Ordinary preventive maintenance was performed on all equipment. Unusual maintenance probicas were detailed in Section C under discussion of events causing reactor trips. 1
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. J Inspection of control rod drive wiring showed deterioration of wire insulation in exposed ends of a coiled cable that connec',s to rod drive mag-nets. The deterioration was due to oxidation on one er d and oil absorotion on the other end. Insulation within the outer cable jacket was in good con-dition. Although no problems had been experienced with insulation breakdown, the cable ends were removed and new connections made on the magnet cables.
Other cables within the drive were also checked and reterminated, with some fiber insulation sleeves replaced with heat shrink insulation. E. CHAhdES Iti THE FACILITY CP PROCEDURES rep 0RTABLE U:DEP 10 CFR 50.59 , 1. The Log-t; CIC was moved from its previous location in a bridge corner post (in-water location) to the thermal r olumn. The cove was due to (1) obtain a better neutron /gatma environment, (2) eliminate supra-i linear behavior due to location of the detector above the core, (3) place the detector in a dry environment and (4) eliminate period trips due to l bumping exposed cables to the detector. .The increased amount of full power operation due to the requirenent to maintain fuel at self-protecting radia-tion level for extended periods of time made proper compensation of the de-tector ve:ey difficult in the previous location. In the thermal column, the detector is separated from the core by 2.5 inches of lead and 36 inches of , graphite. Garna compensation is much improved with the new location. The relocation was completed on January 18, 1980.
- 2. Detector operating voltage for all CIC's and the fission counter was decreased from 750 volts to 15C0 volts on March 3,1980. The change was primarily the result of a desire to move the voltage further below the maximum voltage rating of the fissico counter and to allow use of spare fission counters which exhibit breakdcwn at voltages above 700, volts.
Since the 750 volt operating level was originally set to allow use of a l B-10 proportional counter as the original source range instrunent, and fission counters had been used for source range for many years, there itas ' no need _ for the higher voltage. In addition, the planned replacement of the high voltage power supply is easier to implement at the 500 volt level.
- 3. The fire alarm system for the Mechanical Engineering Suilding is 1
in the process of substantial revision and will be completed by July 21, 1980. A part of this revision is the addition of 3 nanual alarm stations,
. smoke and heat sensors, and alarm horns in the Reactor Laboratory. This is a ansiderable change for the laboratory since no alarm sensors had pre-viously been installed in the laboratory.
- 4. A new emergency procedure (UWGR 154) detailing responses to breaching of the security of the Reactor Laboratory and thef t or threat of theft.cf SNM was drafted and approved by the Reactor Sa fety Committee on fiay 20, 1980.
F. RADICACTIVE *.!ASTE DISPOSAL
- 1. Solid Maste There was no solid easte transferred out of the laboratory during the year.
- 2. Liquw Waste Table 1 shows the record of liquid waste disposal during the fiscal yea r.
3 Particulate and Gaseous Radioactivity Released to the Atmosphere Table 2 presents information on stack activity discharged during the year. G. SU." MARY OF RADIATIC:1 EXPOSURES (1 July 1979 - 14 May 19S0) tio significant exposure of personnel occurred due to operation of the reactor. For occupationally exposed personnel: tne highest annual whole body and s, kin doses were 140 arem and 170 mrem respectively, while the highest extremity dose for the entira year was GO mrem. For labora tory students, the highest annual whole body and skin doses wert 30 mren and 70 mrem respectively. No facility visitor received any measurable dose. Routine radiation and contamination surveys o f the facility revealed no areas of high exposure rates or contamination. H. RESULTS OF_E"VIRON'1ElTAL SURVEYS i
'The enviroaaental monitoring progrca at Wisconsin consists of thermo- I luminescent dosimeters (Lif TLD service from Eberline) located in the area surrounding the Reactor Laboratory.
The table below lists doses for persons continuously in the area for representative dosimeter readings . Annual Dose Da ta-Environnental '!onitors location Average Dose Ra te-mremhzeek i Inside Wall of Reactor Leboratory 3.20 .54 l Inside Reactor Laboratory Stack 1.44 .53 I Highest Dose Outside Reactor Laboratory (Reactor Lab roof entrance window: Monitor adjacent to stone surface) 2.37 .81
7 .. r < Annual Dose Data-Environmental Tionitors (Continued): !
' Loca tion Ayerage_ Dose Rate-mremhteek Highest Dose in Occupied ilonrestricted
, . area (third floor classroom facing away from Reactor Lab) .52 .09 Average Dose in 0ccupied tionrestricted Area .36 : .16
- Average Dose in All Unrestricted Areas '
i (29 Monitor Points) .51 .43 1
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i I-i I ( l i i 1-t 1 i l 4 e i i 1 i 9 I. . ? ?
