Text

Fortieth Annual Progress Rept Radiation Science & Engineering Ctr Jul 1994-June 1995
	ML20095J282
Person / Time
Site:	Pennsylvania State University
Issue date:	06/30/1995
From:	Voth M; PENNSYLVANIA STATE UNIV., HARRISBURG, PA
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9512270039
	Download: ML20095J282 (84)
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PENNSTATE CIih Culky of Engmeenng Hreaieak Nuckar Reactor Building Radiation Science and Engneering Center The Penn3)hania State University Unnersity Park PA LM02 2301 l

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Annual Operating Report, FY 94-95 PSBR Technical Specifications 6.6.1 License R-2, Docket No. 50-5 December 20,1995 l l

I U. S. Nuclear Regulatorf Commission l Attention: Document Control Desk i Washington, D. C. 20555 )

Dear Sir:

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Enclosed please find the Annual Operating Report of the Penn State Breazeale Reactor (PSBR). I This report covers the period from July 1,1994 through June 30,1995, as required by technical specifications requirement 6.6.1. Also included are any changes applicable to 10 CFR 50.59.

A copy of the Fortieth Annual Progress Report of the Penn State Radiation Science and ;

Engineering Center is included as supplementary information. !

Sincerely yours, th//0&

Marcus H. Voth l Director, Radiation Science and Engineering Center i

Enclosures l cc: Region I Administrator U. S. Nuclear Regulatory Commission )

D. A. Shirley i e o ,,.

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R PDR. / f An Equal Opportunity Unnersity

PENN STATE BREAZEALE REACTOR 1

l Annual Operating Report, FY 94-95 PSBR Technical Specifications 6.6.1 License R-2, Docket No. 50-5 l Reactor Utilization l

l The Penn State Breazeale Reactor (PSBR) is a TRIGA Mark III facility capable of 1 MW steady state operation, and 2000 MW peak power pulsing operation. Utilization of the reactor and its associated facilities falls into three major categories:

j EDUCATION utilization is primarily in the form oflaboratory classes conducted l for graduate and undergraduate students and numerous high school science groups.

l These classes vary from neutron activation analysis of an unknown sample to the calibration of a reactor control rod. In addition, an average of 2000 visitors tour the l PSBR facility each year.

RESEARCH accounts for a large portion of reactor time which involves i Radionuclear Applications, Neutron Radiograpy, a myriad of research programs by faculty and graduate students throughout the University, and various applications by the I industrial sector.

TRAINING programs for Reactor Operators and Reactor Supervisors are offered

! and are tailored to meet the needs of the participants. Individuals taking part in these I

programs fall into such categories as power plant operating personnel, PSBR staff, and foreign trainees.

The PSBR facility operates on an 8 AM - 5 PM shift, five days a week, with an occasional 8 AM - 8 PM or 8 AM - 12 Midnight shift to accommodate laboratory courses or research projects.

Summary of Reactor Operating Experience l Technical Soecifications reauirement 6.6.1.a.

Between July 1,1994 and June 30,1995, the PSBR was critical for 561 hours0.00649 days 0.156 hours 9.275794e-4 weeks 2.134605e-4 months or 2.2 hrs / shift i subcritical for 401 hours or 1.6 hrs / shift l used while shutdown for 474 hours0.00549 days 0.132 hours 7.837302e-4 weeks 1.80357e-4 months or 1.9 hrs / shift not available 0 hours0 days 0 hours 0 weeks 0 months or 0.0 hrs / shift Total usuage 1436 hours0.0166 days 0.399 hours 0.00237 weeks 5.46398e-4 months or 5.6 hrs / shift The reactor was pulsed a total of 131 times with the following reactivities:

less than $2.00 43

$2.00 to $2.50 54 greater than $2.50 34 The square wave mode of operation was used 89 times to power levels between 100 and l 5%KW.

l Total energy produced during this report period was 259 MWH with a consumption of 13 grams of U-235.

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Unscheduled Shutdowns Technical Soecifications recuirement 6.6.1.b.

The 9 unplanned shutdowns during the July 1,1994 to June 30,1995 period are described below.

July 7,1994 - After the reactor operated at 800 kW for one hour, the N-16 pump stopped l causing a west bridge monitor alann, a building evacuation and a reactor scram. This was the first reactor operation since the bridge installation that required the newly installed N-16 pump to operate. Problem was a thermal overload of the heater coils in the pump relay box; coils were upgraded.

July 21,1994 - After operating at 200 kW for about two minutes, the reactor operator noticed a drop in power and the auto control system driving three rods out to compensate.

The operator scrammed the reactor. The transient rod drive air supply had not been returned to service following the cleaning and lubrication of the transient rod cylinder and i the rod drifted into the core when the air supply in the accumulator tank on the reactor i bridge was exhausted.

August 8,1994 - With the reactor operating at 800 kW, the N-16 pump flow was adjusted to find an optimum flow to decrease the radiation levels as seen by the bridge monitors. First the valve was opened and at 16 psig no significant change in radiation levels was noted and then the valve was throttled to 20 psig. The pump shutoff and the operator scrammed the reactor but not in time to prevent an evacuation from the bridge east monitor at 40 mR/hr. An investigation found that because of thermal heating the pump would shutdown with a flow of about 20 psig (the pump had been operating at 18 psig). The flow was returned to 18 psig and operations resumed. The next day the valve was opened all the way for a pressure of 16 psig and power was increased in steps to check radiation levels; it was decided that this was the optimum pressure for operation.

August 25,1994 - The operator scrammed the reactor as per SOP-9, Operation of the Rabbit System, upon the receipt of a Rabbit System I high radiation alarm from the monitor that looks at the radiation level in the system surge tank. The reactor had been operating at 900 kW for 31 minutes when the alarm was received. Health Physics and reactor staff investigation led to the decision to replace the reactor bay portion of the system poly tubing. The old tubing showed signs of deterioration and air leaks into the system were suspected to have caused elevated argon-41 production.

September 12,1994 - Reactor power had just been increased to 1000 kW when a RSS Fuel Temperature I scram occurred. A historical trend revealed the scram temperature to be 588 degrees C. The fuel temperature had increased during the year and although operators knew the temperature was approaching the scram point, they thought the temperature scram was set at 600 degrees C.

February 10,1995 - The reactor was approaching critical when a DCC-X Interlock Validation Failure Scram occurred ; the operator was not pushing the rod control buttons at the time of the scram. The interlock failure was generated for both the transient and regulating rods. The initial cause for the failure could not be determined from historical trends. A review of the logic did not indicate a condition that would be common for the transient and regulating rods and not common for all four rods. Verified that RSS relays were seated properly, verified up inhibits in DCC-X, verified control voltage for the safety system, and verified proper rod pushbutton up and down response.

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1 l March 31,1995 - Safety rod was being raised to do a scram check during the moming 1 checkout when a DCC-X Transient Rod Velocity Validation Failure occurred . The event 3

was reproduced three times but could then not be repeated again. Using historical trends 1 l

j for troubleshooting, the spread between the feedback signal and the velocity out signal was greater than that allowable thus causing the validation failure. The I/O manufacturer was contacted and could suggest no maintenance once the connections were initially torqued down correctly . A torque screwdriver was ordered and all I/O connections were i

checked during a console calibration / maintenance check in June of 1995.

April 6,1995 - A watchdog scram was initiated when DCC-X failed due to a matrox error a while attempting a backup to floppy for DCC-X bin file group. The watchdog scram l l occurred as it should have. The reactor was shutdown at the time of this event.

, April 20,1995 - The reactor operator wanted to turn on the second bay exhaust fan but l indadvertently turned off the operating bay exhaust fan. As perdesign, the reactor l

! console initiated a scram when it sensed both exhaust fans were off. The operator wanted l to rid the bay of exhaust fumes coming from a roof repair project. ;

1 1 Major Maintenance With Safety Significance ,

Technical Soecifications recuirement 6.6.1.c. l No major preventative or corrective maintenance operations with safety significance have been performed during this report period.

Major Changes Reportable Under 10 CFR 50.59 Technical Soecifications reauirement 6.6.1.d.

Facility Changes - None reportable under 10 CFR 50.59 Procedures - All procedures are reviewed as a minimum biennially, and on an as needed basis. Changes during the year were numerous and no attempt will be made to list them.

A current copy of all facility procedures will be made available on request.

New Tests and Experiments - None having safety significance.

Radioactive Effluents Released Technical Soecifications reauirement 6.6.1.e.

Liquid There were no liquid effluent releases under the reactor license for the report period.

Liquid from the regeneration of the reactor demineralizer is evaporated and the distillate recycled for pool water makeup. The evaporator concentrate is dried and the solid salt residue is disposed of in the same way as other solid radioactive waste at the University.

Liquid radioactive waste from the radioisotope laboratories at the PSBR is under the University byproduct materials license and is transferred to the Health Physics Office for disposal with the waste from other campus laboratories. Liquid waste disposal techniques include storage for decay, release to the sanitary sewer as per 10 CFR 20, and solidification for shipment to licensed disposal sites.

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4 Gaseous i' Gaseous effluent Ar-41, is released from dissolved air in the reactor pool water, dry irradiation tubes, and air leakage from the pneumatic sample trahsfer systems.

4 The amount of Ar-41 released from the reactor pool is very dependent upon the operating power level and the length of time at power. He release per MWH is highest for extended high power runs and lowest for intermittent low power runs. The concentration of Ar-41 in the reactor bay and the bay exhaust was measured by the Health Physics staff during the summer of 1986. Measurements were made for conditions oflow and high power runs simulating typical operating cycles. Based on these measurements, an annual release of between 196 mci and 595 mci of Ar-41 is calculated for July 1,1994 to June 30,1995, resulting in an average concentration at ground level outside the reactor building that is 0.3 % to 0.9 % of the effluent concentration limit in Appendix B to 10 CFR 20.1001 - 20.2401. The concentration at ground level is estimated using only dilution by a 1 m/s wind into the lee of the 200 m2smallest cross section of the reactor bay.

During the report period, several irradiation tubes were used at high enough power levels and for long enough runs to produce significant amounts of Ar-41. The calculated annual production was 66 mci. Since this production occurred in a stagnant volume of air confined by close fitting shield plugs, most of the Ar-41 decayed in place before being j released to the reactor bay. The reported releases from dissolved air in the reactor pool are based on measurements made,in part, when a dry irradiation tube was in use at high power levels; the Ar-41 releases from the tubes are part of rather than in addition to the release figures quoted in the previous paragraph. The use of the pneumatic transfer i systems was minimal during this period and any Ar-41 releases would be insignificant .

since they operate with CO-2 and Nitrogen as fill gases.

Tritium release from the reactor pool is another gaseous release. The evaporation rate of ,

the reactor pool was checked recently by measuring the loss of water from a flat plastic l dish floating in the pool. The dish had a surface area of 0.38 ft2 and showed a loss of l 139.7 grams of water over a 71.9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months period giving a loss rate of 5.11 g ft-2 hr-l.

Based on a pool area of about 395 ft2 the annual evaporation rate would be 4680 gallons.

This is of course dependent upon riative humidity, temperature of air and water, air movement, etc. For a pool 3H concentration of 20,000 pCi/l (the average for July 1994 to June 1995) the tritium activity released from the ventilation system would be 354 pCi.

A dilution factor of 2 x 10 ml 8 s-1 was used to calculate the unrestricted area c concentration. This is from 200 m2 (cross-section of the building) times 1 m s-1 (wind velocity). These are the values used in the safety analysis in the reactor license. A sample of air conditioner condensate showed no detectable 3 H . Thus, there is probably very little 3H recycled into the pool by way of the air conditioner condensate and all evaporation can be assumed to be released.

3H released 354 pCi Average concentration, unrestricted area 2.6 x 10-14 pCi/ml Permissible concentration, unrestricted area 1 x 10-7 Ci/mi

- Percentage of permissible concentration 5.6 x 10-5 %

Calculated effective dose, unrestricted area 2.8 x 10-5 mrem i

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Environmental Surveys Technical Soecifications reouirement 6.6.1.f.

The only environmental surveys performed were the routine TLD gamma-ray dose ,

measurements at the facility fenceline and at control points in residential areas several miles away. This reporting year's measurements (in millirems) tabulated below represent the July 1,1994 to June 30,1995 period. A comparison of the North, West, East, and South fenceline measurements with the control measurements at Houserville (1 mile away) show the differences to be similar to those in the past.

1st Otr 2nd Otr 3rd Otr 4th Otr Intal Fence Nonh 22.7 19.8 20.8 22.7 86.0 Fence West 20.0 19.1 17.9 21.7 78.7 Fence East 22.8 20.0 21.0 22.6 86.4 i Fence South 19.9 19.1 20.8 21.4 81.2 l Control-Houserville 17.5 15.3 16.5 18.6 67.9 Personnel Exposures Technical Soecifications recuirement 6.6.1.e.

No reactor personnel or visitors received an effective dose equivalent in excess of 10% of the permissible limits under 10 CFR 20.

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l Fortieth Annual Progress Report Radiation Science

and Engineering Center l August 1995 1

i I Contract DE-ACO7-941D-13223

. Subcontract C88-101857

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J sFORTIETH ANNUAL PROGRESS REPORTi

[P5NN ST TElR1DI TION SCIENCE 1ND. ENGINE 5 RING CENT 5R) 6sm 2.; aa s , s . , , ,

1 July 1,1994 to June 30,1995 1 l

Submitted to: i 1

United States Department of Energy I

and The Pennsylvania State University By:

Marcus H. Voth (Director) l Terry L. Flinchbaugh (Editor) !

l Penn State Radiation Science and Engineering Center Depanment of Nuclear Engineering The Pennsylvania State University University Park, PA 16802 August 1995 l

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Contract DE-AC07-94ID-13223 i Subcontract C88-101857 !

i U.Ed.ENG 96-29 i

PENNSTATE m

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i STATEMENT OF NONDISCRIMINATION The Pennsylvania State University is committed to the policy that all persons shall have equal access to programs, facilities, admission, and employment without regard to personal characteristics not related to ability, performance, or qualifications as determined by University policy or by state or federal authorities. The Pennsylvania State University does not discriminate against any person because of age, ancestry, color, disability or handicap, national origin, race, religious creed, sex, sexual orientation, or veteran status. Direct all affhmative action inquiries to the Affirmative Action Office, The Pennsylvania State University,201 Willard Building, University Park, PA 16802-2801;(814) 863-0471.

This publication is available in altemative media on request.

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i TABLE OF CONTENTS s

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i V PREFA CE - M . H . Voth . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -

1 I . INTROD U CTIO N - M . H . Vo th . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

I II. PE R S O N NE L - T. L. Fli ne h bau g h ... ........ . .... .......... ..... ..... . .... ... ...... .. .... . 3 i

III. REACTOR OPERATIONS - T. L. Flinchbaugh . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . 7 1 i ,

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, IV. G AMMA IRRADIATION FACILITY - C. C. Davison . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11

? l I V. EDUCATION AND TRAINING - T. L. Flinchbaugh, C. C. Davison ...... .......... 13 l i 1 VI. NEUTRON BEAM LAB ORATORY - R. G ould . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 VII. RADIONUCLEAR APPLICATIONS LABORATORY -T.H. Daubenspeck ........ 21 l'

VIII. LOW LEVEL RADIATION MONITORING LABORATORY - J. Lebiednk ......... 23 IX. ANGULAR CORRELATIONS LABORATORY - G. L. Catchen ..................... 25 t

i X. RADIATION SCIENCE AND ENGINEERING CENTER RESEARCH UTILIZATION - T. L. Flinchbau gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 A. Penn State University Research Utilizing the Facilities of the Penn State Radiation Science and Engineering Center ........................ 29 B. Other Universities, Organizations and Companies Utilizing the Facilities of the Penn State Radiation Science and En gineerin g Cen ter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 APPENDIX A. Faculty, Staff, Students, and Industries Utilizing the Facilities of the Penn State Radiation Science and Engineering Center - T. L.

Fli nc h bau gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57

.I APPENDIX B. Formal G roup Tours - L. D. B razee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 i

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O TABLES Eage Iahlc Personnel..................................................................................... 4 1

2 R e ac to r O p e ra t i o n D a t a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 3 Reactor Utilization Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4 Co'oalt-60 Utilization Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 5 College and High School Group s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 FIGURES Eigmn Eagn 1 Organi zation Chart . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 i

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l PREFACE

.i Administrative responsibility for the Radiation Science and Engineering Center (RSEC) resides i

in the Department of Nuclear Engineering in the College of Engineering. Overall responsibility for the reactor license resides with the Senior Vice President for Research and Graduate Education.

The reactor and associated laboratories are available to all Penn State colleges for education and ;

l research programs. In addition, the facility is made available to assist other educational institutions, govemment agencies and industries having common and compatible needs and objectives, providing services that are essential in meeting research, development, education and training needs. !

l The Fortieth Annual Progress Report (July 1994 through June 1995) of the operation of The l Pennsylvania State University Radiation Science and Engineering Center is subndtted in accordance with the requirements of Contract DE-AC07-94ID-13223 between the United States Department of Energy and Lockheed Idaho Technologies Company (LITCO), and their Subcontract C88-101857 with The Pennsylvania State Umversity. This report also provides the University administration with a summary of the utilization of the facility for the past year.

i Numerous individuals are to be recognized and thanked for their dedication and committment in i this report, especially Terry Flinchbaugh who edited the report and Lisa Brazee who typed it.

Special thanks are extended to those responsible for the individual sections as listed in the Table of i Contents and to the individual facility users whose research summaries are compiled in Section X.

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- I. INTRODUCTION August 15,1995, marked the fortieth anniversary of the initial criticality of the Penn State Breazeale Reactor (PSBR), making it the longest operating university research reactor in the nation. Despite its early beginnings, efforts are made to continually upgrade the entire Radiation i Science and Engineering Center (RSEC) to a state-of the-art facility capable of cutting edge )

research. This report tabulates the number of users, experiments performed, and hours of operation along with summaries of the nature of work performed, and its significance. Highlights among the year's accomplishments are discussed below:

Three visiting scientists performed work at the RSEC. his. Faridah Idris, an lAEA l Fellow, studied ways to increase the power level of the hialaysian TRIGA reactor. Dr.

Evgueni Shabalin, a SABIT Intern, collaborated in cold neutron research techniques while investigating new applications for research reactors, specifically for his facility in Russia. l Dr. Andrea Paesano of Brazil is performing research on materiais in collaboration with Drs. l Catchen and blotta. l l

Dr. Edwards and his students continue to make major contributions in the field of advanced controls. They hosted a successful seminar to disseminate their research findings and l l

prepare to host the 1996 American Nuclear Society topical meeting on Nuclear Plant Instrumentation. Control and Human Interface Technoloev at Penn State.

