ML20217G639

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Univ of Virginia Reactor Facility Annual Rept,1997
ML20217G639
Person / Time
Site: University of Virginia
Issue date: 12/31/1997
From:
VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To:
Shared Package
ML20217G628 List:
References
NUDOCS 9804020480
Download: ML20217G639 (40)
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[ ~~ 1 UNIVERSITY OF l VIRGINIA REACTOR FACILITY 1997 ANNUAL REPORT l i 1 I l l l 'Ihis report was compiled by the following personnel: Deborah Steva, Reactor Health Physicist Section IV, Health Physics Paul Benneche, Reactor Supervisor All other sections

l [' 1997 ANNUALREPORT UNIVERSITY OF VIRGINIA REACTOR FACILITY 1 (. Table of Contents z. I. INTRODUCTION .............................................1 A. ' Reactor Facility Reporting Requirements............................ 1 1. Reporting Period........................................ 1 [: ' 2. Basis for Reporting...................................... 1 B. Reactor Facility Description.................................... 1 [- 1. 2 MW UVAR .........................................1 l 2. 100-watt CAVALIER..................................... 3 j 3. Past Operating History.................................... 3 [ a. U VA R............................................ 3

b. CAVALIER

........................................5 j 4. Summary of l997 Reactor Utilization........................... 5 _ a. U VAR............................................ 5 5. Special Facilities........................................ 6 C. Reactor Staff Organization..................................... 7 1. Operations Staff........................................ 7 2. Health Physics Staff...................................... 7 { 3. Reactor Safety Committee.................................. 7 I { II. REACTOR OPERATION S........................................ 9 A. UVAR. ................................................9 [ 1. . Core Configurations...................................... 9 2. Standard Operating Procedures............................... 9 3. Surveillance Requirements.................................. 9 ( a. Rod Drop Tests and Visual Inspection....................... 9 b. Tests and Calibrations................................ 12 4.- M aintenance.......................................... 14 [ 5. Unplanned Shutdowns................................... 16 6. Pool Water M ake-up.................................... 16 7. Fuel Shipments........................................ 16 h a. Fre sh Fuel........................................ 16 b. Spe nt Fuel........................................ 16 8. l Personnel Training and Instruction........................... 17 a. Reactor Facility Staff................................ 17 { b. Summer Course for High School Teachers....................17 l 9. Reactor Tours......................................... 17 B. CAVALIER Reactor........................................ 17 1. Reactor Shutdown...................................... 18 [L h_

C 11 East J ill.* REGULATORY COMPLIANCE.... ~............... r......=..i..... ; J 17 = - A. Reactor Safety Committee.................................... 17 ' 1.'

Meeting s....................._ _........................ 17.

2. - Aud its.............................................. 1 8 3. Approval s........................................... 18 .4. 10 CFR 50.59 Reviews.................................. 18 - r B. Inspections.............................................. 18

C.. Licensing Action..........................................

18 D.' Enw.rgency Preparedness..................................... 18 IV. j HEALTH PHYSICS........................................... 20 A.. Personnel Dosimetry....................................... 20 1. Visitor Exposure Data For 1997............................. 20 2. . Reactor Facility Personnel................................. 20 a. Monthly Whole Body Badge Data......................... 20 b. Neutron Exposures.................................. 21 c. Extremity Exposures................................. 21 d. Direct-reading Dosimeter Exposures....................... 22 B. Effluents Released During 1997 _................................ 22 - 1. Airborne Effluents....................................... 22 2.- Liquid Effluents....................................... 22 3. Solid Waste Shipments................................... 23 C. Environmental Surveillance................................... 25 1. Water Sampling .......................................25 2. Air Sampling.......................................... 25

3.. Outside Area TLD Network................................

26 D. UVAR Facility Health Physics Surveys............................ 27 - c 1. Radiation and Contamination Surveys.......................... 27 - ' 2... Airborne Radioactivity -.................................. 27

E.

Quality Assurance ".... -. a................................... 27 : F. L S u mmary..... '......................................... 29 r J P T -v ( d e E

1 -ill Eagn TV. ' RESEARCH, EDUCATION AND SERVICE AC'TIVITIES................. 30 : I A; : Irradiation and Other Research Facilities Available.................... 30 - n. 'B Research Activities.......................................... 30 3 c C., Service Projects. '........................................... 31 D. Reactor Sharing Program..................................... 31 E. . Reactor Facility Supported Courses and Laboratories................... 33 ' - F. Degrees Granted by U.Va. in Nuclear Engineering.....................- 33 VIdFINANCES ...............................................34- 'A. Ex pe nd itu res............................................. 34 B. Income ..............................................34 .C. State Support / Research and Service Income........................ 34 s:, I '] k y4 l

k 1997 ANNUAL REPORT ?> University;of Virginia Reactor Facility 1 I. INTRODUCTION - A. 3ametnr Facility Renortino Rannirements 1. Rannrtin! eriod P a This report on Reactor Facility activities during 1997 covers the period January 1, 1997 through December 31,1997. 2. Raele for Renorting - An annual report of reactor operations is required by the UVAR Technical Specifications, Section 6.7.2. Additionally, it is the desire of the Facility management to document and publicize the most important results derived from reactor operations. . B. Raaetnr Facility Descrintion The Reactor Facility is located on the grounds of the University of Virginia (UVA) at - Charlottesville, Virginia and is operated by the Department of Mechanical, Aerospace ' and Nuclear Engineering. De Facility houses the two megawatt University of Virginia Reactor (UVAR), a pool type research reactor, and the Cooperatively Assembled . Virginia low Intensity Educational Reactor (CAVALIER), a 100 watt training reactor,

which is now shut down and awaiting decommissioning. De Facility also has a 2,000 curie cobalt-60 gamma irradiation facility, a hot cell facility with remote manipulators, several radiochemistry laboratories with fume hoods, radiation detectors, counters and.

laboratory counting equipment, computerized data acquisition-analysis systems, and machine and electronics shops. 1. 2 MW UVAR ' De UVAR is a light water cooled, moderated and shielded type reactor that first went into operation at a licensed power level of one megawatt in June 1960, under license No. R-66. In 1971, the authorized power level was increased to two - megawatts. In September 1982 the operating license for the UVAR was extended for 20 years. De UVAR was converted to low enriched uranium (LEU) fuel

j

.during 1994.' Figure 1 shows a layout of the reactor and the various experimental-facilities associated with the UVAR.. ' J 14

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l h N 4 Figure 1. UVAR Experimental Facilities {. r-6 -Lu__.L___.._._ ___.m._E_______._ m .J___ -~ -.-