- . - , , . . . - - - . -. , . . . . - - . , _ . - - . ~ , . - . - . . . . - - - - - - - . _ . . . . . . - - - . - . . , . . - . - - . - . - - . - , .
TABLE 1 LIQUID WASTE TO SANITARY SEMER 11 SEPT 79 3 JAN 1930, 17 MARCH 1980 25 MAY 1980 TOTAL TOTAL ACTIVITY DISCHARGEl' (Mic rocuries ) 171.46 16.42 325.06 68.77 581.73 LIQUID CUM;TITY (Gallons) 1030.0 800.0 900.0 800.0 3530.0 Ra226 - MPC USED - 4x10-7 AMOUNT (pCi) 2. 31 0.224 -- -- 2.53
-CONC (uCi/nl) 5.92x10-7 7.48x10-3 Ru lC5' - MPC USE0 - 4x10-4 AMOUNT (pCi) 4.40x10-4 --
0.008 8.48 18.49 CONC (pCi/nl) 1.12x10-10 2.43x10~9 . i x10-5 CoS7 - MPC USE0 - 2x10-2 AMOUNT (uCi) 0.087 -- -- 5.66 5.75 CONC (;Ci/nl) 2.24x10-8 1.87x10-6 CoS8 - MPC USED - 4x10-3 AMOUNT (uci) 3.74 0.20 -- 8.54 ,. 12.48 CONC (pCi/ml) 9.6x10-7 6.73x10-8 -- 2.82x10" Co60 - MPC USED - lx10-3 AMOUNT (pCi) 69.61 0.156 83.64 3.01 - 156.42 CONC (LCi/al ) 1.68x10-5 3.17x10-3 2.53x10-5 1. 94 x10" Zn65 - MPC USEO - 3x10-3 AMOUNT (pCi) 12.49 0.54 160.9? -- 173.30 CONC (pCi/nl) 3.21x10-6 i.79x10-7 4.73x10-5 Mn54 - MPC USED - 4x10-3 AMOUNT (uCi) 15.26 -- 55.34 19.48 81 .08 CONC (LCi/ml) 3.92x10-6 1.63x10-5 3.46x10-6
);40 - MPC USED - 9x10-5 AMOUNT (pCi) 2.55 0.79 9.82 --
13.16 CONC (pCi/ml) 6.56x10-7 2.62x10-7 2.89x10-6 Fe 55 - MPC USE0 - 2x10-2 AMOUN7 (uct) 53.8 9.05 -- --
$2.85 CONC (pCi/nl) 5.59x10-5 2.99x10-6 Fe59 - MPC USED - 2x10-3 AMOUNT (pCi) 0.997 0.168 -- --
1.16 CONC (uCi/m!) 8.86x10-8 5.54.10-8
- Cr51 -~ MPC USED - 5x10-2 AMOUNT (aci) 10.64 5.29 15.35 22.6 . 53.88 CONC (uci/nl) 2.73x10-6 1.75x10-6 4.50x10-6 7.47x10-0 Average concentration at point of release to sewer = 4.35x10-5 pct /ml (includes natural radioactivit/ ).
Average daily sewage flow fcr dilution = 2.37x104 gallons Average cancentration af ter dilution = 1.78x10-8 nCi/ml
7 4 i J TABLE 2 EFFLUENT FROM STACK i 1. Particula te Activitz There was no discharge of particulate activity in excess of background levels.
- 2. Gaseous Activity - All Argon 41 Activity Maximua Instantaneous Average Stack Discharged Concentration Concentration .iPC Used Manth (Curies) uCi/r1x10-6 uCi/alxi0~8 aCi/ml July 79 0.2427 1.0 13.0 2.4x10-5
- August 0.1825 0.8 9.8 i Septenber 0.1532 6.1 9.9 i
' October 0.1915 1.0 10.7 floverc,b er 0.2590 1.5 13.9 ! December 0.1916 2.2 11.11 January 30 0.2748 0.45 16.2 o r ebruary O.'182 3.7 15.6 Ma rch 0.4684 3.2 27.9 April- 0.0839 1.0 4.S4 May 0.1152 1.05 6.22 June 0.2684 4.5 16.0 g
- -7 j TOTAL 2.679 6.1x10-6 ltaximum 1.30x10 Yearly Average 1 The MPC value above is that calculated in the SAR to be equivalent to
-8 i 3x10 aCi/ml in the area surrounding the laboratory.