- Neutron radiography is being used for a new application by Dr. Prescott and his students as they investigate transport phenomena during the solidification of alloys.

- A staff program has commenced in the hot cell facility to monitor the long term performance of irradiated high nickel steels under strain, integrating the measurements with Dr. hiotta's research in the performance of irradiated metals.

. The spatial transient behavior of the TRIGA reactor is being used by Dr. Feltus and her students to evaluate the fidelity of state-of-the-art power reactor computer models. Similar data was also provided to the Nuclear Regulatory Commission to simulate a classic rod drop accident or rod ejection accident as a benchmark for deliberations in their license review process.

. Preliminary experiments on cold neutron studies commenced with the assistance of Dr.

Shabalin. Work continues on Dr. Sokol's cold neutron irradiation facility in support of improved performance of the Intense Pulsed Neutron Source at Argonne National Laboratory.

. A number of facility enhancements were made to improve the performance and capabilities of the RSEC. A work station provided as part of a DOE grant was installed and made operational for improved capability of analytical computations. A procedure was developed and demonstrated to implement the movable core feature of the bridge modification. A new Cobalt-60 dry irradiator was installed, increasing the effective age of our gamma irradiation capability by 15 years.

Operations in support of these accomplishments proceeded with no violations cited in NRC inspection reports. One Reactor Operator and two Senior Reactor Operator license exams were administered by the NRC with all three candidates passing.

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- II. PERSONNEL l l Maurice Peagler was promoted from Environmental Analyst to Research Suppon Technician III ,

l effective July 1,1994 in the LLRML. Maurice resigned his position effective August 1,1994 to accept a l

health physics assistant position with the university. In anticipation of Maurice's departure, Jana

.ebiedzik was hired as a wage payroll employee effective July 1,1994 and assumed Maurice's position on l I

August 1,1994.

Mac Bryan was promoted from Assistant Research Engineer to Reactor Supervisor / Engineer effective I March 1,1995.

Lisa Brazee, Staff Aiet V, took a personal leave of absence from June 1,1995 to June 30,1995.

Carol Houtz was hired as venge payroll secretary during that time.

i Several wage payroll personnel provided support during the year. Scott Anderson, Mary Imu Gougar, Joy Moncil, Chris Nonnan, Lois Lunetta and Danielle Page provided suppon in the educational programs area. Scott Anderson and Jeff Simons provided clerical support. Brian Marazi provided support to the supervisor of facility services.

Dhushy Sathianathan (Assistant Professor, Engineering Graphics) was appointed to serve on the Penn ,

State Reactor Safeguards Committee (PSRSC) from August 1,1994 to September 30,1995 while committee member Paul Sokol was on sabbatical leave. On January 1,1995, Mike Slobodien (Radiological Controls Director, General Public Utilities) left the committee after serving the maximum two tenns allowed by the committee charter. His replacement was Patrick J. Donnachie, Jr. (Health Physicist, General Public Utilites).

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Personnel Faculty and Staff Ittk i I

- P. G. Boyle Reactor Supervisor / Nuclear Education Specialist j L. D. Brazee Staff Assistant V :

- M. E. Bryan Reactor Supervisor / Engineer G. L. Catchen Associate Professor

- T. Daubenspeck Reactor Supervisor / Reactor Utilization Specialist

- C. C. Davison Reactor Supervisor / Nuclear Education Specialist

- T. L. Flinchbaugh Operations and Training Manager M. P. Grieb Engineering Aide R. Gould Research Assistant )

- D. E. Hughes Senior Research Assistant / Manager of Engineering Services W. A. Jester Professor ,

C. J. Kowalske Administrative Assistant J.Lebiedzik Research Support Technician III l

- A. J. McLellan - Reactor OperatorIntern

- D. R. Miller Reactor OperatorIntem i M. Q. Peagler (resigned) Research Support Technician III

K.E.Rudy Operational Suppon Services Supervisor j P. J. Stauffer Staff Assistant VII

- M, H. Voth Associate Professor / Director .

l 1

1

Licensed Operator

- Licensed Senior Operator i Technical Service Staff J. E. Armstrong Mechanic-Experimental and Maintenance j R. L. Eaken Machininst A j Wage Payroll S. Anderson M. Gougar C. Houtz D. Page L. Lunetta i B. Marazi i J. Moncil ,

C. Norman l J. Simons i

4

4 i - Penn State Reactor Safeguards Committee

- ** P. J. Donnachie, Jr. Health Physicist, General Public Utilities

! E. W. Figard Supervisor of Maintenance, Pennsylvania Power and Light i

Susquehanna Steam Electric Station R. W. Granlund Health Physicist,Intercollege Research Programs and Facilities, Penn State D. E. Hughes Senior Research Assistant, Penn State Radiation Science and Engineering Center P. Loftus Manager, Product Licensing, Westinghouse J. H. Mahaffy Assistant Professor, Nuclear Engineering, Penn State G. E. Robinson Chairman, Associate Professor, Nuclear Engineering, !

l Penn State

- - D. Sathianathan Assistant Professor, Engineering Graphics, Penn State

M. J. Slobodien Radiological Controls Director, General Public Utilities P. E. Sokol Associate Professor, Physics, Penn State M. H. Voth Ex officio, Director, Penn State Radiation Science and Engineering Center W. F. Witzig Professor, Nuclear Engineering, Penn State (retired)

Served through January 1,1995

- Appointed January 1,1995

- - Temporary appointment from August 1,1994 to September 30,1995 during P. E. Sokol's sabbatical 5

- - - . .= . __

, ~ . , .

I, 1

DIRECTOR MANAGER OF MANAGER OF i STAFF OPERATIONS ENGINEERING ASSISTANT Vil AND TRAINING SERVICES i I

i STAFF WAGE PAYROLL /

ASSISTANT V WORK STUDY ,

REA N R REA N R REA N R

RESEARCH SUPPORT RESFARCil OF FACILITY SUPERVISOR /

SUPERVISOR, SUPERVISOR, ASSISTANT TECHNICIAN-Ill LLRML SERVICES ENGINEER i NUCLEAR REACTOR '

EDUCATION UTILIZA~nON l SPECIALIST (2) SPECIALIST !

ENGINEERING AIDE l WAGE PAYROLI/ '

WORK STUDY EXPERIMENTAL .

MACillNIST A AND MAINTENANCE REACTOR MECHANIC OPERATOR INTERN (2) ,

WAGEPAYROLl/

WORK STUDY !

i FIGURE 1 RSEC Organization Chart aS Of 6/30/95 i

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. III. REACTOR OPERATIONS Research reactor operation began at Penn State in 1955. In December of 1965 the original core, which operated at a maximum power level of 200 KW, was replaced by a more advanced TRIGA core, capable of operation at 1000 KW. The present core may also be operated in a pulse fashion in which the power level is suddenly increased from less than 1 KW to up to 2000 KW for short (milliseconds) periods of time. TRIGA stands for Training, Research, Isotope Production, built by General Atomic Company.

Utilization of the PSBR falls into three major categories:

Educational utilization is primarily in the form oflaboratory classes conducted for graduate and undergraduate degree candidates and numerous high school science groups. These classes will vary from the irradiation and analysis of a sample to the calibration of a reactor control rod.

Research accounts for a large portion of reactor time which involves Radionuclear Applications, Neutron Radiography, a myriad of research programs by faculty and graduate students throughout the University and various applications by the industrial sector.

Trainine programs for Reactor Operators and Reactor Supervisors are offered and can be tailored to meet the needs of the participants. Individuals taking part in these programs fall into such categories as PSBR reactor staff and power plant operating personnel.

The PSBR core, containing about 7.5 pounds of Uranium-235, in a non-weapons form, is operated at a depth of approximately 18 feet in a pool of demineralized water. The water provides -

the needed shielding and cooling for the operation of the reactor. It is relatively simple to expose a sample by positioning it in the vicinity of the reactor at a point where it will receive the desired radiation dose. A variety of fixtures and jigs are available for such positioning. Various containers and irradiation tubes can be used to keep samples dry. Three pneumatic transfer systems with different neutron levels offer additional possibilities. Core rotational, east-west, and north-south movements provide flexibility in positioning the core against experimental apparatus.

1 In normal steady state operation at 1000 kilowatts, the thermal neutron flux available varies from approximately 1 x 1013 n/cm 2/sec at the edge of the core to approximately 3 x 1013 n/cm 2/sec .

in the central region of the core.

When using the pulse mode of operation, the peak flux for a maximum pulse is approximately ;

6 x 1016n/cm 2/see with a pulse width of 15 msec at 1/2 maximum.

Support facilities include a machine shop, electronic shop, laboratory space and fume hoods.

STATISTICAL ANALYSIS Tables 2 and 3 list Reactor Operation Data and Reactor Utilization Data-Shift Averages, respectively, for th,e past three years. In table 2, the Critical time is a summation of the hours the reactor was operating at some power level. The Suberitical time is the total hours that the reactor key and console instrumentation were on and under observation,less the Critical time. Subcritical l time reflects experiment set up time and time spent approaching reactor criticality. Fuel movement hours reflect the fact that there were minimal fuel movements made this year.

The Number of Pulses reflects demands of undergraduate labs, researchers and reactor operator training programs. Square waves are used primarily for demonstration purposes for public groups touring the facility, researchers and reactor operator training programs.

The number of Scrams Planned as Part of Experiments reflects experimenter needs. One Unplanned Scram Resulting from Personnel Action occurred when the console sensed both bay 7

exhaust fans were off because of an ope rator swi8ching error. The Unplanned Scrams Resulting '

from Abnormal System Operation were because of: 1) two N-16 pump failures from thermal 1 overloads,2) loss of transient rod air supp1y because of a maintenance error,3) elevated Argon-41 in pneumatic transfer system because of air leaks and,4) normal operating fuel temperature was too close to fuel temperature scram set point.

Table 3, Part A, Reactor Usage, indicates Hours Critical and Hours Subcritical, and also 1 i

Hours Shutdown such as for instruction or experimental setup. Occasionally a component failure prohibits reactor operation. The necessary repair time is included in Reactor Usage as Reactor Not Available to reflect total reactor utilization on a shift basis.

Part B gives a breakdown of the Type of Usage in Hours. The Nuclear Engineering Department and/or the Reactor Facility receives compensation for Industrial Research and Service.

Umversity Research and Service includes both funded and non-funded research, for Penn State and other universities. The Instruction and Training category includes all formal university classes involving the reactor, experiments for other university and high school groups, demonstrations for tour groups and in-house reactor operator training.

Part C statistics, Users / Experimenters, reflect the number of users, samples and experimenters per shift. Part D shows the number of eight hour shifts for each year.

INSPECTIONS AND AUDITS During October of 1994, Stephen Miller, Deputy Director, AFRRI Triga Reactor Facility, conducted an audit of the PSBR. This fulfilled a requirement of the Penn State Reactor Safeguards Committee charter as described in the PSBR Technical Specifications. The reactor staff has implemented changes suggested by that report, all of which exceed NRC requirements.

During November of 1994, a NRC routine inspection was conducted of activities authorized by the broad byproduct material license (37-185-(M), the Cobalt-60 facility license (37-185-05), the self-shielded irradiator license (37-185-M) and the SNM-95 license. No items of non-compliance were identified for reactor activities.

During April of 1995, a NRC routine inspection was conducted of activities authorized by the special nuclear materials license SNM 95 and the R-2 reactor license. No items of non-compliance were identified.

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- TABLE 2 i 1

1 Reactor Operation Data l July 1,1992 - June 30,1995 92-93 2 1-24 244-21 A. Hours of Reactor Operation ;

1. Critical 635 601 561 l

2. Suberitical 404 362 401 !

3. FuelMovement 8 31 27 B. Number of Pulses 77 48 131 C. Number of Square Waves 60 68 89 D. Energy Release (MWH)' 391 391 259 i 1

E. Grams U-235 Consumed 20 20 13 F -. Scrams

1. Planned as Part of Experiments 20 27 15 i

2. Unplanned - Resulting From l a) Personnel Action 2 2 1 b) Abnormal System Operation 1 1 5

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, TABLE 3 .

Reactor Utilization Data Shift Averages July 1,1992 - June 30,1995 22:9.3. 2h24 9_4:.9.1 A. Reactor Usage

1. Hours Cntical 2.5 2.4 2.2 -

2. Hours Suberitical 1.6 1.4 1.6

3. Hours Shutdown 1.6 1.5 1.9

4. ReactorNot Available DJ. 04 0 2

TOTAL HOURS PER SHIFT 5.8 5.9 5.6

B. Type of Usage - Hours

1. Industrial Research and Service 0.9 0.6 0.7 '

2. University Research and Service 2.3 2.1 1.5

3. Instruction andTraining 1.1 1.4 1.3

4. Calibration and Maintenance 1.4 1.8 2

5. FuelHandling 0.1 0.1 0.1 C. Users / Experiments

1. Number of Users 2.7 2.3 2.4

2. PneumaticTransferSamples 0.7 0.6 0.5

3. Total Number of Samples 3.1 2.3 2.4

4. SampleHours 2.7 2.9 2.4 D. Numberof 8 HourShifts 250 254 255 i

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- IV. GAMMA IRRADIATION FACILITY The University, in March of 1956, purchased 23,600 curies of Cobalt-60 in the form of stainless steel clad source rods to provide a pure source of gamma rays. In November of 1971, the University obtained from the Natick Laboratories,63,537 curies of Cobalt-60 in the form of aluminum clad source rods. These source rods have decayed through several half-lives, leaving a July 1,1995 approximate total of 3300 curies.

In this facility, the sources are stored and used in a pool 16 feet by 10 feet, filled with 16 feet of demineralized water. The water provides a shield which is readily worked through and allows great flexibility in using the sources. Due to the number of rods and size of the pool,it is possible to set up several irradiators at a time to vary the size of the sample that can be inadiated, or vary tiie dose rate. Experiments in a dry environment are possible by use of either a vertical tube or by a diving belltype apparatus.

The Cobalt-60 facility is designed with a large amount of working space around the pool and has two laboratories with work benches and the usual utilities.

Maximum exposure rates of 121 KR/Hr in a 3" ID tube and 70 KR/Hr in a 6" ID tube are available as of July 1,1995.

A GammaCell 220 irradiator is being donated to Penn State by the David Sarnoff Research Center in Princeton, New Jersey. The transfer of the device is scheduled for July 1995. This device has a dose rate considerably higher than that currently available in the RSEC pool facility or with another irradiator on campus. It will take approximately fifteen years for the dose rate on the GammaCell 220 to decay to the current RSEC dose rates available, thus providing a fifteen year extension of usable irradiation capability.

Table 4 compares the past three years' utilization of the Cobalt-60 facility in terms of time, numbers and daily averages.

11

I e

TABLE 4 .

Cobalt-60 Utilization Data July 1,1992 - June 30,1995 92-93 23-14 9191 A. Time Involved (Hours)

1. Set-Up Time 171 130 90

2. Total Sample Hours 10,975 6,547 2694 B. Numbers Involved

1. Samples Run 684 510 677

2. Different Experimenters 35 36 39

3. Configurations Used 4 3 4 C. Per Day Averages

1. Experimenters 0.8 0.54 0.59

2. Samples 2.75 2.05 2.72 12

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- V. EDUCATION AND TRAINING During the past year, the Penn State RSEC was used for a variety of educational services; in-house training, formal laboratory courses and many continuing education programs and tours.

The RSEC operating staff has maintained reactor operator competence and safe facility operation thmugh training and requalification. In-house reactor operator requalification during November of 1994 consisted of an oral examination on abnormal and emergency procedures given by P. G. Boyle and an operating test given by T. L. Flinchbaugh. A written exam was administered by K. E. Rudy.

Staff member Thierry Daubenspeck and operator intern Alexander McLellan panicipated in the reactor operator training program during 1994 and were granted their senior reactor operator licenses by the NRC in September 1994. Staff member Mark Grieb panicipated in the reactor operator training program during 1994 and 1995 and was granted a reactor operator's license by l the NRC in June 1995.

3 He ninth session of the Pennsylvania Governor's School for Agricultural Sciences was held at i

Penn State's University Park campus during the summer of 1994. Sixty-four high school scholars panicipated in the five week program at Penn State. The Governor's School for Agricultural Sciences includes introduction and experience in many different agricultural disciplines. There are several parts of the program which are considered " core courses". The core courses are fundamentalinstrucuon given to all participants. " Radioisotope Applications in Agricultural i Research" is one of the core courses in the program. The program was conducted at Penn State's l RSEC by Candace Davison along with Mary Lou Gougar and nuclear engineering student Scott l Andenon. Maurice Peagler, Supervisor of the Low-Level Radiation Monitoring Laboratory i provided a session on detection of radiation in the environment including radon gas. The students performed a series of experiments focusing on the fundamentals of radiation interaction and principles of radioisotope, applications. These experiments included a demonstration of a cloud

chamber; penetrating abihty of alpha, beta and gamma radiation; half-life calculation and gamma ray spectroscopy. The importance of statistics in taking data and other applications of radioactive materials in research were discussed. The students were also given a tour of the reactor facility.

He Nuclear Concepts and Technological Issues Institute (NCTII) was conducted from July 11-22,1994 at the University Park campus. The Nuclear Concepts program was designed to prepare secondary science educators to teach the basics of nuclear science, radiation, and i applications and is offered as a special topics course in nuclear engineering. Twenty-three l secondary science teachers participated in the program. The program was developed in 1970 and j

has been conducted every summer since that time. The 1994 program differed in that it was a two-week applications course. This change provided an intense course in a short period of time.

)

Suppon for the program included funding through a grant from the National Science Foundation for ten teachers. Sponsorship of the other thineen participants was provided by Baltimore Gas and Electric Company, Chem-Nuclear Systems Inc., Edison Electric Institute, General Electric Company, Gilbert Associates, GPU Nuclear Corporation, Oxford Instruments Inc. and various school districts. Materials were obtained from the U.S. Department of Energy, USCEA, ANS and other sources. General Electric Company donated many educational materials to the course including a full-size Chart of the Nuclides and booklet to each panicipant.

The institute was coordinated by Candace Davison and was conducted through Penn State's Continuing Education Office. Joseph Bonner presented the fundamental nuclear science lectures.

3 Other instruction was provided by Nuclear Engineering department personnel and Rodger j Granlund, University Health Physicist. Guest speakers from government, research, and industry

provided expertise for the technical and issues sessions. Guest speakers included Mr. Alan

Brinser from Chem-Nuclear Systems Inc., Mr. John Redding from General Electric Company, 4

Mr. Chris Davis from Westinghouse Electric Corporation, and Dr. Frank Olney from Radiology 13

Associates. Several Alumni from the course discussed implementation of nuclear science into ,

their curriculum.