3 2. 100 W CAVA11ER f - The CAVALIER first went into operation in October 1974, under license R-123, at a licensed maximum power of 100 watts. The reactor was built to accommodate ( reactor operator training and perform experiments for undergraduate laboratory courses. The operating license was renewed in May 1985, for a period of 20 years. Figure 2 shows a layout of this reactor and its control room. A dismantlement plan [ was submitted in November,1987 to the U.S. Nuclear Regulatory Commission (NRC).' The NRC requested a decommissioning plan which was submitted early in 1990. An order to decommission was issued by the NRC on February 3,1992. f The reactor will be decommissioned in the near future. 3. Past Ooerating History a. UVAR The UVAR operating history is shown in Table 1. TMG 1 Operating History of University of Virginia Reactor Year (s) Megawatt-hours Hours Operated j f 1960-1970 3,960 4,500 1971-1975 1,654 1,800 1976-1978 1,769 1,480 { 1979 1980 9,036 5,627 1981 4,988 3,568 1982 5,507 3,024 1983 6,079 3,556 1984 5,687 3,166 1985 927 718 1986 1,330 891 f 1987 1,220 801 1988 910 621 1989 1,378 869 1990 1,837 1,087 1991 2,360 1,365 1992 2,428 1,450 .J 1993 2,663 1,533 1994 1,594 1,016 1995 1,703 1,079 i 1996 1,741 1,083 f-1997 1.954 1.230 t {- During the yer.rs 1979 through 1984, the UVAR was operated approximately 110 hours per week to irradiate metal specimens for radiation damage studies on pressure vessel steels. Since that time, the reactor has operated on a variable schedule up to about 40 hours per week. The UVAR first operated at full power with LEU fuel on May 12,1994.

a [.- 4 [ ~ ~ ' ' ~ ,r MICFJJIICE, ^ t ECUIF.wINT ECCM l [ T MAGITT SHCP_ { t STATP.S 70 XC22.UI!G [1 CPI?ATIlic AF.IA CCliCPIII SEIID ( ' ' a' h *. 'A N J e 1, FIACICR HOIE?ATCA [i PIT '4l ]83 TA2iX . -s L I i i Plas Viev et CAVA1.IEA Operating Area 1 [. CC!iCPITI SEII.L3 .r <k'.4 6.8] ^ 4 j CECWD TIDOR mu, 4e 3a 1,8, 7 Cg., MODEPATCR ,* ^ *.*N l, l'. IW' a '.,7 j a L., s,8 s' 11 ,e ' L DEIO!lIIIR IARII ..a 4 s gag 73 TILL i 6 PIACICR T2u. a m CCPI

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5 L b. CAVALIER The CAVALIER operating history ir shown in Table 2. ~ TABLE 2 [ Operating History of CAVALIER Year (s) Watt-hours Hours Operated 1974 1980 2,128 758 1981 1985 1,278 388 1986 147 37 1987 28 29 1988-present shutdown shutdown b The CAVALIER was used primarily for reactor operator training and undergraduate lab experiments, although it has not been operated over the past (_ nine years. The last date of operation was August 4,1987. The CAVALIER fuel and start-up source were unloaded on March 3,1988. A decommissioning plan was submitted to the NRC in January,1990. An l h order to decommission was issued by the NRC on February 3,1992. j Decommissioning should be completed in the near future. (- 4. Summarv of 1998 Reactor Utilization a. UVAR l During 1998, the UVAR was operated for 1,230 hours and a total integrated j power of 1,954 Megawatt-hours. The following projects were performed l (- utilizing the UVAR: 312 neut 9 activation analysis (NAA) samples were run in the {- pneumati. . bit systems (total activation time: 84 hours) 7 Irradiation ;cles of 100 hours each were completed in the mineral { irradiation facili. / (MIF). 131 containers or specimens were irradiated in the canister irradiation facility (CIF) for a total irradiation time of 698 hours. {- there were 176 hours of radiography completed using the 8" neutron beam port and 52 hours of counting experiments using the two one-half inch neutron beams of the southeast neutron beam port facility. l [ Student Laboratory Experiments Reactor Operator Training { [

6 5. Snecial Facilities b ' The following facilities are operated in connection with the UVAR: [ Two neutron beam ports, of eight-inch diameter entrance, stepped to 10 inches at the exit, are available. One beam port is currently dedicated to neutron radiography. .Two access ports (6 ft x 4 ft). One port is currently configured for a high energy photon beam, and the other port for a neutron beam. Hydraulic rabbit, for activation analysis, permitting samples with less &aii 0.9 inch diameter and 6 inch length (not used in 1997). Two pneumatic rabbit ied!! ties, for activation analysis and source production, permitting sample dhmeters of one inch and length not exceeding 2.3 inches. One facility is for irradiation with thermal neutrons and the other is cadmium lined for the use of epithermal [ neutrons. Solid gel irradiator for electrophoresis (not used in 1997). f Epithermal neutron mineral irradiation facility. ( A rotating irradiation facility used to equalize neutron fluence during irradiation of a large number of specimens (not used in 1997). [. Epithermal neutron irradiation facilities with heaters for sample temperature control (not used it.1997). Cobalt-60 gamma irradiation facility with 2,000 curies, permitting underwater exposures at rates up to 80,000 Rads per hour. Depleted uranium suberitical facility (not used in 1997). Small hot cell, (10 ft x 6 ft x 12.5 ft high) with remote manipulators, ( currently housing equipment for X-ray radiography. Machine and electronic shops. Several radiochemistry labs with fume hoods, counters and standard lab equipment. . IAw-background counting room with shielded, solid state germanium and silicon detectors and computerized data acquisition / analysis system. f

7 7 ' C. Ranetnr Staff Orennhatton 7 1.' " Onerations Staff ' A NRC approved Reactor Facility organization chan is shown in Figure 3. ~ Personnel on the reactor staff as of the end of 1997 were: R.U. Mulder L. Reactor Director P.E. Benneche. Reactor Supervisor (SRO) B. Hosticka. Research Scientist (SRO). C.A. Bly..... Senior Reactor Operator (SRO) M.J. Cook.... Part-time Student Assistant M.J. Crawford. Electronic Shop Supervisor ~ J.S. Baber...- Machine Shop Supervisor V.S. Romas.. Reactor Facility Secretary L.R. Dorne... Office Services Assistant 2. Henith Phynlen Staff at the Facilitv D.P. Steva.... Reactor Health Physicist D.A. Moody... Radiation Safety Technician ne Health Physicist is assisted by students employed by the Reactor Facility. Other . health physicists and technicians are on call through the Office of Environmental Health and Safety. h L 3. Remetnr Safety Committam ( :. He Reactor Safety Committee was composed of the following individuals (as of the I end of 1997): Ii W.R. Johnson.. Professor Emeritus, Nuclear Engineering (Chair) R. A.~ Rydin... Associate Professor, Nuclear Engineering L J.S. Brenizer.. Associate Professor, Nuclear Engineering G.T. Gillies... Research Professor, Mechanical & Biomedical Eng. R.U. Mulder... Reactor Director & Assoc. Professor, Nuclear Eng. R.G. Piccolo... University Radiation Safety Officer - D.P. Steva.... Radiation Safety Specialist,- - UVA Office of Environmental Health & Safety j, i. r Pj.,- 9 .~

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II. REACTOR OPERATIONS b "A." bVAR " " ~< "k- ~ ~ " " ' ~ ~ 1. Core Confieuratinns ' A typical UVAR core configuration is shown in Figure 4. De reactor employs-three boron-stainless steel safety rods and one stainless steel regulating rod for fine power control. De fuel elements are of the V.aterials Test Reactor (MTR) flat plate-type elements, utilizing U Si. De fuel is approximately 19.7% enriched in 3 2 the U-235 isotope. The fully loaded elements have 22 fuel plates per element, with (

an initial. loading of approximately 275 grams of U-235 per element. -ne control rod elements and partial fuel elements have 11 fueled plates with an initial loading l"

- of approximately 137 grams U-235 per element. A plan view of these elements is - shown in Figure 5. '2. i Standard OnerADrocedures (SOP) l During the year, changes were made to Chapter 10, Radiation Protection, of the SOP's. The Reactor Safety Committee reviewed and approved these changes. i o b"' - 3. Surveillance Requirements ( i# The following surveillance items were corrpleted during the year as required by Section 4.0 of the Techni.:al Specificatlans: a. Rod Drop Tests rjad Visual Insnection J Rod drop times are measured at least semi-annually, or whenever rods are moved or maintenance is performed. Magnet release time should be less than 50 milliseconds and free drop time less than 700 milliseconds. - Rods are visually inspected at least annually for physical integrity. r Rod drop times were measured on the UVAR and are shown in Table 3. L I' h:-. V r 'js h ~ u..