4 i I i i 4 L___ .-_,_ . - _ _ . , _ _ . _ _ _ _ . . -
_14_ I. PUBLICATIONS AND PRESENTATIONS ON ':0RK BASED 0:1 REACTOR USE Biochemistry . G. F. Leatham, PhD Thesis, " Selected Physiological and Biochenical Studies of _ Growth and Development of Shiitake, the Edible ' Japanese Forest "ushroom, Lentinus Edodes. 1979. Geology & Geophysics Je f fe ry D . Ke i th , M.S . The si s . "'iictene Porphyry Intrusi tons , Volcanism, and Mineralization, Southwestern Utah and Eastern ' Nevada. 1980 Two additional _ publications will .be' written during the coming months.
- Nuclear Encineering, Energy Systems and Policy Research Program Gary J. Russell, Samit K Bhattacharyya and Wesley K. Foeil, "A Hybrid Static /0ynamic Heating Technique for the "easurement of Nuclear Doppler Effects, Nuclear Instruments and Methods 143, pp 99-111 (1978).
Radiology, .'uclear Medicine Section) S. J. Gatley and W. J. Shaughnessy, " Synthesis of I 8F dcocy fl uoro glucose with a Nuclear Reactor", Int. J. of Appl . Radiat. Isotopes, (in press). S. J. Gatley, R. D. Hichwa, L. M. Liebernan and R. J. 7lickles , " Aspects
- of the Production of. I8F deoxy-2-fluoro glucose", Int. J. of Aopl . Radiat.
Isotooes, (in press). j S. J. Gatley and W. J. Shaughnessy, "Sucleophilic Substitution with Fluoride", J. of Labelled Comrounds and Radiopharmaceuticals, (in press). Soils I
; Heimke, Habermann, Hanson, "Reacticos of Fly Ash", Water Resources Center i Publica tion , 1979.
Glenn Hanson, M.S. Thesis, " Fly Ash Mineralogy",1973. Fernando DaSilva, PhD Thesis, " Trace Elements in Wisconsin River Sediments", I in progress. fjaria DaSilva, PhD Thesis, " Mineralogy of Wisconsin Glacial Deposits", in progress. Heinke, P. A. , W. P. Robarge, R. L. Korotev and P. J. Schomberg, " Effects of Soil-Applied Sewage Sludge on Concentrations of Elements in Earthworns", J. Environ. Oual. 8: pp 322-327, 1979. May, H. M. , P. A. Helmke and M. L. Jeckson, "Gibbsite Solubility and Therr.o-dynamic o roperties of Hydroxy-Aluminum Ions in Aquecus Solution at 25 C", Geochim. Cosmochin. Acta 43: pp 861-253, 1979 Hanson, G. D., M.S. Thesis, " Pozzolanic Reactions of Fly Ash and Mixtures - of Fly Ash and Flue Gas Desulfurization Sludge,1979. ' Checkal, R. T. . M. S. Thesis, " Isotopically Exchangeable Zinc in Wisconsin . Soils, 1979. Helmke, P. A. and R. D. Koons, "Long-Term Ef fects of Heavy "etals in Land Treataent-Trace Element Migrition in Soils", U. S. Army Cold Regions Research and Engineering Laboratory,1980. Koons , R. O . , P. A. Helmke nd M. L. Jackson, " Association of Trace Elements with Iron Oxides.During Rock Weathering", Soil Sci. Soc. Am. J. 44: pp 155-159, 1930.
d a 1 THE UNIVERSITY OF WISCONSIN
- NUCLEAR REACTOR i
4-i. l. i s i j CORE TEST PROGRAM l- ALL FLIP CORE I i l 1 i PREPARED BY: R. J. CASHNELL DEPARTMENT OF NUCLEAR ENGINEERING T JANUARY 1980 'l s
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THE JUVE?.$ITY OF '4:SCONSIM lUCLEAR REACTOR CORE T ST PROGPNi -- ALL FLI? CCPE INTRODUCTION This report details the loading and testing of the core for the University of Wisconsin reactor, which is constituted of all FLI? fuel bundles. A number o f di f-ferent cores were loc.ded end investiga ted before selection of an operational core for long-tern use. This report gives data deve!cped during the period of the sest program which lasted ' rom June through Novemoer,1979. A. LICENSE CPANGES H AUTHOR:ZE FUEL Amendment No.14 to License R-74 was issued with an e f fective date of 14 April 1979. This amendmer' authorized a larger posses 3f on limit to enable use of an all FL!? core and continued possession of the standard TRI3A fuel already on hand. In addi tion, the license is written in accordance with the current rphasis on sa fe-guarding of Special Nuclear '43terial to include a provision that no race than 4.5 kilograms of Uranium-235 in the form of Uranium enriched to >2M nay be 1 eft in a "non-sel f-prote: ting" sta te. The provision m ans that the FL:? fuel on hand that has irradiation level of <100 rem per hour at three feet can not total more than 4.5 kilograms contained Uranium-235. This license provision is slightly more re- -trictive than the limit contained in the regulations on 5N'i which indicates up to 5 kilograms of non-sel f-protecting Urantun-235 may be possessed without being :an-sidered a Category I facility. The plan for loading the fuel, therefore, was to receive two shioments o f <4.5 kilograms Uraniun-235 :ontent with sufficient operation at high power levels a fter receipt of the first shipment to assure attainnent o f self-protecting level of that fuel before the second shipment was received.