Laboratory experiments are an important aspect of the institute as the teachers are able to have hands-on expenence with radioactive materials. The laboratories were conducted at the RSEC under the direction of the RSEC and Health Physics personnel. Guy Anderson, a chemistry teacher from the Bald Eagle Area School District was in charge of the laboratories. The laboratory experiments and demonstrations included: characteristics of ionizing radiation, neutron activation of Indium, complex decay of Silver-110 and Silver-108, neutron radiography, and the approach to critical experiment. Discussion and problem solving sessions along with a field trip to either Three Mile Island Unit 1 (a PWR) or Susquehanna Steam Electric Station (a BWR) were included in the schedule.

Evaluations from the participants were very positive concerning the course. As in previous institutes, the participants in NCTIl were encouraged to return with their students for a day of experiments at the RSEC. Two follow up programs were conducted during Octoberin the Harrisburg area. The first program on the Medical Applications of Radiation and Radiosotopes was conducted at the Hershey Medical Center on Friday, October 14,1994. The program included a variety of speakers who discussed their research and how radioisotopes are used. An overview of medicalimaging and a tour of the Low-level waste storage facility was also included for the participants. A program on Fundamental Particles and Interactions was conducted on Saturday, October 15,1994 at the Penn State Harrisburg Campus. Dr. Ted Zalesckiewize of the University of Pittsburgh at Greensburg conducted the program and utilized a hypercard computer program and slides to introduce the topic.

The University Reactor Sharing Program is sponsored by the U.S. Department of Energy.

The purpose of this program is to increase the availability of the university nuclear reactor facilities to non-reactor owning colleges and universities. The main objectives of the University Reactor Sharing program are to strengthen nuclear science and engineering instruction and to provide research opportunities for other educational institutions including universities, colleges, junior colleges, technical schools and high schools.

A total of 842 students and teachers from 35 high schools and 2 colleges came to the RSEC for experiments and instruction. (see Table 5). Candace Davison and Lois Lunetta were the main instructors for the program. Other instruction and technical assistance for experiments were provided by Thierry Daubenspeck, Jana Lebiedzik, Robert Gould and Alex McClellan.

The RSEC staff and facilities provided educational opportunities along with a tour for student and teacher workshops, many of which were conducted as part of a larger program on campus through Penn State Continuing Education Programs. The student programs included: the Kodak BEST (Business, Science, Engineering and Technology) program, the High School Summer Internship, the Civil Engineering VEC-tour program and the Upward Bound program for minority and "at risk" students. Twenty four teachers from the Harrisburg area participated in a full day of experiments as part of the course " Exploring the Nuclear Option". Thirty-six teachers from the Enter-2000 program received instruction and toured the facility to learn more about nuclear energy and related careers.

In addition to the full or half-day programs with experiments, educational tours were conducted for students, teachers, and the general public. All groups, including the reactor sharing groups, who toured the facility are listed in Appendix B. The RSEC operating staff and Nuclear Engineering Department conducted 122 tours for 2,518 persons.

14

_ _ _ _ _ _ i

The RSEC was used by several Nuclear Engineering and other courses during the year.

Semester Course Instmetor StuderJ2 Hours Summer 1994 NucE 497B-Nuclear Concepts C. C. Davison 23 4 Summer 1994 NucE 444-Nuclear Reactor Operations D. E. Hughes 3 12 Fall 1994 NucE 451-Reactor Physics R. M. Edwards 23 67 W. A. Jester 1994 Food Science 313-Process Plant Production R. B. Beelman 21 2 Fall Spring 1995 NucE 444-Nuclear Reactor Operations D. E. Hughes 8 32 Spring 1995 NucE 450-Radiation Detection and M. H. Voth 23 66 Measurement W. A. Jester 1995 NucE 401-Introduction to Nuclear E. S. Klevans 8 4 Spring Engineering Summer 1995 SciEd 497-Exploring the Nuclear Option C. C. Davison 24 4 In January and February of 1995, a total of 42 University Police Services personnel were given training and retraining sessions by C. C. Davison at the RSEC to ensure familiarity with the facilities and to meet Nuclear Regulatory Commission requirements.

During the 1994-95 academic year, one IAEA fellow and two other visiting professors were hosted by the RSEC and Nuclear Engineering Department.

Ms. Faridah Idris, Research Of6cer for the reactor at the Malaysian Institute for Nuclear Technology Research in Kajank, Malaysia, arrived in January 1995 for a four month visit. She was sponsored as an Intemational Atomic Energy Agency Fellow. Her mission was to study safety analysis technique in preparation for upgrading their one megawatt TRIGA to two megawatts. In addition to working with the RSEC staff, she worked closely with Dr. Haghighat in applying Monte Carlo techniques and using the MCNP code for power distribution and shielding calculation.

Dr. Evgueni Shabalin of the Frank Laboratory of Neutron Physics, Joint Institute for Nuclear Research in Dubna, Russia, arrived in May 1995 for a five-month visit. He is an intern in the Special American Business Internship Training Program (SABIT) with Penn State, funded by the U.S. Department of Commerce. The purpose of Dr. Shabalin's visit is to receive training in commercial aspects of operation of a research reactor. He has .11so turnished technical expertise to the reactor staff and the physics department as they design a Cold Neutron Irradiation Facility.

Dr. Andrea Paesano is currently Assistant Professor of Physics at the State University of Maringd, Brazil. He received both his B.S. and Ph.D. in Physics from the Federal University of Rio Grande do Sul, Brazil. He will be here for at least one year in the context of a collaboration between Penn State and the Federal University of Rio Grande do Sul to study defects in intermetallic compounds of the Zr-Fe system using nuclear spectroscopy, namely, penurbed-angular-correlation, M6ssbauer-effect, and positron-lifetime spectrocopies. He is a specialist in multilayer thin films and M6ssbauer-effect Spectroscopy, and he is working with Dr. Arthur T.

Motta and Dr. Garv L. Catchen.

15

I l

TABLE 5 .

University Reactor Sharing Program l College and High School Groups J 1994-1995 Academic Year J Those who came to the RSEC for experiments received instruction on the basics of radiation l and nuclear energy and received a tour of the facility. All groups either conducted the approach to i l critical experiment or saw a demonstration with the reactor. Most groups also did one of the other l experiments listed below.

4 Gamma Ray Spectroscopy Neutron Activation and Complex Decay of Silver Barium-137m Decay or Silver Decay Neutron Activation Analysis Relative Stopping Powers for (x, and yin Air, Aluminum and Lead Number of Month School and Teacher Students & Teachers

October 4 Harrisburg Academy 29 Barbara Thrush 7 Harmony HS 23 Chad Weiwiora 7 IU-9 50

. Karen Kelly t

November 9 Glendale HS 53

Paul Conway

, 14 State College HS 8 1 Jan Hildenbrandt 16 IU-9 7 JoAnn Castle 18 Williamson HS 31 Bob Burket 21 Greensburg-Salem HS 39 Cheryl Harper December 1 Lock Haven University 4 15 Dubois HS Physics 3 16 Carlisle HS 70 Robert Barrick March 1 Germantown Friends 10

Gary Garber 6 Redland HS 19 Robert Lighty 13 Berwick HS 14 Jeff Snyder, Dave Dobler 15 Bermudian Springs HS 16 Jeanne Sucht 20 Daniel Boone HS 13 Larry Tobias 22 Eastern Lebanon HS 8 Richard Schwalm 22 Peters Township HS 18 WalterJennings 28 State College HS 42 Tod McPherson i

16 i

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, JFOkTIITIfiNNU fPROGRESS: REPORT-

, '. s l.l.PENN.. 5t Ts.RXbi TION SdI5NC, E1ND. EN. GIN...E5RINGidNNI5M h&:: )M.$ s ddM d v2 i:}..i .f.(v34 + v w +

July 1,1994 to June 30,1995 l

l Submitted to:

United States Department of Energy I I

and l l

\

The Pennsylvania State University ,

1 By:

Marcus H. Voth (Director)

Terry L. Flinchbaugh (Editor)

Penn State Radiation Science and Engineering Center Department of Nuclear Engineering The Pennsylvania State University University Park, PA 16802 August 1995 Contract DE-AC07-94ID-13223 Subcontract C88-101857 U.Ed.ENG 96-29 PENNSTATE h

STATEMENT OF NONDISCRIMINATION The Pennsylvania State University is committed to the policy that all persons shall have equal access to programs, facilities, admission, and employment without regard to personal characteristics not related to ability, performance, or qualifications as determined by University policy or by state or federal authorities. The Pennsylvania State University does not discriminate against any person because of age, ancestry, color, disability or handicap, national origin, race, n:ligious creed, sex, sexual orientation, or veteran status. Direct all affirmative action inquiries to the Affumative Action Office, The Pennsylvania State University,201 Willard Building, University Park, PA 16802-2801;(814) 863-0471.

This publication is available in alternative media on request.

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TABLE OF CONTENTS i

EaSa P REFA CE - M . H . Vo th . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

v 1

I . INTR ODU CTION - M. H. Vo th . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

II. PERS ONNEL - T. L. Flin c h ba u g h ............ . .. .. .. .... ... .. .. .... .. . .... . . . . .. . .... ... . . 3 III. REACFOR OPERATIONS - T. L. Flinchbau gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 IV. GAMMA IRRADIATION FACILITY - C. C. Davison . . . .. . . .. ...... .. ... ..... . . . .. . I1 V. EDUCATION AND TRAINING - T. L. Flinchbaugh, C. C. Davison ..... .. ........ 13 VI. NEUTRON BEAM LABORATORY - R. Gould . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 VII. RADIONUCLEAR APPLICATIONS LABORATORY-T. H.Daubenspeck ........ 21 VIIL LOW LEVEL RADIATION MONITORING LABORATORY - J. Lebiedzik ......... 23 IX. ANGULAR CORRELATIONS LABORATORY - G. L. Catchen ..................... 25 X. RADIATION SCIENCE AND ENGINEERING CENTER RESEARCH UTILIZATION - T. L. Flinchbau gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 A. Penn State University Research Utilizing the Facilities of the Penn State Radiation Science and Engineering Center . ...................... 29 B. Other Universities, Organizations and Companies Utilizing the Facilities of the Penn State Radiation Science and En gineerin g Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 APPENDIX A. Faculty, Staff, Students, and Industries Utilizing the Facilities of the Penn State Radiation Science and Engineering Center - T. L.

Fli n c h ba u gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 APPENDIX B. Formal G roup Tours - L. D. Brazee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 iii

. _ ._ .. _ _ . . . _ . _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . . . . . ~ . . . . _ _ . . _ . _._.._ _.

1 TABLES 1

Table Eagn 1 1 Personnel..................................................................................... 4 2 Reac tor Ope ra tio n D a t a . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . 9 3 Reactor Utilization Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4 Cobalt-60 Utilization Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 5 College and High School Groups . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 FIGURES Figure East 1 Organ i zation Chart . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 IV

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l PREFACE Administrative responsibility for the Radiation Science and Engineering Center (RSEC) resides in the Department of Nuclear Engineering in the College of Engineering. Overall responsibility for the reactor license resides with the Senior Vice President for Research and Graduate Education.

The reactor and associated laboratories are available to all Penn State colleges for education and l

research programs. In addition, the facility is made available to assist other educational 4

institutions, government agencies and industries having common and compatible needs and objectives, providing services that are essential in meeting research, development, education and training needs.

The Fortieth Annual Progress Repon (July 1994 through June 1995) of the operadon of The Pennsylvania State University Radiation Science and Engineering Center is submitted in accordance with the requirements of Contract DE-AC07-94ID-13223 between the United States Department of Energy and Lockheed Idaho Technologies Company (LITCO), and their Subcontract C88-101857 with The Pennsylvania State University. This report also provides the University admmistration with a summary of the utilization of the facility for the past year.

Numerous individuals are to be recognized and thanked for their dedication and committment in this report, especially Terry Flinchbaugh who edited the report and Lisa Brazee who typed it.

Special thanks are extended to those responsible for the individual sections as listed in the Table of Contents and to the individual facility users whose research summaries are compiled in Section X.

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I. INTRODUCTION .

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August 15,1995, marked the fortieth anniversary of the initial criticality of the Penn State l Breazeale Reactor (PSBR), making it the longest operating university research reactor in the i nation. Despite its early beginnings, efforts are made to continually upgrade the entire Radiation l l

Science and Engineering Center (RSEC) to a state-of-the-art facility capable of cutting edge research. This report tabulates the number of users, experiments performed, and hours of operation along with summaries of the nature of work performed, and its significance. Highlights l among the year's accomplishments are discussed below .

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. Three visiting scientists performed work at the RSEC. Ms. Faridah Idris, an IAEA Fellow, studied ways to increase the power level of the Malaysian TRIGA reactor. Dr.

Evgueni Shabalin, a SABIT Intern, collaborated in cold neutron research techniques while !

investigating new applications for research reactors, specifically for his facility in Russia. j Dr. Andrea Paesano of Brazil is performing research on materials in collaboration with Drs. j Catchen and Motta.

. Dr. Edwards and his students continue to make major contributions in the field of advanced controls. They hosted a successful seminar to disseminate their research findings and ,

l prepare to host the 1996 American Nuclear Society topical meeting on Nuclear Plant Instrumentation. Control and Human Interface Technolocv at Penn State.

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- Neutron radiography is being used for a new application by Dr. Prescott and his students l

as they investigate transport phenomena during the solidification of alloys.

A staff program has commenced in the hot cell facility to monitor the long term performance ofirradiated high nickel steels under strain, integrating the measurements with Dr. Motta's research in the performance of irradiated metals. ,

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+ The spatial transient behavior of the TRIGA reactor is being used by Dr. Feltus and her students to evaluate the fidelity of state-of-the-art power reactor computer models. Similar data was also provided to the Nuclear Regulatory Commission to simulate a classic rod i drop accident or rod ejection accident as a benchmark for deliberations in their license l review process.

Preliminary experiments on cold neutron studies commenced with the assistance of Dr.

Shabalin. Work continues on Dr. Sokol's cold neutron irradiation facility in support of improved performance of the Intense Pulsed Neutron Source at Argonne National Laboratory. l

A number of facility enhancements were made to improve the performance and capabilities l of the RSEC. A work station provided as part of a DOE grant was installed and made operational for improved capability of analytical computations. A procedure was developed and demonstrated to implement the movable core feature of the bridge modification. A new Cobalt-60 dry irradiator was installed, increasing the effective age of our gamma irradiation capability by 15 years.

- Operations in support of these accomplishments proceeded with no violations cited in NRC inspection reports. One Reactor Operator and two Senior Reactor Operator license exams were administered by the NRC with all three candidates passing.

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- II. PERSONNEL Maurice Peagler was promoted from Environmental Analyst to Research Support Technician III effective July 1,1994 in the LLRML Maurice resigned his position effective August 1,1994 to accept a health physics assistant position with the university. In anticipation of Maurice's departure, Jana 12biedzik was hired as a wage payroll employee effective July 1,1994 and assumed Maurice's position on August 1,1994. l Mac Bryan was promoted from Assistant Research Engineer to Reactor Supervisor / Engineer effective l March 1,1995. I 1

Lisa Brazee, Staff Assistant V, took a personalleave of absence from June 1,1995 to June 30,1995.

Carol Houtz was hired as a wage payroll secretary during that time.

Several wage payroll personnel provided support during the year. Scott Anderson, Mary Imu Gougar, !

I Joy Moncil, Chris Norman, Lois Lunetta and Danielle Page provided suppon in the educational programs area. Scott Anderson and Jeff Simons provided clerical support. Brian Marazi provided support to the j supervisor of facility services.

Dhushy Sathianathan (Assistant Professor, Engineering Graphics) was appointed to serve on the Penn State Reactor Safeguards Committee (PSRSC) from August 1,1994 to September 30,1995 while committee member Paul Sokol was on sabbatical leave. On January 1,1995, Mike Slobodien (Radiological Controls Director, General Public Utilities) left the committee after serving the maximum two terms allowed by the committee charter. His replacement was Patrick J. Donnachie, Jr. (Health Physicist, General Public Utilites). .

1 3

TABLE I ,

Personnel Faculty and Staff Iitle

- P. G. Boyle Reactor Supervisor / Nuclear Education Specialist L. D. Brazee Staff Assistant V

- M. E. Bryan Reactor Supervisor / Engineer G. L. Catchen Associate Professor

- T. Daubenspeck Reactor Supervisor / Reactor Utilization Specialist

- C. C. Davison Reactor Supervisor / Nuclear Education Specialist

- T. L. Flinchbaugh Operations and Training Manager M. P. Grieb Engineering Aide R. Gould Research Assistant

- D. E. Hughes Senior Research Assistant / Manager of Engineering Services W. A. Jester Professor C. J. Kowalske Administrative Assistant J.Lebiedzik Research Support Technician III

- A. J. McLellan Reactor OperatorIntern

- D. R. Miller Reactor OperatorIntem M. Q. Peagler (resigned) Research Support Technician III K. E. Rudy Operational Suppon Services Supervisor P. J. Stauffer Staff Assistant VII

- M. H. Voth Associate Professor / Director Licensed Operator

- Licensed Senior Operator Technical Service Staff J. E. Armstrong Mechanic-Experimental and Maintenance R. L. Eaken Machininst A Wage Payroll S. Anderson M. Gougar C. Houtz D. Page L Lunetta B. Marazi J. Moncil C. Norman J. Simons 4

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Penn State Reactor Safec_uards Committee

- P. J. Donnachie, Jr. Health Physicist, General Public Utilities l

E. W.Figard Supervisor of Maintenance, Pennsylvania Power and Light Susquehanna Steam Electric Station i

l R. W. Granlund Health Physicist,Intercollege Research Programs and Facilities, Penn State D. E. Hughes Senior Research Assistant, Penn State Radiation Science and 1 I

l Engineering Center Manager, Product Licensing, Westinghouse j P. Loftus J. H. Mahaffy Assistant Professor, Nuclear Engineering, Penn State G. E. Robinson Chairman, Associate Professor, Nuclear Engineering, Penn State

- - D. Sathianathan Assistant Professor, Engineering Graphics, Penn State

M. J. Slobodien Radiological Controls Director, General Public Utilities P.E.Sokol Associate Professor, Physics, Penn State M. H. Voth Ex officio, Director, Penn State Radiation Science and Engineering Center 1 I

W. F. Witzig Professor, Nuclear Engineering, Penn State (retired) l

Served through January 1,1995 l

- Appointed January 1,1995

- - Temporary appointment from August 1,1994 to September 30,1995 during P. E. Sokol's

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DIRECTOR i

MANAGER OF MANAGER OF STAFF OPERA" DONS ENGINEERING -

ASSISTANT Vil AND VIAINING SERVICES ,

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MACilINIST A AND MAINTENANCE REACTOR MECHANIC OPERATOR i i

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WORK STUDY FIGURE I RSEC Organization Chalt aS Of 6/30/95

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. III. REACTOR OPERATIONS Research reactor operation began at Penn State in 1955. In December of 1965 the original core, which operated at a maximum power level of 200 KW, was replaced by a more advanced 1 TRIGA core, capable of operation at 1000 KW. The present core may also be operated in a pulse fashion in which the power levelis suddenly increased from less than 1 KW to up to 2000 KW for short (milliseconds) periods of time. TRIG A stands for Training, Research, Isotope Production, built by General Atomic Company.