L E-10 L UNIVERSITY OF VIRGINIA REACTOR CORE LOADING DIAGRAM - 2.783 $ (Base) . CORE LOADING;_ ~ 95-3 SHUTDOWN MARGIN. 'DATE 7-3-97 EXCESS REACTIVITY + 3.974 $ (Base) ' U-235 4.502a EXPERIMENTWORTH 0.83 $ [ F-Normal Fuel Element P-Grid Plate Plug PF-Partial Fuel Element THERMAL RABBIT-Thermal Pneumatic Rabbit F-CR Control Rod Fuel Element EPI-RABBIT-Epithermal Pneumatic Rabbit { G-Graphite Element SOURCE G-Graphite Source Element F-REG -Control Rod Fuel Element with Regulating Rod Rod Worths

  1. 1 - 3.882$
  2. 2 - 3.731 $'
  3. 3 - 3.026$

Rea - 0.468$ MINERALIRRADIATioN FACluTY(MIF) MIF LEAD SHIELD F l F F F-REG F F G VS015 VS000 VC001 ' VS013 VS004 P P r l-11 12 13 14 15 16 17 18 F F-CR1 PF F F G VS006 VC002 VP001 VS007 VS008 P P [ 21 22 23 24 25 26 27 28 F F F F-CR2 F [ G VS001 VS010 VS002 VC003 VS012 P P L 31 32 33 34 35 38 37 38 l F F F-CR3 F F f G VS014 VS003 VC004 VS005 VS011 P P i L.- 41 42 43 44 45 de 47 48 i SOURCE G G G G G G P P 51 52 53 54 55 56 57 58 EPI-l G G G RABBrr G G G G l ~~ 61 62 63 64 65 66 67 68 I THERMAL G G RABBrf G G P G G 7J 72 73 74 75 76 77 78 [: G G G G G G G G 81 82 83 84 85 86 87 88 [ Figure 4 D

E a 11 I L M LEU FUEL ELEMENTS

.(Dimensions in inches)

FL l F ' 3.001 2.9 91 t.. a {~ m.040 i l' [ i 3.140 $T M ARD l t ,1 n L 1.570 I. o o 'u c 7. _.099 COOLANT GAP 21 PLACES .085 i j u. 3.0 01 c: 2.991 i n l s 1 s s ?, E-u- ,s 3.140 \\ s r N \\ b \\ N COhTROL~% \\ \\ h \\ \\ s N {.. - N J' 1.570 (L e o COOLANT GAP 11 PLACES [:- [::< Figure 5 b.;

L i 12 TABLE 3 Measured Control Rod Drop Times on UVAR Rod Magnet Rod Magnet Free Total Number Current Position Release Drop. Drop r [ (m-amps) (inches) Time Time Time (avec) (msec) (msec) 416-97 Semi-annual Surveillance r i 1 175 26 22.4 477.2 500.2 2 175 26 31.6 464.6 495.6 3 75 26 46.8 463.6 510.6 i 10-28-97 Semi-annual Surveillance 1 175 26 18.8 497.8 516.6 2 175 26 37.4 464.0 501.4 3 75 26 i 33.8 466.6 500.4 f L The rod drop times continue to be within the limits required by the Technical Specifications (700 msee free drop and 50 msee magnet release). The UVAR control rods were visually inspected on 4-16-97. The following is abstracted from the surveillance files: L Rod #1 - Inspected rod under water. No cracks or significant rub marks were observed. A 0.90 inch gauge easily passed over the rod. 1 Rod #2 - Inspected rod under water. No cracks or significant rub marks were observed. Red dot is again noted on side of rod. Surface r roughness noted on top ofland near the bottom. A 0.95 inch gauge t easily passed over the rod. r [ Rod #3 - Inspected rod under water. No cracks or significant rub marks were observed. 'Ihere was considerable redish - brown discoloration at the top of the rod near the transition piece. The same discoloration was f noted all over the rod, in a spotty fashion. A 0.95 inch gauge easily j passed over the rod. l ( All of the rods appear essentially the same as in previous inspections. b. Tests and Calibrations Data on these tests and calibrations are on file at the Facility. '1) Monthly l Operational checks of the ventilation duct, personnel door, truck door and emergency exit cover were performed as required. h

( 13

2) l $gmilAnnually r.

w: E o -15 " A visual inspection of gaskets on pmonnel door, ventilation duct and -~ - truck door was completed. . Calibration checks of source range channel, linear power channel, core gamma monitor, bridge radiation monitor, reactor face monitor, duct e L argon monitor, constant air monitor, pool level monitors, pool temperature monitor, core differential temperature monitor, and primary flow instrument were done. [ 3) Annually L Be emergency cooling system was tested on December 1,1997. The results are as follows: S.E. Tank S.W. Tank (ent/ min) (ent/ min) minimum required flow 11.0 11.5 11-04-96 actual flow 12.2 12.4 last five year range 11.9-12.5 12.1-12.5 No pattern was observed in the variation of the test results for the last j five years. [. 4) Daily Checklist L The daily checklist, which is completed when the reactor is to be operated, provides for checks on all the significant automatic shutdown systems associated with the reactor. -l 5) Rancenr Pool Water Quality De Technical Specifications require that the pH and conductivity of the pool water be measured at least once every two weeks, These l measurements were actually made on a daily basis when the reactor was operating and at least once each week. - Dese measurements have c indicated that the water quality was maintained well within the Technical - h - Specification limits of pH between 5.0 and 7.5.with conductivity < 5

micromhos/cm.

' 6)

Core Cnnfleurstinn Chaneen De UVAR core configuration was modified slightly in early July 1997.

+ ' . Two graphite elements were substituted in the place of grid plate plugs which had been in locations' adjacent to the core. This was done to slightly increase the reactivity of the core without either adding or ' moving fuel., Dis change was made just prior to a required control rod " ;_f m _=

r. L (- 14. L,. calibration. t[' t-M jirs; a"ey 7)f ~ Communibwinn Chehka._ t [ 'Ihe security system and emergency communications with the University. Police and Fire Department were checked on a weekly basis throughout - the. year. These checks confirmed the availability of systems and. l. communication equipment. Maintenance

4..

l The maintenance performed on the UVAR systems during the calendar year 1997 is l shown in Table 4. No significant trends were noted in the maintenance. j. 1-l~ l i l l t l 1 i r r; ..(- .i