- 3. FUEL RECE!?TS Notice of shipment of the first batch of fuel U.92 kilograms Uraniun-235) was received on 30 Vay 1979 .vith an estimated time of arrival of 1 June 1979. The shipment finally arrived on 13 June 1979. The shipnsnt was delayed in part because of an overly optimistic estinated tine of arrival and in part because sf the diffi-culties concerned with trucker unrest during the summer of 1979. Reports of blocked roads and gunfire directed at trucks on the road were quite ccmron during that time interval . '4e, there fore , noti fied General Atomi: that .ve did no t ent the secord shi; ment of fuel shipped until the situation with the truckers had e-turred to normal. A large number of telephone calls to ':RC personnel and to General Atomic were necessary during this time period in ordar to rcaintain an idea of where the fuel was and comply with NRC regulations.
The second shipment of fuel (3.13 kilograms Uranium-235) aas received on 26 July 1979, one day before the announced estimated time of arrival . The #frst batch of fuel had been resident in, the core long enough to assure that all the FLI? fuel on hand wa sei f-protec ting.
' The top"end boxes for -the first shipment of fuel were delivered without the hel fcal _ thread inserts installed. The inserts were procured locally and installed-in our machine shop so thati fuel- assembly and initial operation could take place as' scheduled. Two of the bottom end boxes in the second shipment of fue' (for bundles- 57 and 59) were unusable because the holes into which the eleme.. are threaded did not have parallel axes. The non-parallel axes caused interference between the fuel elements which would not allow the elements to seat properly at the end box when using the torque specified by our fuel assembly procedure.
General Atomic was contacted and replacenent end boxes were received in November 4 ] so that the fuel could be assembled properly. Fortunately, however, there was l enough FLIP. fuel on hand to complete the loading of an all FLIP core. Original plans were to have 25 tundles of FLIP fuel in the core plus two spare bundles plus two spare instrumented elements on hand. Therefore, the total
-inventory of FLIP fuel on hand is twenty-six 4-element bundles one 3-element bun-die containing a transient control rod guide tube, and two spare individual in-strumented elements, for a total of 109 FLIP individual elements.
C. LAST OPERATION OF CORE LOADING G25-R10 -(15 FLIP bundles and 10 Standard bun-
~~
3Tes) Core G25-R10 was last operated on 14 June 1979. At that time, total opera-ting statistics sere: Item G25-R10 Core Total on 'RIGA Cores Critical Hours 596.95 7079.75 Megawatt Hours 383.82 5052.32 Pulse s Fired 117 _1361 Core Excess Reactivity 3.77%
- 0. CRITICAL EXPERIMENT AND INITIAL OPERATION 0_F,PC'lER All standard fuel was removed, inspected, measured, and stored in storage baskets that fit in the bottom of the-pool. The 15 FLIP fuel bundles that con-stituted the central portion of G25-R10 loading were left in place.
On 15 June 1979, loading of new FLIP fuel began. Initial criticality was reached with 13 'uel _ bundles at 1432 on 15 June 1979. Excess reactivity of this core 'was -0.077% reactivity with a shutdown margin of 7.5% reactivity. The remaining 3 FLIP bundles ca hand were loaded to constitute an all FLIP core designated H?l-R10. H21-R10 is essentially a 5x5 array of fuel with the four corner positions vacant. This core had an excess reactivity of about 3% reacti-vity with a neasured shutdown margin of 4.5% reactivity. With the most reactive control blade (13) 'and the regulating blade full out., shutdown margin was 1.5% re-activity and, thus, this core met technical specification requirements. The transient control rod was measured to be worth 1.5% on 18 June 1979, and the' drive was shimmed out 0.25 inches to reduce the transient control rod worth to 1.33% ' reactivi ty. Power calibrations and full power runs were thea begun in
order to. bring the fuel to sel f-protecting levels. This core was not evaluated for pulsing operations since it was not intended as a long term operational core. A number of power calibrations were made as the calibration shifted due to flux dis-
..tribution changes while the new fuel was initially exposed. As with previous cores, we noticed gradual changes in power calibration until a pulsing operation had loosened clad to give a more stable fuel temperature distribution.