Utilization of the PSBR falls into three major categories:

Educational utilization is primarily in the form oflaboratory classes conducted for graduate and l undergraduate degree candidates and numerous high school science groups. These classes wil!

vary from the irradiation and analysis of a sample to the calibration of a reactor control rod.

Research accounts for a large portion of reactor time which involves Radionuclear Applications, Neutron Radiography, a myriad of research programs by faculty and graduate students throughout the University and various applications by the industrial sector.

Trainine programs for Reactor Operators and Reactor Supervisors are offered and can be tailored to meet the needs of the participants. Individuals taking part in these programs fallinto such categories as PSBR reactor staff and power plant operating personnel. '

The PSBR core, containing about 7.5 pounds of Uranium-235,in a non-weapons form, is operated at a depth of approximately 18 feet in a pool of demineralized water. The water provides the needed shielding and cooling for the operation of the reactor. It is relatively simple to expose a sample by positioning it in the vicinity of the reactor at a point where it will receive the desired radiation dose. A variety of fixtures andjigs are available for such positioning. Various containers and irradiation tubes can be used to keep samples dry. Three pneumatic transfer systems with different neutron levels offer additional possibilities. Core rotational, east-west, and north-south movements provide flexibility in positioning the core against experimental apparatus.

In normal steady state operation at 1000 kilowatts, the thermal neutron flux available varies from approximately 1 x 1013 n/cm 2/sec at the edge of the core to approximately 3 x 1013 n/c m2fsee in the central region of the core.

When using the pulse mode of operation, the peak flux for a maximum pulse is approximately 6 x 1016 n/cm2/sec with a pulse width of 15 msec at 1/2 maximum.

Support facilities include a machine shop, electronic shop, laboratory space and fume hoods.

STATISTICAL ANALYSIS Tables 2 and 3 list Reactor Operation Data and Reactor Utilization Data-Shift Averages, respectively, for the past three years. In table 2, the Critical time is a summation of the hours the reactor was operating at some power level. The Suberitical time is the total hours that the reactor key and console instrumentation were on and under observation,less the Critical time. Suberitical time reflects experiment set-up time and time spent approaching reactor criticality. Fuel movement hours reflect the fact that there were minimal fuel movements made this year.

The Number of Pulses reflects demands of undergraduate labs, researchers and reactor operator training programs. Square waves are used primarily for demonstration purposes for public groups touring the facility, researchers and reactor operator training programs.

The number of Scrams Planned as Part of Experiments reflects experimenter needs. One Unplanned Scram Resulting from Personnel Action occurred when the console sensed both bay 7

i exhaust fans were off because of an operator switching error. The Unplanned Scrams Resulting '

i from Abnormal System Operation were because of: 1) two N-16 pump failures from thermal overloads,2) loss of transient rod air supply because of a maintenance error,3) elevated Argon-41

in pneumatic transfer system because of air leaks and,4) normal operating fuel temperature was

too close to fuel temperature scram set point.

4 Table 3, Part A, Reactor Usage, indicates Hours Critical and Hours Suberitical, and also Hours Shutdown such as for instruction or experimental setup. Occasionally a component failure prohibits reactor operation. The necessary repair time is included in Reactor Usage as Reactor Not Available to reflect total reactor utilization on a shift basis.

Part B gives a breakdown of the Type of Usage in Hours. The Nuclear Engineering Department and/or the Reactor Facility receives compensation for Industrial Research and Service. <

Umversity Research and Service includes both funded and non-funded research, for Penn State and other universities. The Instruction and Training category includes all formal university classes involving the reactor, experiments for other university and high school groups, demonstrations for tour groups and in-house reactor operator training.

Part C statistics, Users / Experimenters, reflect the number of users, samples and experimenters per shift. Part D shows the number of eight hour shifts for each year.

INSPECTIONS AND AUDITS During October of 1994, Stephen Miller, Deputy Director, AFRRI Triga Reactor Facility, conducted an audit of the PSBR. This fulfilled a requirement of the Penn State Reactor Safeguards Committee charter as described in the PSBR Technical Specifications. The reactor staff has implemented changes suggested by that report, all of which exceed NRC requirements.

During November of 1994, a NRC routine inspection was conducted of activities authorized by the broad byproduct material license (37-185-04), the Cobalt-60 facility license (37-185-05), the self-shielded irradiator license (37-185-06) and the SNM 95 license. No items of non-compliance were identified for reactor activities.

During April of 1995, a NRC routine inspection was conducted of activities authorized by the special nuclear materials license SNM-95 and the R-2 reactor license. No items of non-compliance were identified.

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I Reactor Operation Data July 1,1992 - June 30,1995 1

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i A. Hours of Reactor Operation

1. Critical 635 601 561

2. Suberitical 404 362 401 1

3. FuelMovement 8 31 27 4

B. Number of Pulses 77 48 131 j

C. Number of Square Waves 60 68 89 l l

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E. Grams U-235 Consumed 20 20 13 i i

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TABLE 3 ,

Reactor Utilization Data Shift Averages July 1,1992 - June 30,1995 22-21 23:.2.4 24:25.

A. ReactorUsage

1. Hours Critical 2.5 2.4 2.2

2. Hours Suberitical 1.6 1.4 1.6

3. Hours Shutdown 1.6 1.5 1.9

4. ReactorNot Available QJ. QJi Q_.

TOTAL HOURS PER SHIFT 5.8 5.9 5.6 B. Type of Usage - Hours

1. Industrial Research and Service 0.9' O.6 0.7

2. University Research and Service 2.3 2.1 1.5

3. Instruction andTraining 1.1 1.4 1.3

4. Calibration and Maintenance 1.4 1.8 2

5. FuelHandling 0.1 0.1 0.1 C. Users / Experiments

1. Number of Users 2.7 2.3 2.4

2. Pneumatic Transfer Samples 0.7 0.6 0.5

3. Total Number of Samples 3.1 2.3 2.4

4. Sample Hours 2.7 2.9 2.4 D. Numberof 8 Hour Shifts 250 254 255 10

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- IV. GAMMA IRRADIATION FACILITY The University, in March of 1956, purchased 23,600 curies of Cobalt-60 in the form of stainless steel clad source rods to provide a pure source of gamma rays. In November of 1971, the University obtained from the Natick Laboratories,63,537 curies of Cobalt-60 in the form of aluminum clad source rods. These source rods have decayed through several half-lives, leaving a July 1,1995 approximate total of 3300 curies.

In this facility, the sources are stored and used in a pool 16 feet by 10 feet, filled with 16 feet of demineralized water. The water provides a shield which is readily worked through and allows great flexibility in using the sources. Due to the number of rods and size of the pool,it is possible to set up several irradiators at a time to vary the size of the sample that can be irradiated, or vary the dose rate. Experiments in a dry environment are possible by use of either a vertical tube or by a diving bell type apparatus.

The Cobalt-60 facility is designed with a large amount of working space around the pool and has two laboratories with work benches and the usual utilities.

Maximum exposure rates of 121 KR/Hr in a 3" ID tube and 70 KR/Hr in a 6" ID tube are available as of July 1,1995.

A GammaCell 220 irradiator is being donated to Penn State by the David Sarnoff Research Center in Princeton, New Jersey. The transfer of the device is scheduled for July 1995. This device has a dose rate considerably higher than that currently available in the RSEC pool facility or with another irradiator on campus. It will take approximately fifteen years for the dose rate on the GammaCell 220 to decay to the current RSEC dose rates available, thus providing a fifteen year extension of usable irradiation capability.

Table 4 compares the past three years' utilization of the Cobalt-60 facility in terms of time, numbers and daily averages.

11

I TABLE 4 .

Cobalt-60 Uti!ization Data l July 1,1992 - June 30,1995 l i

22:93 9.1-2.4 23:21 A. Time Involved (Hours)

1. Set-Up Time 171 130 90

2. Total Sample Hours 10,975 6,547 2694 I

B. Numbers Involved

1. Samples Run 684 510 677

2. Different Experimenters 35 36 39

3. Configurations Used 4 3 4 C. PerDay Averages

1. Experimenters 0.8 0.54 0.59

2. Samples 2.75 2.05 2.72 P

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- V, EDUCATION AND TRAINING During the past year, the Penn State RSEC was used for a variety of educational services; in-house training, formal laboratory courses and many continuing education programs and tours.

The RSEC operating staff has maintained reactor operator competence and safe facility operation through training and requalification. In-house reactor operator requalification during November of 1994 consisted of an oral examination on abnormal and emergency procedures given by P. G. Boyle and an operating test given by T. L. Flinchbaugh. A written exam was administered by K. E. Rudy.

Staff member Thierry Daubenspeck and operator intem Alexander McLellan participated in the reactor operator training program during 1994 and were granted their senior reactor operator licenses by the NRC in September 1994. Staff member Mark Grieb participated in the reactor operator traming program during 1994 and 1995 and was granted a reactor operator's license by the NRC in June 1995.

The ninth session of the Pennsylvania Govemor's School for Agricultural Sciences was held at Penn State's University Park campus during the summer of 1994. Sixty-four high school scholars participated in the five week program at Penn State. The Governor's School for Agricultural Sciences includes introduction and experience in many different agricultural disciplines. There are several parts of the program which are considered " core courses". The core courses are fundamentalinstruenon given to all participants. " Radioisotope Applications in Agricultural Research" is one of the core courses in the program. The program was conducted at Penn State's RSEC by Candace Davison along with Mary Lou Gougar and nuclear engineering student Scott Anderson. Maurice Peagler, Supervisor of the Low Level Radiation Monitoring Laboratory provided a session on detection of radiation in the environment including radon gas. The students i performed a series of experiments focusing on the fundamentals of radiation interaction and principles of radioisotope applications. These experiments included a demonstration of a cloud chamber; penetrating ability of alpha, beta and gamma radiation; half-life calculation and gamma ray spectroscopy. The importance of statistics in taking data and other applications of radioactive materials in research were discussed. The students were also given a tour of the reactor facility.

The Nuclear Concepts and Technological Issues Institute (NCTII) was conducted from July 11-22,1994 at the University Park campus. The Nuclear Concepts program was designed to prepare secondary science educators to teach the basics of nuclear science, radiation, and applications and is offered as a special topics course in nuclear engineering. Twenty-three secondary science teachers participated in the program. The program was developed in 1970 and has been conducted every summer since that time. The 1994 program differed in that it was a two-week applications course. This change provided an intense course in a short period of time.

Support for the program included funding through a grant from the National Science Foundation for ten teachers. Sponsorship of the other thirteen participants was provided by Baltimore Gas and Electric Company, Chem-Nuclear Systems Inc., Edison Electric Institute, General Electric Company, Gilbert Associates, GPU Nuclear Corporation, Oxford Instruments Inc. and various school districts. Materials were obtained from the U.S. Department of Energy, USCEA, ANS and other sources. General Electric Company donated many educational materials to the course including a full size Chart of the Nuclides and booklet to each participant.

The institute was coordinated by Candace Davison and was conducted through Penn State's Continuing Education Office. Joseph Bonner presented the fundamental nuclear science lectures.

Other instruction was provided by Nuclear Engineering department personnel and Rodger Granlund, University Health Physicist. Guest speakers from government, research, and industry provided expertise for the technical and issues sessions. Guest speakers included Mr. Alan Brinser from Chem-Nuclear Systems Inc., Mr. John Redding from General Electric Company, Mr. Chris Davis from Westinghouse Electric Corporation, and Dr. Frank Olney from Radiology 13

Associates. Several Alumni from the course discussed implementation of nuclear science into ,

their curriculum.

Laboratory experiments are an important aspect of the institute as the teachers are able to have hands-on experience with radioactive materials. The laboratories were conducted at the RSEC under the direction of the RSEC and Health Physics personnel. Guy Anderson, a chemistry teacher from the Bald Eagle Area School District was in charge of the laboratories. The laboratory experiments and demonstrations included: characteristics of ionizing radiation, neutron acuvanon of Indium, complex decay of Silver-110 and Silver-108, neutron radiography, and the approach to critical experiment. Discussion and problem solving sessions along with a field trip to either Three Mile Island Unit 1 (a PWR) or Susquehanna Steam Electric Station (a BWR) were included in the schedule.

Evaluations from the panicipants were very positive concerning the course. As in previous institutes, the panicipants in NCTII were encouraged to return with their students for a day of experiments at the RSEC. Two follow-up programs were conducted during October in the Harrisburg area. The first program on the Medical Applications of Radiation and Radiosotopes was conducted at the Hershey Medical Center on Friday, October 14,1994. The program included a variety of speakers who discussed their research and how radioisotopes are used. An overview of medical imaging and a tour of the Low-level waste storage facility was also included for the participants. A program on Fundamental Panicles and Interactions was conducted on Saturday, October 15,1994 at the Penn State Harrisburg Campus. Dr. Ted Zalesckiewize of the University of Pittsburgh at Greensburg conducted the program and utilized a hypercard computer program and slides to introduce the topic.

The University Reactor Sharing Program is sponsored by the U.S. Depanment of Energy.

The purpose of this program is to increase the availability of the university nuclear reactor facilities to non-reactor owning colleges and universities. The main objectives of the University Reactor Sharing program are to strengthen nuclear science and engineering instruction and to provide research opponunities for other educational institutions including universities, colleges, junior l colleges, technical schools and high schools. l A total of 842 students and teachers from 35 high schools and 2 colleges came to the RSEC for i experiments and instruction. (see Table 5). Candace Davison and Lois Lunetta were the main l instructors for the program. Other instruction and technical assistance for experiments were I provided by Thierry Daubenspeck, Jana Lebiedzik, Roben Gould and Alex McClellan.

The RSEC staff and facilities provided educational opponunities along with a tour for student and teacher workshops, many of which were conducted as pan of a larger program on campus through Penn State Continuing Education Programs. The student programs included: the Kodak BEST (Business, Science, Engineering and Technology) program, the High School Summer Intemship, the Civil Engineering VEC tour program and the Upward Bound program for minority and "at risk" students. Twenty four teachers from the Harrisburg area participated in a full day of experiments as part of the course " Exploring the Nuclear Option". Thiny-six teachers from the Enter-2000 program received instruction and toured the facility to learn more about nuclear energy and related careers.

In addition to the full or half-day programs with experiments, educational tours were conducted for students, teachers, and the general public. All groups, including the reactor sharing groups, who toured the facility are listed in Appendix B. The RSEC operating staff and Nuclear Engineering Department conducted 122 tours for 2,518 persons.

1 14

1 The RSEC was used by several Nuclear Engineering and other courses during the year.

Semester Course Instructor Students Hours Summer 1994 NucE 497B-Nuclear Concepts C. C. Davison 23 4 Summer 1994 NucE 444 Nuclear Reactor Operations D. E. Hughes 3 12 Fall 1994 NucE 451-Reactor Physics R. M. Edwards 23 67 W. A. Jester Fall 1994 Food Science 313-Process Plant Production R. B. Beelman 21 2 Spring 1995 NucE 444-Nuclear Reactor Operations D. E. Hughes 8 32 Spring 1995 NucE 450-Radiation Detection and M. H. Voth 23 66 Measurement W. A. Jester Spring 1995 NucE 401-Introduction to Nuclear E. S. Klevans 8 4 '

I Engineering Summer 1995 SciEd 497-Exploring the Nuclear Option C. C. Davison 24 4 In January and February of 1995, a total of 42 University Police Services personnel were

- given training and retraining sessions by C. C. Davison at the RSEC to ensure familiarity with the facilities and to meet Nuclear Regulatory Commission requirements.

During the 1994-95 academic year, one IAEA fellow and two other visiting professors were hosted by the RSEC and Nuclear Engineering Department.

Ms. Faridah Idris, Research Officer for the reactor at the Malaysian Institute for Nuclear Technology Research in Kajank, Malaysia, arrived in January 1995 for a four month visit. She was sponsored as an International Atomic Energy Agency Fellow. Her mission was to study safety analysis technique in preparation for upgrading their one megawatt TRIGA to two ,

megawatts. In addition to working with the RSEC staff, she worked closely with Dr. Haghighat in applying Monte Carlo techniques and using the MCNP code for power distribution and shielding calculation.

Dr. Evgueni Shabalin of the Frank Laboratory of Neutron Physics, Joint Institute for Nuclear Research in Dubna, Russia, arrived in May 1995 for a five-month visit. He is an intem in the Special American Business Intemship Training Program (S ABIT) with Penn State, funded by the U.S. Department of Commerce. The purpose of Dr. Shabalin's visit is to receive training in commercial aspects of operation of a research reactor. He has also furnished technical expertise to the reactor staff and the physics department as they design a Cold Neutron Irradiation Facility.

Dr. Andrea Paesano is currently Assistant Professor of Paysie at the State University of Marings, Brazil. He received both his B.S. and Ph.D. in Physics from the Federal University of Rio Grande do Sul, Brazil. He will be here for at least one year in the context of a collaboration between Penn State and the Federal University of Rio Grande do Sul to study defects in intermetallic compounds of the Zr-Fe system using nuclear spectroscopy, namely, perturbed-angular correlation, M6ssbauer-effect, and positron-lifetime spectrocopies. He is a specialist in multilayer thin films and M6ssbauer effect Spectroscopy, and he is working with Dr. Arthur T.

Motta and Dr. Gary L. Catchen.

15

TABLE 5 .

University Reactor Sharing Program College and High School Groups 1994-1995 Academic Year Those who came to the RSEC for experiments received instruction on the basics of radiation and nuclear energy and received a tour of the facility. All groups either conducted the approach to critical experiment or saw a demonstration with the reactor. Most groups also did one of the other experiments listed below.