15 TABLE 4 Reactor System Maintenance Performed in 1997 - Date - System Problem Corrective Action 01-09-97 Regulating rod rod will not drive in either added BNC connector to replace direction RC type connector 0128-97 L Linear power / servo regulating rod moves in ajumpy troubleshoot only; found no control fashion when in automatic control definitive or correctable problems 02-17-97 Linear / N-16 recorder recorder response not tight enough interchanged amplifier boards, 02-18-97 for smooth operation of the reg. cleaned and lubed drive chain, 02-19-97 rod when in automatic control cleaned slide wires and replaced the back slide wire which was found to be cracked 03-03-97 Linear / N-16 recorder will not track properly to allow replaced capacitors on both operation in automatic control amplifier boards 03 10-97 Core Gamma Monitor new picoammeter needed testing new instrument tested OK l 03-10-97 Nitrogen-16 Detector new picoammeter needed testing new instrument tested OK 04-09-97 Demineralizer room door open intrusion alarm not regiaced with spare parts intrusion alarm working 05-20-97 Epithermal rabbit minor leakage of pool water into cut 1/2" off of gas inlet tube and irradiation facility facility through bottom gas inlet replaced swages.md nuts tube (pitting corrosion) l 05-23-97 Secondary Instrument bad DC power supply which replace with new AC power Console powers the " pump-on" lamps __ supply 1 06-10-97 Portable pool water not operating properly, batteries cleaned battery compartment and conductivity meter found to be leaking replaced batteries 07-08-97 Power Range #1 performance of detector had removed about two feet of wire deteriorated somewhat; wires near and replaced connectors; built detector found to be in bad shape new detector holder 07-16-97 Security System tree down across phone lines transferred system function to a severs the connection with the working line and tested system r UVA Police 08-18-97 Secondary Cooling yearly inspection and cleaning, six six leaking tubes were plugged System, Heat Exchanger tubes found to be leaking slightly j 26-97 Core differential pool delta temperature monitor will not found and repaired a crushed I water temperature monitor zero after several hours with wire primary pump running 09 15-97 Nitrogen-16 Detector operation questionable, instrument replaced cable in heat exchanger getting old room and reactor room to reduce electronic noise 11-25 97 Common alarm panel silence switch not working replaced silence switch 12 15-97 Common alarm panel reset button sometimes trips the replaced reset switch alarm 12-16-97 Regulating rod rod will only drive in, not out, cleaned and adjusted cycle of when in automatic control non-shorting convertor on servo amplifier 12-18-97 Regulating rod rod motion sluggish, sounds bad replaced bearings in motor gear when moving box g.. -...

L 16 r u 5. Unnlanned Shutdowns e " Ihe 17 unplanned shutdowns which occurred on the UVAR during the calendar, 4 + year 1997 are shown in Table 5. E TABLE 5 Unplanned Reactor Shutdowns in 1997 L Date Shutdown Mechanism 01-13-97 1 Scram - Operator trainee turned off pri. pump rather than cooling tower fan. 01-21-97 1 Scram - Intermediate range period; due to movement of neutron source. 03-06-97 1 Scram - Electronic noise; bridge radiation monitor. 04-24-97 1 Scram - Electronic noise; intermediate range period. 05-15-97 1 Scram - Momentary building power failure. p t 05-22-97 1 Scram - Power range; failure to throw range switch when going to high power. 06-05-97 1 Scram - Bridge radiation monitor; high radiation from sample in rabbit system. r 06-10-97 1 Scram - Bridge radiation monitor; samples out of container irradiation facility L moved too close to pool surface 06-10-97 1 Scram - Mineral irradiation facility gas pressure sensor; indicated low c-pressure; gauge very jumpy. L 06-13-97 1 Scram - Mineral irradiation facility gas pressure sensor; low pressure indication while flow was being adjusted 07 02-97 1 Scram - Intermediate range pedod; due to movement of neutron source. 7 L 07-11-97 1 Scram - Mineral irradiation facility gas hose came loose. 07-16-97 1 Scram - Mineral irradiation facility lead temperature; thermocouple connection on bridge bumped. 7 L 07-29-97 1 Scram - Momentary building power failure. 11-05-97 1 Scram - Momentary building power failure. 11-05-97 1 Scram - Power range #2; instrument welt allowed to go in too far while being r L adjusted. 12-17-97 1 Scram - Momentary building power failure. r L None of the unplanned shutdowns had " reactor safety significance". 6. Pool Water Make-un { During the year makeup water to the reactor pool averaged 72 gallons per day. { Much of this is due to evaporation while operating the UVAR at 2 Mw. l 7. Fuel Shinments [- a. Fresh Fuel [ No fresh fuel was received at the facility during 1997. b. Soent Fuel [. ~ No spent fuel was shipped from the facility during 1997. [: E

i 17 l l 8. Personnel Training and Instruction .,_~ j, :! y~ m: a. - Rencenr Facilits Staff '~ At the end of 1997 the staff had three senior reactor operators. All licensed operators participated in the Facility's operator requalification program, which was carried out during the year. The program consists of periodic lectures, participation in the daily operation of the Facility, performing checklists and j . start-ups of the reactor and a biennial written examination. l b. Summer Course for High School Tanchers - 1 During the month of June,1997,28 high school teachers from within the state of Virginia attended a one week special course at the Reactor Facility entitled-u " Science of Nuclear Energy and Radiation". De course consisted of formal j lectures, laboratory experiments with the UVAR reactor in the areas of sub- -l critical multiplication, basic radiation counting, and gamma-ray analysis. l During the week the teachers also visited the North Anna Nuclear Power l Station. 9. Ranctnr Tours During the calenda year 1997, the staff guided 32 groups on tours along with a number of individual tours of the Facility, for a total of 688 visitors. L-B. CAVAI IFR Reactor 1. Reactor Shut Down The reactor was completely and permanently unloaded during the first week of March,1988. A decommissioning order was issued by the NRC on February 3, 1992. De decommissioning should be completed in the near future. 'III. REGULATORY COMPLIANCE.

4. ' Rancenr Safety (_ommittee 1

1. Maating , During 1997, the Reactor Safety Committee met four times, on the following dates: . '. January 20,19971 September 11,1997 m ' February 25,1997 ' . September 29,1997 - De Technical Specifications require the committee to meet at least twice each year. t --/:_ m m r.ms ... -w. ...es .......1.

I 18 2. Audits L ..During the year sub committees of the Reactor Safety Committee performed two audits of the Facility. One audit of the reactor operations records is required every year and was completed on April 8,1997. The second audit that was done was of experimental procedures, QA/QC procedures and training. An audit in these areas is done every two years. 3. Annrovals l During the year, the Reactor Safety Committee approved a number of changes to Chapter 10, Radiation Protection, of the UVAR Standard Operating Procedures. { 4. 10 CFR 50.59 Reviews Bere was one 10CFR50.59 analysis perfoimed during the year related to the E design, installation and use of a new experimental facility, the Small Animal Neutron Irradiator Tube. This was reviewed by the Reactor Safety Committee: l B. Inspections During 1997 the Facility had two NRC compliance inspections, at the following times and in the areas of: April 14-17,1997

  1. 50-62/97-01 Reactor operations y

i November 11-13,1997

  1. 50-62/97-201 Radiation protection
  2. 50-396/97-201 L

nere were no violations or deviations cited as a result of these inspections. C. Licensing Action

L 1.