Core H21-R10 was operated until 30 July 1979 when the operating statistics were'as shown in the table below: Item H21-R10 Core Total on TRIli Cores Critical Hours 96.03 7175.73 Meganatt Hours 87.46 5139.73 Pulses. 0 1361 l E. LOADING TO OPERATIONAL CORE On 31 July 1979 loading to the opera tional core was bequn. The planned : ore, H25-R10, was identical to the previous operational care (G25-RIO) except that all fuel would be FL!p fuel . Loading from H21-R10 to M25-R10 was done in three steps wi th excess reactivity estimated and shutdown margin ceasured at each step. Core H25-R10 had an excess reactivity of about 5.1% reactivity with a measured shutdown margin of 2.05% with 3 whale tubes and the porpoise tube in place. These
; experimental facilities were removed and shutdown margin was nessured to be 2.2%
reactivity, indicating a worth of -0.25% for these four experimental facilities.
- The transient rod worth was measured to be 1.37%. Further tests indicated that
! technical specifications 'or shutdown margin with the most reactive control element and the regulating -blade full out could 'not be met for this core.
All reflector elements were removed increasing the shutdown margin to 3.675. Further measurements were made on the 25 bundle core with no graphite ce flectors (core H25) to yield the following measured characteristics: H25 Core and Variants Item Reactivitv Wortn - i c 11- Control Blade l.99"
#2 Control Blade 1.76%
#3 ControlE Blade 2.66%
Regulating Blade 0.40%
-Transient Control Rod 1.39" Shutdown Margin '(Reg Blade Out) 3.10%
Approxima te Excess Reactivity 4.20%
- North of Corner Fuel 3undles. (each) + 0.42%
Worth .of Fuel Sundle in 07 or 03 0.97% Add 10: Reflector Elements in A and G Rows + 0.904
4 Although the shutdown margin was considerably greater than the . worth .of #3 control blade, the flux shape cnange occurring with the regulating Made out and 13 control blade full out, if the. next control element withdrawn is the transient control rod, takes the stuck rod shutdo.9n margin only 0.155 p instead o f the re-quired minimum'of 0.2% o stated in the technical specifications. It is , there fore, not possible to use H25 as an operational core. Considerations involved in selecting the operaticnal core are as follows:
- 1. The' core should be as symmetrical as possible for ease in calculations
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and _to equalize control blade worth, b 2. It is preferable to have graphite reflectors in the A and 3 rows to , couple flux into the thermal column (for the linear power detectors) and
, the ' pneumatic tube (for irradiations).
- 3. In view of the license limit on SW which is not sel f-protecting and be-cause of uncertainties involved in the "Upgrada Rule", it is desirable to have as little fuel as possible that is not self-protecting since we
.i have, as part of our inventory,10 FLIP elements intended as spares if we run a 25 bundia core. The option of taking the 4 corner bundles off and using this for the oper3tional core would give an unieradiated total of-25 individual fuel elements or 3.2 kg of 70", enriched fuel tha t would always be :on-sel f-protecting. For this reason, a 21 bundle core was very i undes i ra bl e. 4 It is desirable to maximize the thermal neutron flux available for irra-dia tions and to minimize the reactivity worth of samples undergoing f r-radiation when this can be accompiished.
- 5. The core, of ccurse, must meet all technical specification requirements, ,
including no vacant lattice positions except on the periphery of the core.
- 6. Finally, it is desirable that any instructional experiments, such as Cri-tical Experiment, be performed with as little disturbance of experimental facilities and i strumented n fuel elements as possible. Since the Critical Experiment is performed often, both as part of the NE 428 sequence and in "tility operator training programs, it is desirable to have a core which can be unloaded to a substantially subcritical configuration and reloaded to critical without any manipulation of whale tubes, porpoise tube, source holder, or the instrumented elements and their hold downs.