Gamma Ray Spectroscopy

_) Neutron Activation and Complex Decay of Silver Barium 137m Decay or Silver Decay Neutron Activation Analysis Relative Stopping Powers for ct, and yin Air, Aluminum and Lead Number of Month School and Teacher Students & Teachers October 4 Harrisburg Academy 29 Barbara Thrush 7 Harmony HS 23 Chad Weiwiora 7 IU-9 50 Karen Kelly November 9 Glendale HS 53 Paul Conway 14 State College HS 8 Jan Hildenbrandt 16 IU-9 7 JoAnn Castle 18 Williamson HS 31 Bob Burket 21 Greensburg-Salem HS 39 Cheryl Harper December 1 Lock Haven University 4 15 Dubois HS Physics 3 16 Carlisle HS 70 Robert Barrick March 1 Germantown Friends 10 Gary Garber 6 Redland HS 19 Robert Lighty 13 Berwick HS 14 Jeff Snyder, Dave Dobler 15 Bermudian Springs HS 16 Jeanne Sucht 20 Daniel Boone HS 13 Larry Tobias 22 Eastern Lebanon HS 8 Richard Schwalm 22 Peters Township HS 18 Walter Jennings 28 State College HS 42 ,

Tod McPherson 16 I

- TABLE 5 University Reactor Sharing Program College and High School Groups 1994-1995 Academic Year (Continued)

Number of Month School and Teacher Students & Teachers March 29 Cumberland Valley HS 10 Albert Thompson 31 Jersey Shore HS 10 Gary Heyd April 5 Loyalsock HS 19 John Gennan 5 Bradford HS 35 10 Portage HS 8 Hennan Carl 12 Harborcreek HS 11 Dave Sidelinger 19 Carmichaels HS 29 Pat Gibson 21 East Stroudsburg HS 11 Heather Skeldon 27 Franklin Area HS 22 Beth Green 28 Ridgway HS 21 Ernest Koos 28 St. Mary's HS 26 William Scilingo May 1 Northern Bedford HS 19 Keith Little 2 Indiana University of PA 9 Frank Fazio 4 Marion Center HS 10 John Petrosky 5 Camp HillHS 10 Philipp Schmelzle 8 Westmont Hilltop HS 13 Tom Moore 10 Somerset HS 22 Jon Critchfield .

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12 1

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Larry Greico 23 State College HS 18 Marguerite Ciolkosz 1 Twin Valley Middle School 34 j 29 Doug Mountz l

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VL NEUTRON BEAM LABORATORY The Neutron Beam Laboratory (NBL) is one of the experimental facilities that is a part of the RSEC. A well collimated beam of neutrons, thermalized by a D20 thermal column, is passed into the NBL for use in non-destructive testing and evaluation. Work now being done utilizes a Real Time Neutron Image Intensifier, by Precise Optics, Inc., for real time radiography. The beam is also being used for static neutron radiography and neutron attenuation studies, and flash radiography utilizing pulsing. New equipment is available to digitize the real time radiography images for image processing. A photographic laboratory facilitates the development and analysis of static neutron radiographs.

The NBL was established partially with funds from the U.S. Department of Energy (DOE) with matching funds from the University to:

1. Educace students and the public on an important use of neutrons from a research reactor,

2. Establish a demonstration center, " Neutrons in Action," to show that their use is beneficial to mankind, and

3. Expand the use of neutron radiography in research, both as a tool for improving the development of U.S. industrial products and to develop new information in other fields of science and engineering.

Bettis Atomic Power Laboratory purchased time to utilize the neutron beam laboratoy to evaluate two phase flow during the past year and the project continues. In association with this project, Bettis arranged to borrow a second image intensifier which allows different camera arrangements and will enhance utilization. We continue to have funded service work utilizing the beam to measure neutron attenuation of boraflex materials that have seen service in fuel storage pools.

DOE and University matching funds will be used to build a new D20 thermal column to enhance the neutron beam in the NBL. It is expected that at least an order of magnitude increase in beam flux will result.

Dr. Sokol of the Penn State Physics Department, in conjunction with Argonne National Laboratory,is designing a Cold Neutron Irradiation Facility (CNIF) to study the moderating properties of solid methane at low temperatures. This project will initially benefit from the versatility of the movable core and in later stages of the project will benefit from the ability to open another beam port for use.

New equipment for digitizing and enhancing the real timeradiography images has been purchased using DOE and University matching funds. This system will allow image processing for both single frames and real time sequences of the image.

Dr. Prescott of the Penn State Mechanical Engineering Department is using this facility to examine a gallium - indium alloy with static neutron radiographs.

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0 VII. RADIONUCLEAR APPLICATIONS LABORATORY I

Personnel of the Radionuclear Applications Laboratory provide consulting and technical '

assistance to those University research personnel who wish to utilize some type of radionuclear technique in their research. De majority of these research projects involve neutron activation, but the staffis able to provide services in radioactive tracer techmques, radiation gauging, radiation processing, and isotope production for laboratory, radionuclear medicine and industrial use. J Laboratory personnel continue to supply support for the operation of the RSEC doing analyses of I

water, air monitor filters, and other samples.

Approximately 175 irradiations of semiconductors were performed during the past year.

Laboratory personnel prepared each set of devices for irradiation, calculated the 1-MeV Silicon Equivalent fluence received, and determined the radioisotopes produced in the devices.

He facility performed 19 isotope production runs for industrial use during the past year. The isotopes produced included 2 Na-24 runs,12 Br-82 runs, and 5 Ar-41 runs.

Penn State students and faculty members continue to use the services offered by the radionuclear applications laboratory. During the past year, analysis work was performed for graduate and undergraduate students in the Nuclear Engineering and Materials Science department.

Analysis work has also been performed to support various projects which will be started shortly.

The Penn State Radionuclear Applications Laboratory has continued to be involved with the Armed Forces Radiobiology Research Institute in activation analysis work of the St. Mary's City, Maryland site. NAA was used to investigate the arsenic concentrations found in hair samples. In addition to the St. Marys City work, Penn State has also been involved with AFRRIin a preliminary study to determine the feasibility of using Dysprosium as a tracer material for bomb blasts.

The EG&G Ortec Omnigam neutron activation analysis software is being used for routine analyses; however, additional work is still needed to make better use of the software. An in-house inter comparison program has been initiated with the LLRML to verify counting procedures.

The benchmarking of the reactor neutron energy spectrum following ASTM procedures is complete. Results from two different independent analyses have been received and the final report draft has been written. This draft is currently being reviewed before a final report is submitted.

Activation foils have been irradiated and analyzed for the D2 O tank to determine the neutron flux over the axial length of this fixture. This information will be used for the design of the new D 2O tank. Activation foils have also been irradiated and analyzed for three core locations: the central thimble, the coreface, and the R1 position. These irradiations were performed to determine the flux distribution throughout the core.

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VIII. LOW LEVEL RADIATION MONITORING LABORATORY The laboratory continues to participate in the Environmental Protection Agency's (EPA)

Environmental Radioactivity Laboratory Intercomparison Studies Program for gross alpha, gross beta, radium-226, radium 228, strontium 89, strontium 90, and other gamma emitters as part of the laboratory quality assurance program and to maintain staff proficiency.

The laboratory provides analyses for gross alpha and gross beta activity in reactor pool water, cobalt-60 pool water, and the reactor secondary heat exchanger water. Gamma spectroscopy is performed on these samples if alpha or beta action level limits are exceeded. Tritium content in the reactor pool water and the D2O tank heavy water is determined on a monthly basis. Gamma spectroscopy analyses are performed on a quarterly basis on the reactor pool water and on a water sample from the 6000 gallon holding tank for pool make up water.

The LLRML is maintaining its DER certification via the EPA National Radon Measurement i Proficiency Program to test for radon in air using activated charcoal canisters and both short and long tenn electret ionization chamber detectors. Dr. William Jester, the laboratory's technical supervisor was re-certified this year via the RMP exam for radon test operators and the laboratory I

under his leadership is listed in the EPA posting of certified radon testing labs / individuals.

Ms. Harsha Senaratne, a volunteer part time staff member, is working on the calibration of new diffusion barrier charcoal radon monitoring canisters purchased to replace the existing open face l canisters currently in use. Radon in water analysis, and tritium analysis of ground water are also l provided to laboratories involved in water testing as well as individual clients on a regular basis.

Certification for the analysis of radon in water has been proposed but not yet required by the EPA.

A major focus of the laboratory is on the gross alpha, gross beta, and gamma spectroscopy analyses of zirconia materials used in producing femoral heads in hip-joint replacement pieces.

This service work is required by Howmedica of New Jersey with its zirconia supplier, Morgan Matroc Limited, Warwickshire, England.

The uranium-thorium content in enriched soils was determined by gamma spectroscopy analyses for North American Refractories and their supplier, Muscle Shoals Minerals,Inc., and for Control for Environmental Pollution, Inc. The LLRML's results of analyses were found to be the i most reliable to the NARCO project. The further shipment of samples will depend on the evaluation of all the data from all the testing laboratories.

Cesium-134 and cesium-137 concentrations in several soil samples were determined by gamma spectroscopy for the Forest Resource Laboratory, and a new set of samples is expected to be analyzed during the next fiscal year.

A two gram speciment of sand / soil collected by professor Witzig at the site of the first A-bomb testing in Almagordo, New Mexico was analyzed using gamma spectroscopy to establish the presence of plutonium in the sample. The daughter of plutonium-241 (americium-241) was detected in the soil sample.

Analyses to cenify the 9c' Lithium enrichment for enriched LiOH samples continue for Isotec Incorporated of Ohio. The higher lithium enrichments are important in the nuclear industry to minimize tritium production in pressurized water reactors.

Dr. William Jester's involvement with Dr. Art Rose, Professor of Geochemistry,in utilizing alpha spectroscopy analyses of uranium, thorium, and radium alpha emitters via ions plated on nickel disks should result in the laboratory's capability to analyze soil, silt and clay samples for these elements.

Nancy K. Umisedo, visiting staff member of Saint Paul University in Brazil,is working under the direction of Dr. Jester and Rodger Granlund. She is evaluating environmental gamma radiation 23

data from previous years and taking measurements around the Breazeale Nuclear Reactor using

TLD's and EICs.

Dr. Jester's nuclear engineering graduate student Uditha Senaratne will be working on a project to separate and quantify strontium 89 and strontium-90 in reactor ion exchange resin samples. He is using the Dionex Dx 100 lon Chromatograph in the reactor facility to separate the strontium ,

isotopes from ion exchanger resin extracts. The LKB Wallac Spectral 1219 scintillation counter l unit at the LLRML will be used to count these separated strontium samples.

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j IX. THE ANGULAR CORRELATIONS LABORATORY 2

The Angular Correlations Laboratory has been in operation for approximately 9 years. The laboratory, which is located in Room 116 and Room 4 of the RSEC, is under the direction of Professor Gary L Catchen. The laboratory contains three spectrometers for making Perturbed Angular Correlation (PAC) measurements. One apparatus, which has been in operation for seven

! years, measures four coincidences concurrently using cesium fluoride detectors. A second spectrometer was acquired three years ago, and it measures four coincidences concurrently using barium fluoride detectors. A third spectrometer was set up last year to accommodate the increased demand for measurement capability. The detectors and electronics provide a nominal time resolution of 1 nsec FWHM, which places the measurements at the state-of-the-an in the field of Perturbed Angular Correlation Spectroscopy.

! Currently, Penn State has a unique research program that uses PAC Spectroscopy to characterize technologically imponant electrical and optical materials. This program represents the synthesis of ideas from two traditionally very different branches of chemistry, materials chemistry and nuclear chemistry. Although the scientific questions are germane to the field of materials chemistry, the PAC technique and its associated theoretical basis have been pan of the fields of 4 nuclear chemistry and radiochemistry for several decades. Two federal agencies, the National Science Foundation and the Office of Naval Research, are sponsoring this program.

The PAC technique is based on substituting a radioactive probe atom such as either 111In or 181Hfinto a specific site in a chemical system. Because these atoms have special nuclear propenies, the nuclear (electric quadrupole and magnetic dipole) moments of these atoms can

. mteract with the electric field gradients (efgs) and hyperfine magnetic fields produced by the extranuclear environment.

S.tatm nuclear electric quadrupole interactions can provide a measure of the strength and symmetry of the crystal field in the vicinity of the probe nucleus. In the case of static interactions, the vibrational motion of the atoms in the lattice is very rapid relative to the PAC timescale, i.e.,

0.1500 nsec. As a result, the measured efg appears to arise from the time averaged positions of i the atoms, and the sharpness of the spectral lines reflects this " motional narrowing" effect. In (

contrast to static interactions, time-varying interactions arise when the efg fluctuates during the intermediate-state lifetime. These interactions can provide information about defect and ionic ,

- transpon. The effect of the efg fluctuating in either strength or direction, which can be caused, for example, by ions " hopping" in and out of lattice sites,is to destroy the orientation of the intermediate state. Experimentally, this loss of orientation appears as the attenuation or " smearing-out" of the angular correlation. And, often a correspondence can be made between the rate of attenuation and frequency of the motion that produced the attenuation.

Magnetic hyperfine interactions, which can be measured in fenomagnetic and paramagnetic bulk and thin-film materials, are used to study the effects of defects and lattice distonions in metal and semiconducting structures that have nominal cubic symmetry. The general approach is to measure the magnetic hyperfine interaction in a material with few defects. The cubic symmetry requires that the electric quadrupole interaction vanishes. When either defects or distonions are produced, a quadrupole interaction arises that attenuates the usually-well-defined magnetic interactions. Thus, the analysis of this attenuation can provide information, for example, about the type of defect that produced the quadrupole interaction.

25

Curn nt Activities During the last several years, the PAC technique has been used to investigate phase transitions and local ordering in ferroelectric perovskites such as lead titanate and barium titanate. These compounds and other related materials are widely used as dielectric materials for capacitors, piezoelectric transducer materials, and thin-film elements for random access memories. Static nuclear quadrupole interactions measured in these materials have provided new information about displacive (paraelectric to-ferrcelectric) phase transitions such as the critical behavior of the (titanium-site) electric field gradient at temperatures near the transition temperature. In panicular, since few of the ABO 3perovskites have been investigated, similar measurements need to be 2 performed on KNbO3, KTaO3, and similar materials. The primary objective is to observe critical effects near the ferroelectric-to paraelectric transition temperatures in several of these compounds.

Specifically, the theory of critical pheonomena provides an appropriate context in which to interpret the critical exponents that describe the power-law temperature dependence of the nuclear-quadrupole-interaction parameters at temperatures very close to the critical temperature.

Ultimately, measurements of critical phenomina in ferroelectric crystals can be compared to the results of similar measuremetns on other kinds of highly-correlated crystals such as ferromagnetics. These comparisons could lead to a more fundamental understanding of the crystal instabilities that give rise to the phase transitions. The Office of Naval Research has been funding this project.

Another imponant area of research in electronic materials is the characterizadon of chemical interactions on molecular-beam-epitaxy (MBE) produced surfaces. In principle, the PAC technique can measure the strength and symmetry of the chemical bonding of the 111In probe atom on MBE-produced surfaces of gallium arsenide and other III-V materials. Currently, electron scattering is the predominant technique that is used to evaluate the morphology of MBE-produced III-V surfaces. But, these measurements do not provide any detailed, microscopic information about for example, the effects of step edges and kinks on the chemical bonding ofimpinging atoms on these surfaces. The PAC technique, which would use the 111In probe, could be used to measure these effects. Moreover, during the last decade, a German group has shown that PAC measurements on Cu and CuIn surfaces under ultrahigh vacuum are feasible and that the measurements do provide information about chemical bonding on MBE-produced surfaces. A project of this type requires a collaboration between an expen in MBE-produced surfaces and an expen in PAC spectroscopy. Penn State has such an expen; namely, Professor David L. Miller of the Depanment of Electrical and Computer Engineering. The Electronic Materials and Processing Research Laboratory (of the College of Engineering) has a large state-of-the-art Varian MBE machine. But, to dope the MBE-produced surfaces, a small, dedicated ultrahigh vacuum chamber has been added to the existing MBE system. This chamberis used to dope IV-V surfaces with 111In; and because it is separated from the main MBE chambers, the main chamber cannot become contaminated. After surfaces are doped, PAC measurements are performed while the surfaces are

. maintained under ultrahigh vacuum. Two years ago, the separate chamber and the PAC spectrometer had been placed into operation. Last year, experiments were performed using this new experimental capability. During this year, the results of the first series of experiments were analyzed and reported. The National Science Foundation has been funding this project.

26

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X. RADIATION SCIENCE AND ENGINEERING CENTER RESEARCH UTILIZATION Research continues to be the major focus of the RSEC. A wide variety of research projects are currently in progress as indicated on the following pages. The University oriented research projects are arranged alphabetically by department in Section A. Theses, publications, papers and technical presentations follow the research description to which they pertain. In addition, Section B lists other university and industrial research utilizing the facility.

The reporting of research information to the editor of this report is at the option of the researcher, and therefore the research projects in sections A and B are only representative of the research at the facility. The projects described involved 2 technical presentations,5 reports, 14 papers,10 publications,2 patent disclosures,4 masters' theses, and 15 doctoral theses. The examples cited are not to be construed as publications or announcements of research. The publication of research utilizing the RSEC is the prerogative of the researcher.

Appendix A lists all university, industrial and other users of RSEC facilities, including those listed in sections A and B. Names of personnel are arranged alphabetically under their department and college or ur. der their company or other affiliation. During the past year,51 faculty and staff members,46 graduate students and 6 undergraduate students have used the facility for research.

This reprer.nts a usage by 17 departments or sections in 5 colleges of the University. In addition, 50 indi" duals from 31 industries, research organizations or other universities used the RSEC fa?.Sdes.

27

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A. PENN STATE RESEARCH UTILIZING THE FACILITIES OF THE RADIATION SCIENCE AND ENGINEERING CENTER Biochemistry and Molecular Bioloev GENETIC AND MOLECULAR CHARACTERIZATION OF MUSCLE DEVELOPMENT

Participants:

S. M. Abmayr B. A. Bour M. Grill Service Provided: Gamma Irradiation Our laboratory focuses on genes involved in embryonic muscle development of drosophila ,

melanogaster. Gamma irradiation is used to induce damage to chromosomal DNA. Most often l l

this damage is in the form of a deletion. In order to select for a deletion in the desired region of a chromosome, we utilize genetic markers. Gamma-irradiated flies are mated and their progeny are l l

scored for loss of a genetic marker located in the region we are studying. If this marker lies near a gene involved in muscle development, there is a good chance that this muscle gene will be removed when the genetic marker is removed. The deletions obtained by this method are then assessed for the loss of the muscle-specific gene.

DoctoralThesis:

Bour, B. A., and S. M. Abmayr, advisor. Genetic and Molecular Characterization of Muscle Development. In progress.