A new security plan was submitted to the NRC for approval on February 22,1996. As of this date no action has been taken on this request. D. Emergency Prenaredness 1. On April 11,1997 at 2:03pm a practice evacuation was initiated by activating the criticality alarm system located at the fuel storage area. De alarm was initiated at I the CAVALIER reactor room. All personnel within the building at the time evacuated within three minutes. Ten individuals were accounted for. He staff brought with them portable radiation instruments, pocket dosimeters, portable l_ radios, a cellular phone, personnel dosimetry racks, the visitors log, the reactor log, and two copies of the EPIP's. A staff member in the UVAR reactor room at the time of the alarm reported difficulty hearing the alarm. An additional horn will l be added to that area to improve the audibility of alarms. The drill was terminated at 2:10pm. I

19 { 2. On December 18,1997, an instructor from the American Red Cross conducted a [- recertification course in CPR at the facility.- Four staff members were recertified in CPR. F 3. On January 13,1998, the annual emergency drill for the calender year 1997 was initiated at the facility. This drill is normally held in November but was completed { a little later this year due to some planning difficulties. This year's drill was of the " minor" nature, since major drills involving the majority of the off-site support organizations are only required every other year. The scenario involved a staff [ member working near the edge of the reactor pool, losing his balance and falling into the pc 1, thereby injuring himself slightly and becoming contaminated with reactor pocl water. The reactor was not operating (nor was it simulated to have { been operating) at the time of the " incident". 'Ihus, the actions being tested in this drill were: staff notification, staff initial actions to identify the nature of the accident, contamination control and decontamination procedures, first aid, required [ off-site notifications, appropriate use the Emergency Plan Implementing Procedures and the use of assistance by off-site agencies (in this case, the UVA Office of Environmental Health and Safety). A complete description of the drill scenario, [ the response and the after drill critique was presented to the Reactor Safety Committee in a memorandum dated January 21,1998. b [ [ c: [ [ [ [: [; ) [ ,x

[ 20 g o IV. HEALTH PHYSICS b A. Personnel Dosimetry 1. Esitof Exoosure Data For 1997 During 1997, there were 688 visitors who toured or assisted with work at the Reactor Facility. Of these visitors,585 were visitors in tour groups. The highest [- dose received in any one visit was 2 mrem. Most visitors received no measurable dose. 2. Reactor Facility Personnel Dosimetry Dats,1 "27. a. Monthlv Whole Body Badge Data { Radiation doses received by Reactor Facility personnel were measured using [- Landauer personnel dosimeters. Film badge dosimeters measured exposure from beta, X, gamma and thermal neutron radiation. All personnel working with the neutron beamports at the Facility were issued neutron dosimeters in { addition to their whole body film badges. The neutron dosimeters used were Landauer Neutrak ER badges that allowed detection of an extended range of neutron energies. All dosimeters were changed out on a monthly basis. The dose distribution for personnel badged at the Reactor Facility during the period January 1,1997 through December 31,1997 is shown in Table 6. TABLE 6 1997 Personnel Radiation Doses Received at Reactor Facility Meast. red Accumulated Number ofIndividuals in Deep Dose Equivalent * (mrem) Dose Range Less than 10 (M) 43 [- 10 - 20 13 21 - 30 2 l 31 - 40 1 (;; 41 - 50 n 51 - 100 1 l 101 - 150 0 i {- 151 - 500 3 Greater than 500 0 Number of badged personnel: 63 persons h Collective dose for this group: 1.03 rem

  • Deep dose equivalent as measured by "whole body" film badge

[, dosimeters. These dosimeters have a detection minimum of 10 mrem for gamma, X-rays and thermal neutrons and 40 mrem for energetic beta particles. t =

21 The individual who received the highest annual deep dose equivalent (330 mrem), was a Reactor Facility staff member routinely involved in unloading the mineral irradiation facility and . preparing Iridium-192 for shipment. During 1997, no doses exceeded the UVA ALARA Investigational Level 1 of 125 mrem per quarter. b. Neutron Exnosures Thirteen Facility personnel were issued Neutrak ER neutron badges in 1997. The neutron dose distribution for this group is shown in Table 7. TABLE 7 1997 Personnel Neutron Doses at the Reactor Facility Measured Accumulated Deep Number ofIndividuals in Dose Dose Equivalent (mrem) Range Less than 20 (M) 13 20 40 1 Greater than 40 0 NOTE: These dosimeters have a minimum reportmg dose of 20 mrem. c. Extremity Exnosures During 1997,18 Facility personnel were issued TLD ring badges in addition to their whole body badges. The following is a summary of the extremity j doses received by Reactor Facility personnel who wore ring badges during the period January 1,1997 through December 31,1997. TABLE 8 1997 Personnel Extremity Doses at the Reactor Facili:y Measured Accumulated Extremity Number of Individuals in Dose Dose (mrem) Range Less than 30 8 30 - 500 8 501 - 1250 1 1251-5000 1 Greac than 5000 0 NOTE: These dosimeters have a minimum reporting dose of 30 mrem for X and gamma-rays and 40 mrem for energetic beta particles. The individual who received the highest extremity dose (1530 mrem), was a Reactor Facility staff member routinely involved in unicading the mineral irradiation facility and preparing Iridium-192 for shipment. During 1997 no facility personnel doses (extremity) exceeded the UVA ALARA Investigational Ixvel 1 of 1250 mrem per quarter.

22 d. Direct-reading Dosimeter Exoosures Direct-reading dosimeters (in addition to whole body film badges) are worn by ~ nUVAR personnel when they are handling irradiated material that has a calculated or measured exposure rate of greater than 100 mR per hour, measured at one foot from the source. If the exposure totals more than 5 mR in one day, the exposure is recorded in an exposure log kept in the control room. This information is helpful in assessing the amount of exposure received during specific operations. The total of all exposures recorded in the log book during 1997 was 44.9 mR. The highest individual exposure was 24.0 mR. This exposure was received by a reactor facility staff member handling irradiated material. l B. Effluents Released During 1997 1. Airborne Effluents l Argon-41 gaseous release concentrations are calculated using a methodology l described in a June 1977 memorandum entitled: " Memo to Senior Operators - Argon 41 production in UVAR." The Argon-41 activity is calculated from a known amount of activity release 6 into the reactor room during a leak rate test of the room and readings obtained on the room argon monitor. These readings were then correlated to the normal readings on the argon monitor during 2 MW operation. Using this method, and the known amount of time the reactor was at power during l 1997 (1954.28 MW-hours), the calculated maximum activity of Ar-41 released was 2.81 Curies. Calculations were performed to determine compliance with 10 CFR 61, Subpart I, entitled: National Emissions Standards For Radioactive Emissions From Facilities Licensed by the NRC and Federal Facilities Not Operated by the DOE. The s calculated Total Effective Dose Equivalent (using the USEPA's COMPLY Code: V1.5d), from Ar-41 release was 3.1 x 10 2 mrem. On the basis of this calculation and the totals for the University as a whole, the University is exempt from reparting to the EPA on the annual emissions of radioactive material in 1997. 4 2. Liquid Effluenti 4 Liquid radioactive waste generated at the UVAR is disposed of by one of two means. Liquid waste generated in the student laboratories is poured into approved containers that are collected and disposed of by the Environmental Health and Safety Office. Other liquid wastes generated by the UVAR operation are released to the sanitary sewer in accordance with 10 CFR 20 release requirements. Regeneration of the UVAR demineralizer system is the major source of radioactivity in liquid released from the Facility. Liquid waste from regeneration is collected in three 2,250 gallon tanks on the ground floor of the Facility. The liquid waste collected in these tanks is released to the sanitary sewer in accordance with 10 CFR 20 requirements.