The above considerations led to selection of a 5x5 array of fuel bundles .vith the center bundle on two sides removed and with graphite reflectors on the other two sides. This core was designated I23-R10. l
- F. I, SERIES CORE TESTING A diagram of Core 123-R10 is. shown in Figure 1. The two vacant fuel bundle i positions on the periphery of the core (positicnc 03 and 07) were expected to yield
. intense thermal neutron fluxes for irradiation. Checkout o f core !23-R10 continued wit! measurement oi reactivity sorth, fuel temperatures, fluxes, and pulsing charac-teristics. Unfortuna tely, the requirerents for maintaining the fuel sel f-protecting i
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interfered with carrying out a core test program in the usual manner. The core test program extended through the beginning of the" fall semester and into the rela-tively heavily scheduled use of the reactor for training purposes. Several variants on the 'casic 23 bundle' core were investigated and information developed on several of these cores is- included in subsequent parts of this report. Available thermal neutron fluxes in the vacant positions on two sides of the core wers, indeed, quite high as expected (up to 1.4x1013ny). Un fortuna tely, gcid cadmium ratios in these areas were quite low (as low as 1.9). Gamma ray and neutron heating were quite intense resulting in rapid damage to polyethylene sample contain-
.ers. This is undesirable since most sample irradiations at the facility are in sup-port of instrumental neutron activation analysis, and samples are counted in the same container in which they were irradiated. Sample container swelling and defor-mation as a result cf heating and radiation damage prevent proper operation of the automatic sample : hanger. Finally, samples irradiated in the 03 and 07 water gaps could have large reactivity effe<.ts bn reactor operation, which is also undesirable.
!n order to improve the core performance in view of these problems, a number of core variations were made in order to optimize irradiation positions. The cores are all based on the I23-R10 arrangement (Figure 1). Core I23-R12 (Figure 2) di f-fers by addition of graphite reflector elements in positions D3 and D7 with whale tubes (hydraulic f rradiation facilities) shifted out one row from their location in 123-R10. Cores I23-R14 and -Rl5 have additional graphite reflectors located in po-sitions C8, E3, and/or C2 and E2. Table 2 presents r.easured neutron fluxes in the several. cores checked, while Table 3 indicates the reactivity worth of various types L of samples in cores . I23-Rio and -R12. Based primarily on the results on the flux and reactivity measurements, the final operational core selected was I23-Al2.
Graphs and data are given in the remainder of this report for both I23-R10, and -R12, with some supplemental information for other core variations. Fuel ele-ment temperature distributions and a comparison with calculated values are given only for core 123-R10. Flux capping within the active lattice of the core was also ' completed on the -RIO ccre. Since the two' cores are substantially similar, differing only in the presence of graphite reflectors in positions 03 and 07, the flux distributions would appear to be quite similar. ' A~ comparison of the characteristics in Table 1, however, shows that addition of the graphite reflectors in place of the water gaps, decreased the prompt neutron lifetime slightly yielding larger pulses for she same reactivity input, while control blade worths and excess reactivity were also increased by flux shift resulting from the presence of the reflectors. Despite the ?otential' for confusion, graohs in the remainder of the report are
. grouped by parameter indicated rather than by core arrangement. This technique is used because some curves are applicable to more than one core loading.
G PRESENTATION AND EXPLANATION Of CURVES Figures 3 through 15 are reactivity worth curves for individual control ale-ments in 'the several cores, while' Figures 16 and 17 are operational control element bank' worth curves.used for excess reactivity and reactivity effect measurements. e
p ' Additiot of graphite reflector 11emeats quite evidently shifted flux into the
- control blade shrouds giving increased worth for cantrol clades with little change in transient rod worth. As shown in Figure '3, however, the loss of reactivity with power level was the same for botn the -21] and -R12 variations of the I core. Also evident in Figure 18 is the linear shape.of :he pcaer defect curve due to the variable temperature coefficient of reactivity. Comparing this figure to Figures
, 19 through 22, one notes that the plots of temperature versus power level show a
- decrease in slope as power level and fuel temperature increase as the meat expands toward the clad and i_ncreases the neat transfer. This, coupled with the variable
; temperature coefficient, results in an almost linear increase in power defect with power-level over most of the operating range. The curves showing fuel temperature variations exhibit unusual behavior on indications of the bottom thermocouple in fuel bundle 41. This is due to a previously noted cartial short circuit of this thernoccuple to ground, which makes it read intermittently correct but usually lower 'than the actual fuel temperature.