Sponsors: March of Dimes $60,000 American Cancer Society $90,500 Biochemistry and Molecular Biolocv GENETIC AND MOLECULAR ANALYSIS OF A DROSOPHILA HOMOLOG OF MYOD

Participants:

S. M. Abmayr D. G. Heyser M. S. Erickson Service Provided: Gamma Irradiation Gamma irradiation of Drosophila will cause damage to the DNA with some frequency; approximately 1/10,000 flies will have damage in our area ofinterest. This damage can be detected by scoring the progeny of the irradiated flies for the loss of a genetic marker which would normally be present on an intact chromosome. By irradiating male Drosophila which are then mated to double-balancer females,it is possible to obtain some progeny with deletions of DNA in the desired area. These will then be used to determine if the missing DNA contains genes which are essential to muscle development, which is our area ofinterest.

29

i DoctoralThesis:

Erickson, M. S., and S. M. Abmayr, advisor. The Cloning of MBC, A Gene Involved in Fusion of Drosophila Somatic Muscle. In progress.

Presentations:

Erickson, M. S. The Role of Nautilus in Drosophila Muscle Development. Presentation at Graduate Student Symposium for Biochemistry and Molecular Biology Department. The Pennsylvania State University, June 12,1995.

Abmayr, S. M. Genes Controlling Embryonic Development of the Larval Body Wall Muscles.

Plenary Session Speaker,36th Annual Drosophila Research Conference, Atlanta, Georgia, April 5-9,1995.

Publication:

Rushton, E., R. Drysdale, S. M. Abmayr, A. M. Michelson and M. Bate. (1995) Mutations in a Novel Gene, Myoblast City, Provide Evidence in Support of the Founder Cell Hypothesis for Drosophila Muscle Development. In press,1995.

Sponsor: National Science Foundation 5300,000/3 years Biolorv Deoartment CLONAL ANALYSIS OF THE TRAMTRACK MUTATIONS IN DROSOPHILA

Participants:

Z.-C. Lai Y. Li Service Provided: Gamma Irradiation The tramtrack (ttk) gene acts as a negative regulator in the Drosophila eye development.

Inactivation of the ttk gene results in the development of extra R7 cells. It is known that the sina gene is a positive regulator of R7 cell specificanon. To understand how ttk and sina may act together in determining the R7 cell fate, we used gamma radiation to generate ttk and sina double mutants, and found that the formation of extra R7 cells in ttk mutants does not require the sina gene activity. Thus, ttk may act downstream of sina, or in a parallel signaling pathway.

Publication:

Lai, Z.-C., S. D. Harrison, F. Karim, Y. Li and G. M. Rubin. The Formation of Extra R7 Cells in Tramtrack Mutants Does Not Require the Activity of Sina. Submitted.

Chemistrv Decartment SYNTHESIS AND CHARACTERIZATION OF ANIONIC POLY (ORGANOPHOSPHAZENE) HYDROGELS l i

Participants:

H. R. Allcock l A. A. Ambrosio Service Provided: Gamma Irradiation 30 l s

1 l

3

A series of poly [(propyloxybenzoate) (methoxyethoxyethoxy)-phosphazenes],2a - 5a, was synthesized and characterized. These water-insoluble polymers were then hydrolyzed to yield the anionic derivatives, poly [(oxybenzoate)-(methoxyethoxyethoxy)phosphazenes],2b - 5b, which were glassy and water-soluble. The polymers were cresslinked by 60Co gamma irradiation and the swellability of the cross-linked polymers,2bx - 5bx, was determined as a function of composition, pH, ionic strength and cation charge. Polymers 2bx - Sbx formed hydrogels which had higher equilibrium degrees of swelling in basic than in acidic buffer solutions. Polymers with the higher loading of the oxybenzoate side groups showed higher swellability than those with a lower loading of this side group. The degree of swelling of the polymers was reduced when the ionic strength of the swelling medium was increased. A similar reduction in the swelling of the hydrogels was

- observed when the charge on the cation in the swelling solution was increased. The in vitro release of Biebrich Scarlet from hydrogels 2bx and 4bx was investigated. In pH 2 citrate buffer solutions, the dye was steadily released for the first 12 hcurs. Thereafter, the release curve plateaued reaching appproximately 75% release after 3 days. In contrast, the release rate in pH 7.4 phosphate buffer solutions was rapid with release of all the dye from hydrogels 2bx and 4bx after 70 and 60 minutes respectively.

DoctoralThesis:

Ambrosio, A. A., and H. R. Allcock, advisor. Synthesis of Biomedical Polyphosphazenes. In progress.

Chemistry Deoartment LOWER CRITICAL SOLUTION TEMPERATURE OF POLYMERS

Participants:

H. R. Allcock G. R. Dudley Service Provided: Gamma Irradiation Alkyl ether phosphazene polymers were exposed to gamma radiation to crosslink the polymers.

The crosslinked polymers were then immersed in water and the rate of swelling was measured.

The degree of swelling was then related to the structure of the polymer. The swollen polymers were also placed in water at different temperatures and examined. This project is complete.

DoctoralThesis:

Dudley, G. K., and H. R. Allcock, advisor. Phosphazene Compounds and Polymers. In progress.

Chemistry Decartment SURFACE MODIFICATION OF POLYPHOSPHAZENES

Participants:

H. R. Allcock C. Morrissey Service Provided: Gamma Irradiation The surface modification of polyphosphazenes was examined. These materials may find use as blood or bio compatible surfaces. The modifications were carried by chemical modification of bulk polymers that were uncrosslinked or crosslinked by 60Co yirradiation. Bulk hydrolysis of the 31

e polymers led to the formation of novel hydrogels. Surface modification of the polymers led to increased hydro philicity.

I Doctoral Thesis:

Morrissey, C. T., and H. R. Allcock, advisor. Synthesis and Characterization of Polyphosphazenes. In progress.

Chemistry Decartment GAMMA IRRADIATION CROSSLINKING OF MEEP-PHOSPHAZENE POLYMER FILMS

Participants:

H. R. Allcock M. Olshavsky 1 Service Provided: Gamma Inadiation Project involved trapping of CDS panicles inside a host polymer matrix, which has a fixed pore size as determined by both the constituents making up the polymer and the length of tirr.e the ,

polymer host was exposed to gamma irradiation. These particles were then further used for novel l optical studies.

DoctoralThesis:

Olshavsky, M. A., and H. R. Allcock, advisor. Synthesis of Quantum Confined Cadmium . i Sulfide Nanoclusters in a Phosphazene Polymer Host Matrix. In progress.

Sponsor: NASA Graduate Student Fellowship Program Chemistry Deoartment CHEMICAL INITIATED INCLUSION POLYMERlZATION WITHIN CYCLOTRIPHOSPHAZENE COMPOUNDS

Participants:

H. R. Allcock A. P. Primrose ,

E. N. Silverberg i Service Provided: Gamma Irradiation ,

Vinyl and acrylic monomers included within the host compound tris (o-phenylenedioxy)cyclotriphosphazene were polymerized through thermal activation of free radical 3 initiators. Separate mixtures of acrylonitrile,4-bromostyrene, butylacrylate and 2,3- l dimethylbutadiene containing selected free radical initiators were included by direct contact !

imbibition. Resultant oligiomers characterized through Gel Permeation Chromatography and 13C l NMR analysis are shown to have increased stereoregularity over comparable oligiomers formed in j bulk. Average molecular weights are shown to be dependent upon the amount ofinitiator present. i 2,3-poly (dimethylbutadiene) synthesized within the host adduct over a 50-90 degree temperature {

range using AIBN as the initiator is found to be consistently trans. Electron spin resonance (ESR) analysis of oligiomeric 4-bromostyrene species within the clathrate structure indicates the presence 1 of radicals stable for weeks within the tunnels of the crystal lattice. l s

l l

32 t

I

. 1 l

Chemistw Decartment 1 POLY (ORGANOPHOSPHAZENE) POLYMER ELECTROLYTE ALLOYS:

POLYMER BLENDS AND INTERPENETRATING POLYMER NETWORKS l

Participants:

H. R. Allcock K. B. Visscher S. M. O'Connor D. Olmeijer l l

Service Provided: Gamma Irradiation The synthesis of several new polymer blends and interpenetrating polymer networks (IPN) containing poly (organophosphazenes) and various organic polymers including poly (vinyl ;

ethers), poly (1-alkenes) and poly (vinyl benzo crown ethers) are reported. Polymer blends were prepared by mixing poly [ bis (2-(2-methoxy ethoxy)ethoxy)phosphazene], poly [ bis (2,3-di(2-methoxyethoxy)propoxy)phosphazene], poly [ bis (2,3-di(2-(2'- ,

methoxyethoxy)ethoxy)propoxy)phosphazene] or poly (bis (2,3-di(2-(2'-(2"-

(methoxyethoxy)ethoxy)ethoxy) propoxy)phosphazene] with poly (vinyl ethers), poly (1-alkenes) or poly (vinyl benzo crown ethers) in a common solvent and casting films of the resulting polymer blends. Full, sequential IPNs were prepared by polymerizing vinyl ether,1-alkene or vinyl benzo crown ether monomers within the cross-linked matrix of poly [ bis (2-(2-methoxy ethoxy)ethoxy)phosphazene], poly [ bis (2,3-di(2-methoxyethoxy)propoxy)phosphazene),

poly [ bis (2,3-di(2-(2'-methoxyethoxy)ethoxy) propoxy)phosphazene] or poly [ bis (2,3-di(2-(2'-

(2"-(methoxyethoxy)ethoxy)ethoxy)propoxy)phosphazene]. These materials were characterized ,

by NMR and FT-IR spectroscopy, DSC, electron microscopy and x-ray microanalysis. The conductivity of these materials was measured by impedence analysis. I l

DoctoralThesis:

Visscher, K. B., and H. R. Allcock, advisor. Poly (Organophosphazene) Alloys: Polymer Blends and Interpenetrating Polymer Networks,1993.

Publication:

l Allcock, H. R., S. M. O'Connor, K. B. Visscher and D. Olmeijer. Synthesis and Characterization of Poly (Organophosphazene) Polymer Electrolyte Alloys. To be submitted to Chemistry ofMaterials,1995. l Food Science EVALUATION OF KINETICS OF 0157:717 IN ACTIVATION IN COLICIN-TREATED BEEF PATTIES / HAMBURGERS

Participants:

R. Roberts S. Murinda R. Wilson Service Provided: Gamma Irradiation Gamma inadiation is used to kill all background microflora on beef hamburgers before deliberately inoculating the hamburgers with pathogenic Eschesi Eli a Coli of serotype 0157:117. The hamburgers (which are not for consumption) are also inoculated with colicins, which are inhibitory proteins produced by other strains of E coli: Our hypothesis is that (some of) the colicins will kill the Eschesichi a coli contaminating hamburgers. Conditions for the recovery of E coli and colicins 33

from the hamburgers are being studied so as to establish optimal levels of E coli: added/g and colicin activity units /g of hamburger.

l Treatment of the hamburger with gamma irradiation,4 k gy dose, was found to be adequate to kill all background microflora.

1 Ilamburgers have been associated with foodborne illness involving contamination by E coli ,

nostly of serotype 0157:717. Our goal is to come up with a method for controlling or killing E coli using hamburger as a model system.

DoctoralThesis:

Murinda, S. E., and R. Roberts, advisor. Potential for Colicins to Inhibit Diarrheagenic Verotokigenic Eschenchia Coli Strains of Serotype 015,026,011, Including 0157:717. In Progress.

Materials Science and Engineering DETERMINATION OF STRONTIUM-BARIUM RATIO IN CRYSTALS

Participants:

D. Purdy T. Daubenspeck Service Provided: Neutron Irradiation SrBa crystals were irradiated to determine the feasibility of using neutron activation to determine Strontium-Barium ratio in crystals without producing large amounts of radioactivity. These same crystals will also be analyzed using x-ray diffraction. Preliminary tests worked out and analyses of crystals will begin.

Mechanical Engineering NEUTRON RADIOGRAPHIC ANALYSIS OF MACROSEGREGATION IN BINARY METAL ALLOYS Panicipants: P. J. Prescott V. K. Singh B. Kim Service Provided: Neutron Radiography Convective tiansport phenomena are important during solidification of metal alloys. Fluid flows in the two-phase (mushy) and the fully melted regions are caused by thermally and solutally induced buoyancy forces during solidification of alloys. Fluid flows in the mushy and the melt regions have a profound influence on the metallurgical stmeture and chemical homogeneity of the final casting. Moreover, convection in the solidifying alloy is responsible for macrosegregation, a maldistribution of solute in castings.

A combined numerical and experimental study of convective transport phenomena during solidification of Ga-In (gallium-indium) alloy has been performed, and the effects of varying thermal boundary condition have been considered. Experiments have been performed in a vertical square cavity, which is cooled from a side wall while keeping the other wall insulated.

Experiments are underway to analyze the solidified ingot for any macrosegregation using neutron radiography and comparisons will be made with numerical predictions.

34

4 O

Neutron radiography uses a collimated beam of neutrons to penetrate a specimen. The intensity of the neutron beam exiting the specimen depends on thickness and neutron absorption characteristics of the specimen. There is a large difference in neutron absorption coefficients for gallium (Ga) and indium (In). In other words, gallium is relatively transparent to the neutron beam while Indium is strongly absorbing. The neutron radiograph of the solidified ingot will show the distribution of Ga and In constituents, which is related to convection patterns during solidification.

To relate the neutron beam intensity with Ga-In concentrations, a calibration device has been fabricated. Using the calibration device, a few experiments at the Nuclear Reactor have been performed. The films obtained using Neutron Radiography are being analyzed to develop a correlation between the film density and Ga-In concentrations. In the future, films of the solidified ingot will be taken and the distribution of Ga-In constituents will be determined analyzing the film.

Master's Thesis:

Singh, V. K., and P. J. Prescott, advisor. Convective Transport Phenomena During Binary Alloy Solidification,1994.

DoctoralThesis:

Kim, B., and P. J. Prescott, advisor. An Experimental and Theoretical Investigation of Convection Heat and Mass Transfer During Solidification of Binary Metal Alloys. In progress.

Nuclear Engineering INTERACTIONS OF lilln-+111Cd PROBE ATOMS ON GaAs (111)B RECONSTRUCTED SURFACES MEASURED USING PERTURBED-ANGULAR-CORRELATION SPECTROSCOPY

Participants:

G. L. Catchen D. L. Miller J. M. Adams J.Fu Service Provided: Laboratory Space The radiochemistry laboratories of the RSEC were used to prepare special sources of !!!In.

Specifically, IllInCl was 3 reduced to atomic In under a hydrogen atmosphere in a closed tube. As part of the reduction process the In atoms diffused into a small polycrystalline copper foil. This IllIn-loaded foil was transported to the Electronic Materials and Processing Research Laboratory, where it was used in a specially built illIn effusion source, which was used to effuse atomic 1111n under ultrahigh vacuum conditions onto GaAs surfaces. Subsequently, we used IllIn-+111Cd Perturbed-Angular-Correlation (PAC) spectroscopy to measure hyperfine interactions at surface sites on GaAs (111)B (As-terminated) surfaces. The (111)B surfaces form two reconstructions, 2 x 2, which is formed under As-rich conditions and is stable below = 700 K, and M x M R 23.4*, which is formed under Ga-rich conditions above this temperature. These nearly-atomically-flat surfaces were grown using molecular-beam epitaxy. During each experiment, the IllIn probe atoms were effused onto the GaAs surface, and a series of thermal anneals was performed. A laboratory-temperature PAC measurement was made after each anneal.

The PAC measurements performed on the 2 x 2 reconstructed surfaces show two well-defined nuclear electric-quadrupole interactions that occur at two inequivalent Ga-sites on the surface. The corresponding electric-field gradients (EFGs) are large and asymmetric: Vzz = 8.6 x 1017 35

Vem.2, and a - 0.47 and Vzz = 16.5 x 1017 Vem.2 and a = 0.85; the respective site fractions are

- 50% and = 30%. The measurements performed on the M x M R 23.4' reconstructed surfaces show one well-defined interaction that involved 82% of the probes. The corresponding EFG is also large and asymmetric: Vzz 16.7 x 1017 Vcm.2 and n 0.8, and the EFG z-axis is oriented essentially perpendicular to the surface. Annealing experiments were performed to conven one reconstruction to the other and then to reconven it back to the original reconstruction,

.o. 2 x 2 -+ M x M R 23.4*-+ 2 x 2. The PAC measurements that followed each annealing step sne the characteristic frequencies for each reconstruction. This result indicates that these probe sites are thermodynamically stable. Additionally, at high annealing temperatures and during these themal-cycling experiments, a small fraction of the probes appear to diffuse into the bulk castal The interpretation of the probe-site assignments does not agree with a model of the M . M R 23.4' reconstructed surface developed using scanning-tunneling microscopy. These evperiments represent the first measurements of group III bonding symmetries on a compound III-V semiconductor surface. The corresponding analysis indicates that these symmetries differ qualitatively from the conventional picture.

DoctomiThesis:

Adams, J. M., and G. L. Catchen, advisor. Bond Symmetries and Crystal Structure of Gallium Arsenide (111)B Semiconductor Surfaces Characterized by Surface Electric-Field Gradients, 1995.

Publication:

Adams, J. M., G. L. Catchen, J. Fu and D. L. Miller. Interactions of IllInsillCd Probe atoms on GaAs (111)B Reconstructed Surfaces Measured Using Perturbed-Angular-Correlation Spectroscopy. Surface Science,in press,1995.