l 23 1 In unusual situations, (e.g. draining of the reactor pool, pool leaks, sink drain i disposal), an onsite pond may receive radicactive liquid discharges from the facility. The rnajor sources of water in the pond are surface runoff and a creek that . flows into it from the west end. Water is periodically released from the pond in a controlled manner via a spillway. A small amount of pond water routinely leaks through the pond spillway to the release standpipe at an average rate of 0.5 gallons per minute. As this is considered release of pond water, the volume and activity released via this pathway was included in the 1997 liquid release totals. During 1997 there were 23 releases of pond water and 3 releases to the sanitary sewer (see Table 9). Prior to, and during all liquid releases, water samples are collected and analyzed for radioactivity content. The average concentration of radioactive material (as measured by gross beta particle activity analysis) released in effluent from the UVAR pond was 5.0 x 104 Ci/ml. This concentration was 17% of the UVAR administrative release limit anc was less than the average concentration of radioactive material measured in the water upstream of the pond (7.0 x 104 Ci/ml). The average tritium concentration in effluent released from the pond was 1.2 x 104 Ci/ml. This concentration was 0.12% of the applicable Effluent Concentration (EC) limit (1.0 x 10 3 Ci/ml). The total volume ofliquid released off site, from the pond, in 1997 was 25,000,000 liters (6,654,000 l gallons).The total activity (excluding tritium activity) in this volume was 123 Ci. ( This activity was primarily from naturally occurring radionuclides contributed to the pond from the runoff in the feeder creek mentioned above. The total tritium activity released in pond water was 17,600 Ci. l The total volume of waste water released to the sanitary sewer was 54,300 liters. l The total tritium activity released to the sanitary sewer was 5,551 pCi. The total of i l all other radionuclides released to the sewer was 298 Ci. All radionuclides released to the sewer were in concentration that were less than 1.0% of their I individual EC limits. I-I 3. Solid Waste Shioments j I l In 1997, twenty four (24) cubic feet of low level radioactive waste was transferred from the reactor to EHS for disposal.. l

1 h '24 f TABLE 9 .. Pond Release Sample Results ^~ ^ ' Release l Avg. Gross Beta Release Avg. Gross Beta No. Activity No. Activity (excluding Tritium) (excluding Tritium) (x104 Ci/ml i2 s.d.) (xl&8 C1/ml t2 s.d.) l 1 0.3 i 0.1 14 0.6 t 0.1 [ 2 0.1 0.2 15 0.3 0.2 } 3 0.3 i 0.2 16 0.6 0.4 i 4 0.3 i 0.1 17 0.5 0.1 j 5 0.6 0.8 18 0.5 i 0.2 6 0.5 i 0.2 19 0.6 i 0.2 7 0.4 0.4 20 0.5 i 0.4 8 0.5 i 0.01 21 0.4 0.6 9 0.4 i 0.2 22 0.5 0.1 10 0.5 i 0.1 23 1.2 2.6 11 0.6 0.4 12 0.5 0.2 13 0.3 i 0.1

  • 3 samples are collected during the release. Number reported is the average (or mean) of the 3 samples and 2 s.d. of this mean A priori LLD: 0.3 x 10' pCi/ml

~ 1 l I TABLE 9a 1997 Sewer Release Data Nuclide Release #1 Release #2 Release #3 l l. % of Release % of Release % of Release Limit

  • Limit Limit H-3 1.13E-5 1.47E-3 1.84 E-3 f

Mn-54 3.01E-6 1.4BE-4 9.57E-5 f Co-60 1.31E-4 1.38E-3 1.05E-3 Cs-137 2.43E-2 2.6E-3 5.12E-4 Cs-134 ND ND 1.17E-4 ' Cr 51 ND 1.78E 5 1.0$E-5 Zn-65 ND-5.8E-4 3.8E-4 Sb-124 ND 6.09E-4 1.06E-3 Sb-125 ND 1.78E 5 3.4 E-5 Co-58 ND ND 6.94E-6 - ND - Not detected

  • Release Limit - 10CFR20 Appendix B, Table 3

I 25 C. Environmental Surveillance f-1. Water Samnling j Environmental water samples were collected on a monthly basis from the locations t indicated in Table 10. Gross beta particle activity analysis was performed on all water samples collected. The results of the analyses are provided in Table 10. The [. average gross beta particle activity measured at each location was less than the t UVAR Administrative Effluent Concentration Release Limit of 3 x 10-8 Ci/ml. TABLE 10 I Environmental Water Sampling Results 1 Gross Beta Particle Activity ( x 108 uCi/ml 2 sigma) l Meadow Creek near Barracks Road,1.8 mi. 1 [ northeast (2 samples i 1 Upstream of on-site Water filtration plant collected short distance l pond 0.26 mi. southeast apart on creek, results are averaged) l January 0.5 i 0.2 0.1 i 0.1 0.5 i 0.1 February 0.6 i 0.2 0.3 i 0.1 1.0 i 0.02 March 0.4 0.2 0.1 i 0.1 0.3 0.1 April 0.7 i 0.2 0.1 i 0.1 0.4 t 0.01 i ] May 1.0 i 0.2 0.1 0.1 0.4 i 0.01 June 0.5 i 0.2 0.0 i 0.1 0.3 i 0.1 1 1 July 0.9 0.2 0.3 i 0.1 0.6 0.1 J August 1.010.2* 0.2 0.1 0.7 0.1 September 0.4 i 0.2 0.04 i 0.1 0.5 t 0.02 October 0.7 i 0.2 0.2 0.1 0.8 0.1 November 0.4 1 0.2 0.5 0.2 0.4 0.1 December 0.9 i 0.2 0.1 i 0.2 1.1 i 0.03 f Avg 12 s.d. 0.7 i 0.5 0.2 i 0.1 0.6 i 0.5

  • High sediment content A priori LLD: 0.3 x 108uCi/ml l

2. Air Samnling Environmental air samples were collected on a monthly basis at the following location : A-1 Roof of reactor building A-2 Indicator - approximately 0.13 mi. E of UVAR A-3 Control - approximately 3.1 m!. NW of UVAR Fixed sampling locations are utilized to collect air samples at locations A-2 and A-3. Sampling time for these off-site samples is approximately 96 hours. Air

l 26 - samples were collected at location A-1 using a portable air sampler that was run for approximately two hours. All air samples collected at these locations were particulate air samples and were analyzed for gross beta particle activity. Results. h . are provided in Table 11. The airborne radioactivity detected wes primarily due to naturally occurring radon and thoron daughters. The average activity measured at each location was less than the Effluent Concentration Limit of 1 x 10'" rCi/ml. TABLEI1 Environmental Air Sampling Results Gross Beta Particle Activity in Air Particulates ( x 10" uCi/ml i 2 sigma) Roof of UVAR 0.13 miles east 3.1 miles northwest Facility of UVAR Facility of UVAR Facihty January 2.2 i 0.5 0.6 i 0.05 0.8 0.06 l February 2.9 i 0.5 1.0 i 0.1 1.4 i 0.1 March 2.9 i 0.5 No Data

  • 0.7 i 0.04 April 2.8 t.8 0.9 i 0.04 1.4 i 0.05 i

May 4.5 i 0.6 0.5 0.03 0.7 i 0.04 i June 5.4 0.7 1.5 i 0.1 1.9 i 0.1 July 5.8 i 1.1 0.6 i 0.05 0.7 i 0.05 l l August 8.9 i 0.9 1.8 i 0.1 2.7 i 0.1 September 6.7 i 0.8 No Data