Table 4 supplies information on power distribution in the core. The values of kw per element snd predicted fuel- temperature are. from two dimensional diffusion theory computer runs with temperature predictions based on :easured response of the instrumented elements in previous cores. Note that the two instrumented ele- ' ments give markedly different responses when the elements are interchanged. I t-is likely that non-instrumented elements also have large dif'erences in internal temperature for the same power density. 'feasurements of fuel tem;'eratures in all represantative positions of the core wera made cnly in core I23-R10. Figures 23 through 33 present flux shape in#ormation as measured by a minta-ture fission chamber in the spacas available for such measurements in one quarter i i of the core. No attempt was made to convert these data to actual thermal neutron fluxes, figures 34 and 35 present curves for initial power reached for square wave
-operation. Although square wave operation is not routinely used for irradiations, it has proved useful in deconstrations and training sessions on reactor kinetic i
behavior. Figures 35 .hrough 30 show pulsing per'ormance of the all FLIP core compared to all previous cores used at ylsconsin and data from the TRIGA prototype. As ex-pected, Figure 33 and 39 indicate quite sinilar behavior for all cores, while
. Figures 36, 37, and a0 show changes due to the reduction in prompt neutron life-time in the FLIP regions. There are slight differencas between the R-10 and-R-12 cores due .to' the slight differences in pronpt necron li'etime, but none af the behavior is unexpected. The non-linearity indicated in Figure 36, particularly on inverse period versus prenpt reactivity insertion, is also due to the shorter neutron li. f atice'. When the response was observel, an extra galvanometer in the
= fast "ecorder ass connected to -indicate wnen the transient control rod began to
_ move and when it' reached its fired position _ relative to the tine at which the pulse began. The fast recorder has three power level indications, one of which t is calibrated at 250.W per inch; the other two which are ampit fled traces are used to obtain period information for pulsing neration. For the 1.39% puise, . the transient-control rod was not full out until 20 miliseconds after the priod i - traces 'went of fscal e. In fact, the pulse had reached about 12% of its final height before _the transient rod impacted on the shock absorcer. For 1.355 pul ses , the transient rod was- full out by the time the period tracas began. These investi-
.gations-(on pulses 1334 through 1358) also showed that the transient red does bounce . a bit about 50 miliseconds af ter it hits the shock absorber, but it is- also poss-F ible- that the indication of'a bounca is due to the unusual way in which the micro-Lswitch senses shock absorber pos'ition.
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- - - -+ ~ + - - - *
' Figures 41 through 44 also present pulse behavior information in the format used _for normal operation where pulse peak power and energy relecse are plotted versus reactivity insertion.
H. REACTIVITY EFFECTS OF EXPEp,IME,1TAL FACILITIES AND SA"PLES The reactivity e ffect of loading 3 whales and the porpoise is negative and does not exceed an absoluta value o' O.3*, reactivity. The data previously pre- - sented in Table 2 indicates that chinging samples in core I23-R12 experimental facilities during full power operation can be adequately controlled by poker co-efficient and the automatic control system. I loading !23-R10, a cadmium sanple would have a large enough effect on reactivit to cause a reactor trip upon re-turn of a whale sample aaruptly, although the opera tion of the whale tube is such that sanples cove very slowly wnen returned, and she reactivity change associated with.it could be controlled by the automatic control system. The reactivity ef-fect of samples was considered as one of the criteria under which the -R12 core was selected. I. REACTIVITY CHANGE WITH SURNUP Figure 15 presents the reactivity history of all TRIGA cores at UWNR to date. We expect only minor shifts in core reactivity for the nex! few acnths since nost of the fuel presently in the core has been irradiated for several- MW days during the period'of time between the two fuel shiprents. The initial, abrupt change in core excess reactivity that was observed when the first 9 FLIP fuel bundles were loaded,-.has not occurred on subsequent cores, and an examination of the slope of the curves for the all-FLIP cores indicates that the fuel lifetime will, indeed, be considerably increased over ~ that of the Standard TRIGA fuel . J. CONCLU: IONS s The core presently in use as the operational loading (!23-R12) meets all tech-nical speci fica tion and operational requirements and is expected to remain the stan-dard core for .3 long period of time unless the experimental program at the labora-tory changes. Should higher neutron fluxes be essential for specific sample irra-diations, they can be obtained with loading :23-R10 at the expense of the capabi-lity of providing routine irradiations in polyethylene encapsulation, and at the expense of con:iderably more radiation damage co sample materbl and considerably increased sample heating during irradiation. 1
TABLE 1 . Reactivity - 7,p
,; '/ALUE Ut VALUE IN PARAMETER I23-RIO 123-R12 Excess Reactivity 3.16 3.80 Shutdown Margin 5.10 4.90 Worth, Slade #1 1.90 2.01
#2 1,77 1 .91
#3 2.25 2.52 Reg. Blade 0.339 0.404 Transietn Rod 1.39 1.39
, . Power Defect at 1 ~ MW l.50 1.50 Fuel Temperatures 'C at Full Pcwer F41 244 241 F42 453 432 ;
Pulse Characteristics for 1.39% o pulse > - Peak Power 950 1140 Full Width at Half Maximum -msec 12.3 12.0 Period - msec 3.6 3.4 i Intescated ?cwer - MW see 13.9 17.2 Prompt Neutron Flux - seconds -6 23x10 22x10'O l i i 4 M i ?