Sponsor: National Science Foundatic n S199,000 Nuclear Engineerine O ANION TRANSPORT MEASURED IN SEVERAL R2 M2 07 PYROCHLORES USING PERTURBED ANGULAR CORRELATION SPECTROSCOPY

Participants:

G. L. Catchen T. M. Rearick Services Provided: Neutron Irradiation, Angular Correlations Lab and Laboratory Space j We have used perturbed-angular-correlation (PAC) spectroscopy to measure static and fluctuating electric-field gradients (EFGs) at the M-sites in the pyrochlore ceramic materials, R2 M207 (R = ;

Nd,Sm,Eu, and Gd; M = Zr and Hf). Samples were doped with a small concentration of 1 181Hf-4181Ta PAC probe ions, and the M-site nuclear electric-quadmpole interactions were J observed primarily at elevated temperatures that ranged up to approximately 1300 K. At I temperatures below several hundred degrees, the perturbation functions for the Sm , Eu , and Gd , l containing compounds show broadened lines that indicate primarily the presence of static, disordered O ions. At somewhat higher temperatures, the perturbation function show attenuated lines that fluctuating EFGs produce, which arise from the hopping motion of O-ions. At very high temperatures, the perturbation functions show sharp lines, which have shapes that reflect the presence of axial symmetry, and these lineshapes indicate that the EFG fluctuation rates have mereased to the motional-narrowing limit. Analysis of the attenuation rates, which were measured in the fast fluctuation regime, give activation energies with the electrostatic barriers that 0-ions encounter when they jump to a vacant site. In contradistinction, the measurements on Nd2Zr207 36

4 l show sharp lines over the entire temperature range. This result indicates that the O-ions are i ordered in the Nd crystal and that low-temperature kinetic pathways to disordered stmetures are not accessible to the O-ions. The magnitudes of the measured activation energies are not consistent with the results of theoretical calculations and with electrical-conductivity-measured energies

. reported earlier. Thus, the O-anion transport effects, which we used PAC spectroscopy to 2 measure, provide new benchmarks for future theoretical calculations, and these effects suggest that pyrochlores such as Gd2 Zr207 may become the basis for compounds from which new types of ionic-conducting matenals could be developed. j 4

Publication: 1 i Catchen, G. L., and T. M. Rearick. O-Anion Transport Measured in Several R2 M207 l Pyrochlores Using Perturbed-Angular-Correlation Spectroscopy. To be published in Physical i i

Review B, October 1995.

! Sponsor: Office of Naval Research $249,416 l

1 Nuclear Engineerine ANALYSIS OF ROCK TAKEN FROM THE WUPATKI PUEBLO RUIN IN i ARIZONA

Participants:

T. H. Daubenspeck Q. L. Hartwig

} Services Provided: Neutron Inadiation and Radiation Counters d

Numerous sandstone pueblos were abandoned around 1100 AD for no obvious reason. Many hypotheses have been suggested, but none proven. The presence of uranium deposits in the

' southwestern United States raises the possibility that the rock composition of the pueblos may have

, subjected the occupants to a level of radioactivity that some how caused them to leave.

1 During a visit to the Wupatki Pueblo ruin in northern Arizona, Dr. Hartwig collected two rocks, one of basalt, one oflimestone and sent them to the RSEC for analysis for natural radioactivity.

The samples did not exhibit inherent radioactivity. The analysis did reveal the presence of various trace elements and a survey of them is still ongoing.

j Nuclear Engineerine i

POTENTIAL OF SILVER SULFADIAZINE (SILVADENES) TO INCREASE I

SODIUM AND CHLORIDE IN BURN ESCHAR

Participants:

T. H. Daubenspeck

{ Q. L. Hartwig 7

Services Provided: Neutron Irradiation and Radiation Counters Silver sulfadiazine, a topical antibiotic, is routinely applied to burned tissue to prevent infection.

Preliminary data from RSEC of neutron activated, thermally burned skin (eschar) suggested that j the siiver drew significant amounts of sodium and chloride into the eschar.

Since reports of electrolyte imbalance have been associated with the application of silver nitrate, a topical antibiotic, but not silver sulfadiazine, this preliminary finding prompted a follow-up of a

more extensive study.

37 i

i l

\

l Twelve samples of eschar and nonnal tissue were obtained from surgery, processed, and sent to the RSEC for neutron exposure and counting to determine the silver, chlorine, and sodium concentrations in each based on the irradiation of Standard Reference Material 1566a, Oyster Tissue. Examination of the data did not support the thesis that the silver in silver sulfadiazine l entrapped sodium and chloride into the burn tissue.

Still, the concept of attracting or preventing movement or organisms / substances through the burn eschar could have application to the continuing problem of eschar infection. Thus, the time interval between antibiotic application and tissue collecnon will be funher examined and possibly lead to another experimental design, collection and neutron activation.

Nuclear Encineering INVESTIGATION OF HISTORIC ST. MARY'S CITY HUMAN REMAINS USING NEUTRON ACTIVATION ANALYSIS Panicipants: T. H. Daubenspeck M. Moore H. Miller S. D. Harry Services Provided: Neutron Irradiation, Radiation Counters and Neutron Activation Analysis Three lead coffins at the Historic St. Mary's City contain the remains of three Maryland colonists buried there 300 years ago. Archaeologists think one coffin may contain the remains of Philip Calven, youngest son of Sir George Calvert, the first Lord Baltimore. Philip, the colony's first chancellor, died in 1682. The other two coffins are thought to contain the remains of Philip's wife and child. The remains of the woman are the best preserved 17th-century remains ever found in North America.

Last year, NAA was used to identify the composition of crystalline residue found on the remains.

From activation analysis results and results of other tests, the composition and formation of the crystalline residue was able to be determined. Hair samples analyzed using NAA found unusual amounts of acenic and silverin one of the hair samples. It was determined that the silver concentration was due to jewehy worn in the hair. The arsenic concentration led to an investigation that focused on the use of arsenic in medicines in colonial days. This year, further hair analysis continued.

Nuclear Engineering i ISOTOPE PRODUCTION FOR TRACER STUDIES Panicipants: T. Daubenspeck M. Bothe J. Kolek M. Flenniken D. Bucior Services Provided: Neutron Inadiation and Isotope Production Fourteen isotope production runs were performed for Tru-Tec during the past year. These runs included 2 Na-24 runs, and 12 Br-82 runs. A total of 800 mci of Na-24 and 3.7 Ci of Br-82 was l

l l 38

~

produced. Five Ar-41 production runs were performed for Tracerco during the year with a total of 1.4 Ci of Ar-41 produced.

Nuclear Eneineering SEMI CONDUCTOR IRRADIATIONS Panicipants: T. Daubenspeck l F. Kalkbrenner l R. Diette C. Uber Service Provided: Neutron Irradiation Semi-conductor inadiations for commercial and military applications numbered 175 for the year.

There were 142 irradiations for Harris Semiconductor,30 for Raytheon, and 3 for E-Systems.

l Nuclear Engineering NEUTRON ACTIVATION ANALYSIS - QUALITY ASSURANCE FOR ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE

Participants:

T. Daubenspeck M. Moore R. George Services Provided: Neutron Inadiation and Radiation Counters The Armed Forces Radiobiology Research Institute (AFRRI) had various types of samples analyzed at the PSBR as part of a quality assurance program to compare the PSBR results to those of the AFRRI neutron activation analysis laboratory. Some of these analyses involved a project AFRRIis doing for the United States Nuclear Defense Agency to determine the feasibility of using Dysprosium to monitor the dispersion pattern of bomb blasts.

Nuclear Encineerine VARIOUS ANALYSES OF SAMPLES USING THE SERVICES OF THE RADIONUCLEAR APPLICATIONS LABORATORY Participant: T. Daubenspeck Services Provided: Neutron Irradiation, Radiation Counters and Flux Monitoring Rabbit runs of Y(NO 3)3 solutions were performed for thesis work currently in progress (Senaratne, Jester).

Analysis of water samples for MEA project (Gould).

Stainless steel samples irradiated and analyzed to determine possible activation products created during Bittecker project (Hughes).

Activated and analyzed iron foils (Cumblidge).

39

, i Irradiated 3 pair (1 bare,1 cd covered) of activation foils (AuAl, MnCu, and Fe) in core positions Cf. B9 and R1 for determining the power distribution through core (Haghighat).

Irradiated 2 sets of activation foils (Ni, AuAl) on D20 tank to detennine flux distribution over axial length of tank for use in D 2O tank design project (Haghighat).

Performed a flux run using sulfur pellet dosimetry to determine the irradiation time required for devices to receive 2.5 x 1018 n/cm2 in our bare 2" x 6" irradiation fixture. This flux run was part I of a feasibility study conducted for a possible project (Draper Labs).

Irradiation and analysis of one Maalox sample and 2 unknown samples to determine the concentration of aluminum and magnesium based on the known Maalox concentrations (Fazio, Indiana University of Pennsylvania).

Irradiated various samples of aluminum to determine activation products created in Mercury source I (Kahn, Kenney, Gould).

NAA was conducted on four air filters taken from the Great Lakes area. The analyses were l performed to determine the feasibility of using this facility in a project which would determine the spread of pollution and air quality over the Great Lakes area (Ondov, University of Maryland).

Nuclear Engineerine l

NE 451, UNDERGRADUATE LABORATORY OF REACTOR EXPERIMENTS l

Participants:

R. M. Edwards W. A. Jester J. A. Turso M. E. Bryan Services Provided: Laboratory Space, Machine Shop, Electronics Shop, SUN SPARC server computer system, Reactor Instrumentation and Support Staff.

The Nuclear Engineering 451 course is the second of two required 3 credit laboratory courses.

Each weekly laboratory exercise usually consists of 2 lectures and one laboratory session. The first course (NucE 450) covers radiation instrumentation and measurement and is conducted in the 2nd semester of the junior year. By the beginning of the senior year, the students have already covered the LaMarsh Introduction to Nuclear Engineering text including reactor point kinetics. The 451 course then emphasizes experiments using the instrumentation that was covered in the first course and is divided into two (more or less) equal " tracks". These tracks can be coarsely described as TRIGA and non TRIG A experiments and each is the major responsibility of a different professor. The non-TRIGA track includes 3 graphite pile,2 analog simulation, and 1 power plant measurement experiment, in 1994, the TRIGA track included: i

1. Digital Simulation of TRIG A Reactor Dynamics

2. Control Rod Calibration

3. Large Reactivity Insertion (Pulsing)

4. ReactorFrequency Response

5. Neutron Noise

6. Reactor Control This sequence was first introduced in 1991 when the reactor control experiment replaced a reactor gamma field measurement experiment and the digital simulation exercise was modified to point kinetics from its previous focus on Xenon dynamics. The laboratory utilizes Macintosh computers 40

s with GW Electronics MacAdios Jr data acquisition hardware and Superscope II software. The Superscope II software was a major software upgrade for 1993 and with its new point-by-point seamless mode enabled effective reactivity calculations and control experiments. The Mathworks SIMULINK simulation software was used for the digital simulation exercise for the first time in 1992. Reactor control is offered as a graduate course in our department but until 1991 our undergraduates did not receive a complete introduction to feedback control. In the Fall of 1994, a new UNIX network compatible control system was utilized for the reactor control experiment. The new system was also acquired to enhance the NSF/EPRI sponsored research and is described in more detail in subsequent sections. The UNIX Network compatible controller programming is performed using the Mathworks SIMULINK block programming language in a SUN SPARC workstation. An automatic C code generation process produces and downloads the necessary real-i time program for execution in a microprocessor-based controller with an ETHERNET network l interface to the host workstation. i The 1994 version of the control experiment thus unities all of the MATLAB/SIMULINK (

instruction earlierin the course into a demonstration of state-of-the-art CASE based control system j design and implementation.

Sponsor: Tuition Surchage 56,690 (1994)

I Nuclear Eneineering NSF/EPRI: EXPERIMENTAL DEVELOPMENT OF POWER REACTOR INTELLIGENT CONTROL

Participants:

R. M. Edwards K. Y. Lee D. E. Hughes Laboratory Space, Machine Shop, Electronics Shop, SUN SPARC server j Services Provided:

computer system, Reactor Instrumentation and Support Staff. l A

This is a major three year project supported by the National Science Foundation and Electric Power l Research Institute. Initiated in January 1993, the project is composed of five major tasks: 1) l Advanced Direct Control Experiments,2) Intelligent Control Research,3) Multivariable Control {

i Capability,4) Hybrid Reactor / Simulation, and 5) Dissemination of results. Specific activities during the 1994-95 academic year are summarized in the following descriptions. l For the summer of 1995, an NSF supplemental grant for Research Experiences for Undergraduates (REU) was obtained and two undergraduate students are participating.

Paper-Edwards, R. M., K. Y. Lee and D. E. Hughes. An Experimental Testbed for Advanced Digital Nuclear Reactor Control. The Fifth Intemational Joint IS A POWID/EPRI Controls and l Instrumentation Conference, pp. 235-243, La Jolla, Califomia, June 1995.

Publication:

Second Annual Progress Report on Experimental Development of Power Reactor Intelligent Control, ECS-9216504, Report to National Science Foundation, March 1995.

Sponsors: FERMI S12,000 (1992) NSF/REU (1995) 59,000 FERMI $18,000 (1994) NSF/EPRI (1993-1995) $300,000 for the following NSF/EPRI projects:

41

\

Nuclear Eneineering NSF/EPRI ADVANCED REACTOR TEMPERATURE CONTROL ALGORITHMS

Participants:

R. M. Edwards H. D. Gougar K. Y. Lee P. Ramaswamy R. M. Johns G. L. Meyers R. F. Sanchez D. E. Hughes M. E. Bryan 1 Services Provided: Laboratory Space, Machine Shop, Electronics Shop, SUN SPARC server computer system, Reactor Instrumentation and Support Staff.

l Advanced reactor temperature control algorithms are developed in the first component of the NSF/EPRI project. Based on a prototype TRIGA Reactor Optimal Control experiment conducted during the summer of 1991 and subsequent work by Mike Power in the previous 93-94 academic year, this area was expanded into design and assessment of enhanced observer-based PID and 1 optimized feedforward control during the 94-95 academic year. l 1

In addition, a new UNIX network compatible controller (same as adopted in the control experiment l of the NucE451 laboratory course) was acquired in the Fall of 1994 and allows the utilization of a state-of the-art CASE-based environment for controller design, testing, and implementation. The microprocessor based controller uses the Wind River Systems VxWorks real time operating system to implement a control strategy which is developed in a UNIX host computer CASE-based controller development environment. The VxWorks microprocessor is a general purpose and l

diskless 68040 Motorola-based microprocessor with ADC/DAC cards and standard ETHERNET network interface to the UNIX host development environment. The micro interfaces with the reactor secondary control rod (SCR) which travels in the central thimble while the licensed control and safety system is in a manual mode of operation. This new state-of-the-art CASE environment replaces the Bailey Network 90 system for many of the experiments conducted in previous years.

2 Advanced control algorithms, such as an optimal control algorithm, require a dynamic model of the ,

process in order to achieve improved performance characteristics. The concept of 1 l

robustness relates to how far can the actual process deviate from the assumed process model and still maintain required stability and desired performance improvement. Through extensive simulation, this optimal controller, which is based on a one-delayed neutron group model, has '

been shown to maintain desired performance for a factor of 10 variation in the power level and !

control rod worth for which it was designed. l Algorithms with improved reactor temperature performance developed for full range robustness testing in 1994-95 include: H -based p-synthesis, fuzzy logic, neural network, PID and optimized feedforward / robust feedback.

Papers:

Edwards, R. M., R. M. Johns, S. J. Kenney and H. D. Gougar. Unconventional Digital Reactor i Control without Conventional Programming. Trans. Amer. Nucl. Soc. 22: 298-300, June !

1995.

i 4

l 42

.I

~

l Power, M. A., and R. M. Edwards. Implementation of Robust Control Experiments on a Nuclear Reactor. Proceedings of the Ninth Power Plant Dynamics and Control Conference, pp 30.01-30.15, Knoxville, Tennessee, May 1995.

Ramaswamy, P., R. M. Edwards, and K. Y. Lee. Performance Evaluation of Fuzzy Logic and Neural Network Controllers. Proceedings of the Ninth Power Plant Dynamics and Control Conference, pp 65.01 65.11, Knoxville, Tennessee, May 1995.

Johns, R. M., Y. Zhao and R. M. Edwards. Optimized Wide-Range Robust Control for a Nuclear Power Plant, pp 34.01-34.03, Proceedings of the Ninth Power Plant Dynamics and Control Conference, Knoxville, Tennessee. May 1995. (An updated version of the paper was not submitted in time to be included in the initially distributed printed proceedings.) 1 Power, M. A., and R. M. Edwards. Functional Prototype Testing of Model-Based Advanced l Control For Nuclear Reactors. Trans. Amer. Nucl. Soc. H:361-362, November 1994.

Ramaswamy, P., R. M. Edwards and K. Y. Lee. Validating Real-time Implementations of l l

Diagonal Recurrent Neural Network and Fuzzy Logic Controllers. Trans. Amer. Nucl. Soc.

H:364-365, November 1994.

Weng, C. K., M. A. Power, R. M. Edwards and Asok Ray. Feedforward-feedback Control by Nonlinear Programming and Structured Singular Value Approach. Trans. Amer.Nucl. Soc.

H:365-366, November 1994.

Weng, C. K., R. M. Edwards and Asok Ray. Robust Wide-Range Control of Nuclear Reactors By Using the Feedforward Feedback Concept. Nuclear Science and Engineering HZ:177-185, July 1994.

l l

Nuclear Engineerine j 1

NSF/EPRI INTELLIGENT CONTROL OF TRIGA REACTOR TEMPERATURE j

Participants:

R. M. Edwards S.J.Kenney D. E. Hughes Services Provided: Laboratory Space, Machine Shop, Electronics Shop, SUN SPARC server computer system, Reactor Instrumentation and Support Staff.

An intelligent reconfigurable reactor power controller has been developed and implemented in the second component of the NSF/EPRI project. The intelligent controller automates a monitodng and decision-making process that chooses the best controller to achieve improved reactor l l

temperature perfomiance over a wide range of operating conditions. The available controllers are those developed in the previously described advanced reactor temperature control algorithm research. On-line performance of an enforced controller is determined by measures of integrated quadratic temperature error, power demand, rod reactivity rate demand, and rod reactivit; femand.

The decision making process uses a learning systems based automaton at the pretent time.

Master's Thesis:

l Kenney, S. J., and R. M. Edwards, advisor. An Intelligent Reconfigurable Reactor Power Controller. In progress. i 1

43 l

l 1

Papers:

Kenney, S. J., and R. M. Edwards. An Intelligent Reconfigurable Reactor Power Controller.

Proceedings of the Ninth Power Plant Dynamics and Control Conference, pp 32.01-32.16, Knoxville, Tennessee, May 1995.

Kenney, S. J., M. A. Power, H. E. Garcia and R. M. Edwards. Improved Reactor Temperature Response Using an Intelligent Reconfigurable Reactor Power Controller. Trans. Amer.Nucl.

Soc. 21:362-364, November 1994.

Nuclear Engineerine NSF/EPRI MULTIVARIABLE CONTROL DEVELOPMENT

Participants:

R. M. Edwards D. E. Hughes H. D. Gougar Services Provided: Laboratory Space, Machine Shop, Electronics Shop, SUN SPARC server computer system, Reactor Instrumentation and Support Staff.