  • 3.3 0.1 October 6.3 i 0.7 2.6 i 0.1 12.0 i 3.5 a l

November 6.5 i 0.9 0.7 t 0.04 2.7 0.8 Dec mber 2.9 i 0.7 2.4 i 0.1 4.0 0.8 Avg.i 2 s.d 4.8 i 4.2 1.3 i 1.5 1.8 2.3 Sampler malfunction z. I hour sample only, unusually low background count, outlier not included in average l l Effluent Concentration (EC) Limit: 1.0 x 10" pCi Roof sampler a priori LLD: 2.8 x 10" pCi/mi Environmental samplers apriori LLD: 6.2 x 10" pCi/ml 3. Outside Area TLD Network . TLD's are mounted at 8 fixed field sites in the vicinity of the UVAR. All of the sites are outside the UVAR facility but within the area surrounding the facility that is bounded by the exclusion fence. The dosimeters are changed out and read on a . quarterly basis. Table 12 shows the doses recorded by these dosimeters. All doses measured were less than the annual dose limit of 100 mrem.

27 TABLE 12 1997 Environmental Surveillance - Outside Area TLD Network Deep Dose Equivalent (mrem) For Periods Shown Below location 1" 2nd 3rd 4th Annual Annual Quarter Quarter Quaner Quaner Total Net

  • 280 20 40 10 M

70 40 281 20 40 20 20 100 70 282 40 50 10 10 110 80 283 30 40 20 M 90 60 284 30 40 10 M 80 50 285 M 40 M M 40 10 286 10 40 10 M 60 30 287 M 40 M M 40 10 Control M 30 M M 30 Control Control M 30 M M 30 Control M = min. detection limits: 10 mrem for gamma and x-rays,40 mrem for energetic betas.

  • Annual Net = Annual Total-Control Annual Total D.

UVAR Facility Health Physics Surveys 1. Radiation and Contamination Surveys Daily, weekly and monthly surveys are performed throughout the Facility to monitor radiation and contamination levels. All required area radiation and contamination surveys were performed during 1997. The levels of contamination detected in the Facility during 1997 were generally 2 very low (typically less than 50 dpm/100 cm ). In keeping with the ALARA policy, most areas are decontaminated if found to have greater than 50 dpm/100 2 cm. No increase in background or systems related radiation levels was detected by the routine health physics surveys 2. Airborne Radioactivity Airborne particulate samples are collected in the reactor room as part of the weekly survey of the Reactor Facility. The average concentration of radioactive material detected in reactor room air (as measured by gross beta particle activity analysis of the particulate samples) was 2.9 x 10 '2 Ci/ml. The airborne radioactivity detected was primarily due to radon and thoron daughters. None of the measured concentrations exceeded the applicable Derived Air Concentration (DAC) of 3.0 x 10-" pCi/ml. E. Ouality Assurance The UVAR Facility participates in the U.S. Environmental Protection Agency (EPA) Laboratory Intercomparison Studies Program as part of its quality control program for

b 28 radiation measurement of air and water samples. The UVAR Facility participates in the following studies: Gamma In Water on a triennial basis Gross Alpha, Gross Beta in Water on a triennial basis [ Tritium in Water on a semiannual basis Three independent determinations for each radionuclide included in a study are made and [ analysis results are reported to the EPA. A tabulation of all results reported by all participating laboratories is generated by the EPA. This tabulation report contains [ analytical precision values that are used as a basis for judging a laboratory's performance. Table 13 contains the results of the UVAR's performance in the above mentioned studies. The normalized deviation of the mean from the known value is calculated from the deviation of the mean from the known value and the standard error of the mean values. { The deviation of the mean from the known value is calculated by subtracting the known value from the average of the laboratory's three results. The standard error of the mean is calculated by dividing the expected precision by the square root of 3 (the number of { results). The normalized deviation of the mean from the known value is calculated by dividing the deviation of the mean from the known value by the standard error of the - mean. All intercomparison results provided by UVA indicated very good analytical process precision. [ [ i ( [ [ ( ( w.x-__._...._____-.--__--__._.__

I 29 TABLE 13 Results of EPA Radioactivity Measurement Laboratory Inter-Comparison Program Date Study Known Value UVAR reported Normalized average value Deviation

  • 1-31-97 Gross al in 14.7 pCi/l 15.17 0.16 7 18-97 HO 15.1 pCi/l 16.73 0.57 2

10-31-97 48.9 pCi/l 50.03 0.39 3-07-97 H-3 in water 7,900 pCill 8,783 1.94 8-08-97 11,010 pCi/l 11,447 0.69 6-06-97 Gamma in water Co-60 27 pCi/l 27.0 0.00 Zn-65 75 pCi/l 75.3 0.07 Cs-134 10 pCi/1 9.3 -0.23 Cs 137 74 pCi/l 76.3 0.81 Ps 133 99 pCi/l 92.0 -1.21 11-07-97 Gamma in water Co-60 18 pCi/l 22.7 1.62 Zn-65100 pCi/l 101.3 0.23 Cs-134 22 pCill 19.3 -0.92 Cs-137 49 pCill 51.7 0.92 l Ba-133 25 pCi/l 25.7 0.23 NRP - No results reported by UVAR Facility If this value is between 2.00 and 3.00 the analytical process precision is in the warning zone; if it exceeds 3.00 it is outside of the control limits specified by the EPA. G. Summarv l During 1997, no State or Federal limit for exposure to personnel or the general public was exceeded. l l

30 V. .RESEARCH, EDUCATION AND SERVICE ACTIVITIES A. Irradiation and Other Research Facilities Available An overall description of the experimental facilities available at the UVAR is listed in section I.B.5. During 1997, one new facility was designed, constructed and put into use to neutron irradiate mice to study the efficacy of Boron Neutron Capture Therapy for the treatment of certain cancers. No substantial changes were made to any existing experimental facilities. B. Research Activities 1. A continuing program of research was pursued on behalf of the Philip Morris Company. This work was supervised by Dr. Jack Brenizer and conducted primarily by graduate students with Reactor Facility staff assistance. The major projects were neutron radiographic examinations of burning cigarenes, neutron activation analysis of various tobacco products and other substances used in the tobacco industry and the analysis of the distribution of smoke from a smoked cigarette through spiking of tobacco with radioactive isotopes. 2. Staff assistance was provided to a number of small projects utilizing a cobalt-60 irradiation facility. Several researchers at both UVA, other universities and some high schools provided a number of different kinds of samples to be irradiated for either sterilization or to attempt to create genetic mutations. 3. Several special radioactive sources were created and shipped to a researcher at the University of Alabama at Huntsville for use in a project sponsored by NASA. 4 Several uranium-235 foils were irradiated in the reactor to produce small quantities of fission products to be used to test counting equipment being assembled and tested for PSR Corporation which is working under a federal government contract. Several other sources for use in the calibration of detector set-ups were also produced. Comprehensive Test Ban Treaty Radiation Monitoring sponsored by PSR remained an ongoing project, involving radiation detector and spectrum analysis using irradiated materials. One staff member and one professor were involved in this project. 5. Eagle Picher, a manufacturer of commercial boron products had the Reactor Facility (a professor, staff and students were involved) perform neutron radiography and gaging on a large number of aluminum-boron plates as part of a quality assurance program. These plates are designed to be part of a nuclear power plant spent fuel storage containers. 6. Industrial Quality, Inc., SBIR Phase 11 for U.S. Navy. A major two year program to develop a new electronic neutron imaging system was ongoing. This work involved evaluation of numerous thermal and fast neutron scintillators as well as evaluation of a new CCD camera. One professor and one student were involved in this project.