TABLE 2 ' FLUX MEASUREME'iT SU," MARY I23-R10 13 14 Facility & 0 Totai 3d 9th
-Condition. (ny)
P.cd 9 Fast (Fission) (ny) (ny) (Gold Cad- (ny) mium Ratio) Pneunatic Tube 5.53E12 1.39E12 4.14E12 I 3.98 1.17x10 Porpoise Tube-
'E2-No Graphite 1.5E13 5.8E12 9.35E12 2.64 E2-Graphite in D3 1.98E13 6.45E12 1.34E13 3.10 El-Graphite in D3, C2, E2' 8.73E12 2.18E12 6.50E12 4.03 Whale C C2-flo Graphite 1. l E13 3.5E12 7.8E12 3.21 j C2-Graphite in 03 1.56E13 4.00E12 1.16E13 3.91 s.09E12 Cl-Graphite in C2, 03, E2 0.63E13 1.l E12 5.3E12 5.70 1 06E12 i
Mhale 3 West
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07 2.48E13 1.1 E13 1.4E13 2.25 08-Graphite 37' l.73E13 0.687E13 1. 09E13 2.59 3.36E12 t Graphi te 'in C8, D7, E3 1.95E13 7.20E12 1.23E13 2.70
. Whale D East s
, 03 2.56E13 1.36E13 1 .13 1.89 I _D2-Graphite 03 1.62E13 0.567E13 1. 06E13 2.86 3.10E12 02-Graphite in C2, 03, E2 1.56E13 0.653E13 0.922E13 2.45 3.94E12 i i i I l Note: :Th'e- term E13 is used for x10 4 4
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s i p 4 l TABLE 3 i 2 SAMPLE REACTIVITY WORTHS i t i l Core Loading Facility / Location Sample. Reactivi ty '.! orth l 123-R10 Porpoise Tube /C2 cr E2 Void flegli gi ble Cadmium Filled -0. 01 % i 1 Whale /03 or D7 Void -0.01% ! Cadmium Filled -0.2695 I Rabbit Tube H 0 Filted +0.006?: ' C!dmium Filled -0.003s ! I23-R12 Porpoise Tube /E2 Void fle gl i gible i J Cadmium Filled -0.011 % j Whale /02 Void -0.016 N i Cadmium Filled 0.085% Whale /D8 Void -0.026" Cadmium. Filled -0.100% i ! Whale /C2 Void -0.0035 i Cadmium Filled -0.0601 I r Rabbit Tube H 0 Filled +0.0059 C$dmiumFilled -0.0063 i 1 ) i 1 } } i 4 I h, 1 s (- - - -
TABLE 4 CCRE LOADING F25-R10 TEMPERATURES AT FULL POWER
<W in
. 7'redicted Temp. 441 c' 2 2
' Core Position Element (#42)*C Bot Ctr Too Bot ?Er Too DS -NE 15.0 4 c:, Can't Measore NW 14.9 170 Can' t Measuee SW 15.0 490 Can' t Measure E5 NE' 15.5 480 365 332 353 NW 12.4 460 SW 12.6 465 SE 14.6 465 340 362 338 E4 NE 11.9 415 300 315 295 NW 13.6 442 334 350 328 SW 13.7 450 330 350 326 SE 12.1 420 305 325 305 D4 SW 15.2 r/5 390 405 380 492 432 407 SE 15.1 470 426 380 343 E3 NE 14.2 455 277 259 375 337 300 NW 12.2 420 275 290 270 SW 9.9 l 385 275 285 265 i SE. 10.6 395 241 224 l F5 NE 11.6 415 450 400 350 SE 7.9 345 341 301 268 F4 NE 9.3 380 410 362 325 MW 11.0 405 442 395 352 i SW 7.5 340 340 300 270 SE- 6.8- 325 305 270 ~240 F3 NE .8.7 360 31 3 2E2 241 I NW 3.1 345 362 320 280 l
'SW 5.9 300 220 245 230 i SE 6.7 325 242 220 198 l
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