31 7. Aerogel water vapor uptake was measured for a new project investigating the use of aerogels as collectors. This work, sponsored by PSR and DARPA, involved two professors and a staff scientist. T C. Service Projects 1. Iodine determination by epithermal neutron activation analysis (ENAA) was l performed on behalf of several sponsors, including Ross Laboratories, Woodson-Tenet Laboratories, Industrial Laboratories and the IAMS Company. The f substances analyzed were infant formula, liquid diet supplements and pet foods. L 2. The project involving the color enhancement of various gemstone grade minerals by I fast neutron irradiation was pursued by the reactor staff on behalf on several sponsors involved in the commercial gem trade. [ 3. The Protechnics International Company and its subsidiary Spectratec Services, which supply various radioactive sources to industry, had the Reactor Facility irradiate and ship to them about 50 canisters of a ceramic powder spiked with I iridium. This material is used by companies performing oil well drilling. The canisters were irradiated (for 25-35 hours) and shipped three at a time. L 4. A number of small radioactive sources were produced for use in graduate and j undergraduate nuclear engineering laboratories. ( 5. A UVA graduate chemistry class used NAA to determine the yield on synthesized transition element compounds. r 6. Co-60 sterilization was completed on a large number of micro-pipettes used for l manipulation and fenilization of human eggs prior to their implantation in a woman's uterus. This is a continuing project for a local company, Humagen - L Fertility Diagnostics, Inc. that manufactures and distributes these pipettes. j i r D. Reactor Sharing Program I The Department of Energy has for the past sixteen years funded a program at the University entitled Reactor Sharing. The purpose of this program is to make available the UVAR facilities to faculty and students at universities and other educational institutions which do not have nuclear science facilities. Over the years, hundreds of [ students and dozens of professors have used this arrangement to enhance both their educational and research opportunities. This past year a number of tours, laboratories and research projects were conducted under this program. l l [- [ L --- --- ---

32 The following is a list of both the directly and indirectly funded activities completed in 1997. School tours: Twenty-one tours from high schools, middle schools and elementary schools involving 495 students and teachers. College tours: One tour from colleges involving 8 students and instructors. Special tours in conjunction with U.Va. programs: Ten tours involving 82 individuals; including faculty, staff, students and guests. Individual tours: ( Individuals, not part of groups, touring the facility in 1997 totaled 103. Research projects: ( Several research projects utilizing neutron activation analysis or cobalt-60 i gamma ray irradiation were conducted by students and faculty from other j schools during the year. i [ A student from New York University spent about a month at the Facility over the summer doing neutron activation analysis on various phosphorescent f. minerals to see if a correlation might be made between the concentrations of rare earths in these minerals and their degree of phosphorescence. ( l.

E 33 L E. Reactor Facility Suonorted Courses and imhoratories 1. Academic Courses and laboratories The following laboratory course was taught by professors of Nuclear Engineering during 1997 utilizing in part services provided by the Reactor Facility. NE 682 - Nuclear Engineering Laboratory { During June 1997,28 high school and middle school teachers from the state of Virginia attended a one week special course at the Reactor Facility. The title of the course was " Science of Nuclear Energy and Radiation: Environmental Issues and { Safety." It consisted oflectures by University of Virginia nuclear engineering i faculty, laboratory experiments using the reactor and a tour of the North Anna Nuclear Power Station. i F. Degrees Granted by U.Va. in Nuclear Engineering [ The following number of degrees were awarded during 1997 by the University of Virginia in the discipline of Nuclear Engineering: i I [ Masters of Science, Nuclear Engineering............ 2 Masters of Engineering, Nuclear Engineering......... 5 Doctor of Philosophy, Nuclear Engineering........... 3 [ TOTA L................................. 10 i r The following PhD and Master theses by students majoring in Nuclear Engineering L were completed during 1997 in part using services or facilitiet provided at the l U.Va. Reactor Facility. ) A Coucled Deterministic / Stochastic Method for Calculating Neutron Canture Therany Dose Rates. PhD thes's in Nuclear Engineering by Thomas R. Hubbard. Modeline Neutron Attenuntion Prot >crt;es of Boron-Aluminum Shielding Materials. MS thesis in Nuclear Engineering by Jun Gao. Evaluation of Scintillation Screens of Neuten Radiogranhy, MS thesis in Nuclear f Engineering by Carl T. Stebbings. I i Evaluation of a Charge Coupled Device (CCD) for Use as a Nuclear Charged Particle Detector for Snace Anolications, PhD thesis in Nuclear Engineering by { Lisa C. Simonsen Dynamical Analysis of and Accelerator Based Fluid Fueled Sul critical Radioactive Waste Burning System, a PhD thesis in Nuclear Engineering '.,y Michael L. Woosley, Jr. [ The research work for other theses is in progress utilizing Reactor Facility support. 9

4 u VI. FINANCES I 'A. Exnenditures [ Expenditures for 1997 were as follows: State Support Imently Generated Monies g. L Salaries + Fringe benefits: $249,100 $71,300 c Operations: 41,800 35,200 L Subtotals: $290,900 $106,500 F L TOTAL EXPENDITURES: $397,400 r B. Income L Income, both the actual amounts received (for work done in 1997 and in previous 7 years) and billed (in 1997) are shown below: L F Va. State suppon in 1997: $290,900 Local income received in 1997: 195,300 l l '~ TOTAL INCOME: $486,200 7 Total billed in 1997: $155,600 r i L l [. Note: In 1997, additional income and expenses in the form of staff salary support l from research account budgets was also received and spent. This support has the effect of reducing expenditures from the local account budget. In [ 1997, the total for salaries and fringe benefits to support reactor staff. members from research budgets was about $40,000. 1 C. State Sunnort / Retenech and Service Income ) [ 'Ihe' University of Virginia is supported by allocations from the State of Virginia. Of ( . these monies, a portion is allocated for the operation of the Nuclear Reactor Facility. 1~ Th se funds cover many of the expenses directly related to the operation of the reactor but additional monies are necessary to provide for remaining services provided to the university community by the Facility. Additional income is in the form of fees received a 1 m

E 35 for research and service work support. This income is "not business related income" [: because it is primarily used to pay the salaries of extra professional staff members at the Facility who are not state supported. During 1997 there was one full-time salaried staff members receiving their salaries wholly or in part from local funds. Two other full-time [ salaried staff members were supported for part of the year (one resigned in August and the other resigned in November). There were no immediate plans as of the end of 1997 to replace these staff members. One student was employed part-time in the capacity of a b health physics technician while in training to take an NRC operator licensing exam. Some staff members take courses and receive degrees at the University while their salaries are paid from monies generated by service work. In effect, this is another method by which the Reactor Facility supports science education in the University of Virginia School of Engineering and Applied Science. During 1997 one staff member took courses in pursuit of his PhD in Nuclear Engineering. E E E E E 3 I l [ I E ) [ E N __.._-___._.2.--__-_---__-_-_.___--_}}

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