Experimental multivariable control capability is being developed as the third component of the NSF/EPRI funded project. The benefits of advanced algorithms and intelligent control can be more clearly demonstrated in a multiple input-multiple output system where failure in the ability to manipulate one of the inputs can be accommodated by appropriate action in remaining operational controlloops. In 1994-95, various concepts for adding the ability to manipulate TRIGA reactor coolant flow and temperatures, independently of rod reactivity control, were studied. The flow control mechanism which is being pursued will add a shroud around the periphery of the reactor with an adjustable flow area that manipulates the flow entering the side of the reactor. Analytic studies of the approach continue to be conducted. Initialinstallation and testing of the shroud have been approved by the reactor safeguards committee.

Nuclear Engineering NSF/EPRI HYBRID SIMULATION OF BWR USING THE TRIGA REACTOR

Participants:

R. M. Edwards J. A. Turso D. E. Hughes Services Provided: Laboratory Space, Machine Shop, Electronics Shop, SUN SPARC server computer system, Reactor Instrumentation and Support Staff.

Hybrid reactor simulation is the fourth component of the NSF/EPRI project and is achieved by interfacing a computer simulation of an alternate reactor's reactivity feedback mechanism, such as a BWR, to appropriately position a control rod in the reactor. The result is that the observed TRIGA reactor power begins to mimic the characteristics of the alternate reactor. In 1994-95, the previously developed PC computer-based hybrid simulation capability was converted to the new UNIX network compatible controller. A more sophisticated hybrid BWR simulation was developed where the effect of manipulating BWR flow can be directly demonstrated. Results 44

)

obtained from the HRS were utilized to validate a new method of BWR stability monitoring in the thesis of James A. Turso.

DoctoralThesis:

Turso, J. A., and R. M. Edwards, advisor. Reduced-Order Modeling, Analysis and Monitoring of Boiling Water Reactor Dynamic Behavior. In progress.

Papers:

Turso, J. A., J. March-Leuba and R. M. Edwards. A Modal Based Reduced Order Model of BWR Out-of-Phase Instabilities. Trans. Amer. Nucl. Soc.22:376-377, June 1995.

Turso, J. A., R. M. Edwards and J. March-Leuba. Hybrid Simulation of Boiling Water Reactor Dynamics Using A University Research Reactor. Nuclear Technology,110:132-144, April 1995.

Turso, J. A., R. M. Edwards and T. W. Highlands. Boiling Water Reactor Stability Analysis via Kalman Filter Based Estimation and Maximum A Posw ' >n (M AP) Detection. Trans. Amer.

Nucl. Soc. 2.1.:442-444, November 1994.

Nuclear Eneineering NSF/EPRI INTELLIGENT CONTROL WORKSHOP #2

Participants:

R. M. Edwards K. Y. Lee D. E. Hughes H. D. Gougar i R. M. Johns '

J. A. Turso S.J.Kenney l

P. Ramaswamy '

M. Cecnas-Falcon G. Meyers l R.Sanchez l l

l Services Provided: Classroom and Laboratory Space, SUN SPARC server computer system, i Reactor Instrumentation and Support Staff In addition to publications and conference presentations, the fifth component of the NSF/EPRI l project also disseminates research results through periodic workshops. A one day workshop for industry professionals was conducted on March 21,1995. Representatives from the Department of Energy, National Science Foundation, Electric Power Research Institute, a utility, a national laboratory, the Nuclear Regulatory Commission, and a reactor manufacturer attended. The workshop included presentations and TRIGA reactor demonstrations of the NSF/EPRI research.

Publication:

Workshop overheads and Reference Papers.

45 l

Nuclear Engineerine -

THREE DIMENSIONAL COUPLED KINETICS THERMAL-HYDRAULIC BENCHMARK EXPERIMENTS USING THE BREAZEALE TRIGA REACTOR

Participants:

M. Feltus F. A. Alpan Service Provided: TRIGA Reactor The major goal of this expedmental research project is to provide separate effects tests in order to berichmark neutron kinetics models coupled with thermal-hydraulics models used in the NRCs best-estimate codes, RELAP and TRAC. Using simple reactor core configurations,it is possible to determine the level of neutronics modeling required to describe kinetics and thermal-hydraulic feedback interactions. With fuel element thermocouple instrumentation,it is also possible to benchmark the fuel temperature, flux distribution, and thermal hydraulics models in these codes.

This research effort seeks to provide experimental results to quantify the 1- and 3-dimensional kinetics models in the NRC's RELAP and TRAC codes and the RETRAN code series. The first series of experiments will have steady-state power levels to provide flux and fuel temperature distributions on a core wide basis. Then tests using transient power levels, square waves, neutron pulses, and rapid and slow control rod movements will be performed that simulate time-dependent transients with kinetic and thermal-hydraulic feedback. Various symmetric and asymmetric core configurations will be used to develop spatially dependent kinetics and thermal-hydraulic conditions for quasi-static benchmarks. Finally, time dependent core configurations (e.g.,

asymmetric control rod and fuel rod movements) will be simulated first with the computer codes.

Then experimental data will be used to demonstrate code fidelity and what corrections are needed.

The NRCs TRAC and RELAP, and EPRI's RETR AN thermal-hydraulics codes have neutron kinetics models, either in point or 1-dimensional cases in their official released versions.

Generally, it is assumed that thermal-hydraulically induced transients do not provide sufficient perturbation in the kinetics to warrant three-dimensional kinetics treatment within the systems codes. However, Feltus has shown that even thermal-hydraulically induced PWR transients, such as Loss of Reactor Coolant Flow, Main Steam Line Break, and Anticipated Transients without Scram (Station Blackout and less of Main Feedwater), require three-dimensional kinetics analysis coupled with thermal-hydraulic feedback,in terms of core and system-wide best-estimate response. Although there have been some numedcal test cases of 1- and 3-dimensional kinetics, and benchmarks of kinetics models with actual plant tests, i.e., Peach Bottom Turbine Trip Tests, where core-wide parameters, such as pressure, have been matched, benchmarks of these codes against simpler test results have not been done extensively.

One reason is that there is a limited amount of actual in-core kinetics experiments, with thermal-hydraulic feedback coupling available. Recent startup experiments for the Ljubljana TRIGA reactor have been well-documented and have been proposed as suitable for benchmark calculations for physics codes. Such research reactor tests could provide better understanding of the reactor kinetics with thermal-hydraulic feedback.

Another reason is that there is a general perception that small research reactors are essentially point or zero-dimensional in their reactor physics. However, TRIGA reactors can be configured to simulate complex physics conditions. Recently, Mele at al. performed experimental steady-state, ,

pulse, and control rod wonh measurements at the Ljubljana TRIGA Mark II reactor, which was ;

reconstructed in 1991. All the benchmark experiments were perfomied with fresh, compact, and i uniform fuel at 12 w/o, at well-known operating conditions. The Ljubljana TRIGA benchmark I results would be used in this project to qualify the neutronics models in the thermal-hydraulic (i.e., l TRAC, RELAP, and RETRAN) codes. l l

l 46 l 1

_ _ - - - - 1

This project also seeks to provide relatively simple benchmark experiments on the Penn State l l

Breazeale TRIGA reactor, where the flux and temperature distributions are obtained. Using steady-state power distributions for static neutronics feedback,it is possible to evaluate the neutronic/ thermal-hydraulic coupling for transient power conditions, including TRIGA pulsing, l

square waves, power ramps, control rod movements, and rapid scram conditions. One special l

case will be performed moving a fuel rod at power to simulate the operational mistake that happened at the University of Michigan plate-fueled reactor. Such a test would be considered only l l

after pretest calculations are performed, and then, only after the other code-to-experiment benchmarks are completed. l l

Master's Thesis:

Alpan, F. A., and M. A. Feltus, advisor. Three Dimensional Coupled Kinetics Thermal-Hydraulic Benchmark Experiments Using the Penn State TRIGA Reactor. In progress.

Sponsor: US Nuclear Regulatory Commission $109,839 (1/95 - 12/31/96) l Nuclear Engineeriny TRIGA POWER PULSE EXPERIMENTS FOR CHARACTERIZATION OF FAST REACTIVITY INSERTION TRANSIENTS FOR TEST AND POWER REACTORS

Participants:

M. A. Feltus l D. Ebert Service Provided: Breazeale Reactor I

At the request of Dr. David Ebert (NRC) a series of TRIGA pulses were performed to simulate fast reactivity insertion rates in research and large power reactors. Pulse shapes were qualitatively examined and derivations of pulse shape equations were supplied from NucE 597K Reactor Kinetics, course notes. This work was done to support the BWR fuel failures studies performed by the NRC on the Japanese and French test reactors to simulate large rapid reactivity insertions.

These include BWR rod drop accidents in a high bumup core where fuel failures have occurred at low energy depositions, and PWR rod ejection accidents.

Publication:

Ebert, D. Pulse Shapes in Reactors, presentation to the ACRS Reactor Fuels Subcommittee, May 3,1995. Presented RSEC Breazeale reactor pulse results and compared with other research reactors.

Nuclear Engineerine NEUTRON RADIOGRAPHY EXPERIMENTS FOR VERIFICATION OF SOLUBLE BORON MIXING AND TRANSPORT MODELING UNDER NATURAL CIRCULATION CONDITIONS

Participants:

M. A. Feltus G. M. Morlang Service Provided: Neutron Radiography The major goal of this experimental research project is to provide separate effects tests in order to benchmark boron transport models used in best-estimate thermal-hydraulic codes, such as RELAP 47

N .

and TRAC. Using simple and complicated fluid flow geometries, boron mixing effects can be determined under natural c_irculation and low flow conditions using non intrusive, non-destructive neutron radiography techniques.

This research effon seeks to provide experimental results to quantify boron transport and mixing effects, and assess the boron mixing models used in the NRC RELAP and TRAC thermal-hydraulics code series. The first series of experiments will model simple flow configurations to create boron transport separate effects tests to benchmark code results. Later, tests will simulate natural circulation and low flow conditions in the reactor vessel during boron injection during Anticipated Transients Without Scram (ATWS) events and severe accident scenarios. The neutron radiography visualization films and test results and analyses will provide sufficient information to qualify thermal-hydraulic boron tracking models, turbulent mixing assumptions, etc., to upgrade NEC code models to really yield best-estimate results.

Neutron radiography techniques provide a non-intrusive, non-destructive method to "see" turbulent effects in fluid flow streams. The neutron imaging is able to distinguish an image based on hydrogen content and other elements, rather than simple mass attenuation, as in the case of x ray or gamma-ray imaging techniques. This means that the turbulent effects and small scale phenomena can be differentiated, without penu-bing the fluid flow stream with instrumentation or flow blockages. More conventional flu % ilow measurements yield bulk mixing effects; however, the small concentration of boron and s,Aute phenomena can not be readily visualized. Resolution can be achieved by real time or steady-state video camera visualization. This implies that geometric effects, turbulent and laminar flow, and boron mixing effects can be determined under natural circulation and low flow conditions using neutron radiography.

The proposed neutron radiography technique provides significant advantages over more conventional fluid flow methods:

1. There is no perttTrbation in the flow stream by instrumentation.

2. Various densities, solution concentrations, flow rates, etc., can be used to demonstrate turbulent mixing effects.

3. The fine fluid flow structure can be resolved in apparatus that is not transparent, and resolved in three dimensions.

This research effort will provide experimental benchmark information for boron transport and mixing, for real-time transient effects, and static imaging. The results from the tests can be used to qualify the boron tracking models in NRC and industry thermal-hydraulics codes, such as RELAP, TRAC, and RETRAN. By using a neutron transparent fluid at different flow rates, densities, and temperatures, it is possible to s'tmulate boron injection effects in ATWS conditions for BWR and PWR cores. Effects of turbulence and mixing can be simulated and measured to asseas thermal-hydraulic code predictions.

Doctoral Thesis:

Morlang, G. M., and M. A. Feltus, advisor. Neutron Radiography Experiments for Verification of Soluble Boron Mixing and Transport Modeling Under Natural Circulation Conditions. In progress.

Sponsor: Nuclear Regulatory Comrnission $56,406 Phase I (11/93-11/94) 569,878 Phase II(11/94 - 1/96) i I

48

i 1

Nuclear Engineerinc f'

l PIPE WALL THICKNESS MEASUREMENT USING SCATTERED GAMMA RAYS

Participants:

R. Gould ,

j E. S. Kenney E. H. Klevans j X.Xu t S. Kahn D. Wulsch Services Provided: Hot Cell Lab, Laboratory Space, Machine Shop and Electronics Shop !

l Pipe wall thinning continues to be a serious problem in the nuclear industry. The problem first appeared in PWRs, but is now recognized throughout the industry. This project has demonstrated l that pipe wall thinning can be detected using scattered gamma rays. A combination of Monte Carlo studies and pilot experiments have confimled the potential of such a technique. A field usable !

device has been developed to use up to 0.5 curie of Hg-203. Field tests are planned for Summer 1995. Pending the outcome of these field tests, commercialization of the system is expected to be completed by Spring 1996. ,

1 DoctoralTheses:

Xu, X., and E. H. Klevans, advisor. A High Speed Compton Scatter Imaging System. In progress.

Khan, S., and E. H. Klevans, advisor. A Monte Carlo Analysis for a Compton Back-Scatter Pipe f Wall Thickness Gauge. In progress.

Patent Disclosures:

l Gould, R., E. S. Kenney, S. Khan and X. Xu. A Compton Back-Scatter Pipe Wall Thickness i l

Gauge Employing Focusing Collimator and Annular Detector, July 1994.

Xu, X., E. S. Kenney and E. H. Klevans. A Compton Back-Scatter Pipe Wall Imaging System Using a Wide Aperture Annular Detector, April 1995.

Sponsor: FERMI $30,000 Nuclear Eneineerine NON. DESTRUCTIVE EXAMINATION OF CHEMICAL REACTOR COMPONENTS

Participants:

R. Gould J.Li Service Provided: Neutron Radiography This project examined a clogged component from a chemical reactor. It was determined that toluene had carbonized, plugging the outlet of a liquid separator.

49

Nuciear Engineerine EVALUATING TWO PHASE FLOW USING NEUTRON RADIOGRAPHY

Participants:

D. E. Hughes R. Gould S. S. Glickstein Services Provided: Neutron Radiography, Machine Shop and Electronics Shop This project is using neutron radiography to perform 2-phase fluid flow experiments. An upgrade of the flow loop from atmospheric pressure to 2000 psi is being performed, with measurements to follow.

Sponsor: Bettis Atomic Power Laboratory $70,436 Nuclear Engineerine INEL BURIED WASTE INTEGRATION PROGRAM Participant: W. A. Jester Service Provided: Office Space In 1994, Dr. Jester was chosen to be a member of the Technical Academic Review Group (TARG) that reviews the technologies being developed by the Idaho National Engineering Laboratory under the Buried Waste Integrated Demonstration (BWID) program. Dr. Jester was chosen for this prestigious committee because of his expertise in radiation monitors.

Reports:

Jester, W. A. Mid-Year Peer Review of the Buried Waste Integrated Demonstration (BWID)

Program. Submitted to EG&G Idaho,22 pages, May 1994.

Jester, W. A. Evaluating Selected Technologies and Programs of the Buried Waste Integrated Demonstrated (BWID) Program. Submitted to Lockheed Idaho Technologies Program,8 pages, December 1994.

Jester, W. A. Mid-Year Peer Review of the Buried Waste Integrated Demonstration (BWID)

Program. Lockheed Idaho Technologies Program,21 pages, March 1995.

Sponsor: Idaho National Engineering Laboratory $54,404 Nuclear Engineering FLUX AND FLUENCE DETERMINATION USING SCRAPINGS FROM VESSEL COMPONENTS

Participants:

W. A. Jester H. S. Basha Services Provided: Neutron Irradiation, Radiation Counters and Laboratory Space 50

l Experimental analyses were performed to develop a new method to obtain neutron dosimetry data from scrapings chips taken from various vessel components in light water reactors. The concept behind this new methodology is to take steel scrapings from an in-service vessel component such as the reactor pressure vessel wall, core internals, or support structures and use the measured specific activity of radionuclides in the material to predict its neutron exposure. To develop the scrapings technology, several well characterized cadmium covered and bare ferritic and2 stainless steel samples were irradiated at the PSBR facility to a fluence level of 1016-1017n /cm ,

. Instrumental and radiochemical analyses were performed on the irradiated steel samples using a HPGe detector system. The final set of reactions for flux measurements included 3dFe(n,p)34Mn, 60Co,123Sb(n,y)t24Sb, and 181Ta(n,y)ts2Ta for ferritic 5sFe(n,y)59pe,58Ni,(n,p)58Co,59Co(n,y)58Ni(n,p)58Co, steel and 54Fe(n,p)54Mn,58Fe(n,y)$9Fe, and 59Co(n,y)60Co for stainle The maximum difference between the flux calculated using the scrapings methodology and that calculated using the conventional flux wire approach was about 12% for energies greater than 10 key. The good agreement obtained between the two techniques demonstrated the potential accuracy and reliability of the scrapings technique for RPV wall flux measurements.

DoctoralThesis:

Basha, H. S., and W. A. Jester, advisor. Flux and Fluence Determination Using Scrapings from Reactor Pressure Vessel Components,1995.

Publication:

Basha, H. S., and W. A. Jester. Non-Conventional Approach for Determination of Several Key Exposure Parameters for LWR's. Trans. Am. Nucl. Soc., ISSN:0003-018X, TANSO 70 1-458, 372-373, 1994.

Report:

Basha, H. S., and W. A. Jester. Plant-Life Extension Technology: Flux and Fluence Determination Using Scrapings from Inservice Components. Final report presented to project FERMI,8 pages, April 1995.

Nuclear Engineering RADIOLOGICAL ANALYSIS OF THE MATERIALS USED IN THE PRODUCTION OF FEMORAL HEADS

Participants:

W. A. Jester R. W. Granlund M. Peagler J. Lebiedzik Services Provided: Radiation Counters, Laboratory Space and Low Level Radiation Monitoring Laboratory The objective of this work is to determine the relative patient dose from Vitallium

Alloy femoral heads used in hipjoint replacement. The samples are composed of a cobalt / chromium alloy. The alpha, beta, and gamma activities emitted by these samples were measured using long counting times and where possible low background radiation detection equipment. Of special interest was the cobalt-60 activity detected in one of the heads.

A quality assurance procedure has been developed in conjunction with Howmedica to insure that the zirconia used to produce the femoral heads does not contain harmful amounts of alpha and beta emitters. Suppliers of this material send to the LLRML two thin disks produced from each of their 51

batches, for low level alpha and beta activity measurements. Only if the activity of these two samples pass the various quality assurance criteria can the raw material be sent to Howmedica for the pmduction of femoral heads.

Report:

Jester, W. A., M. Peagler and R. W. Granlund. Radiological Analysis of Vitallium

Alloy Disk and Femoral Heads. Final report submitted to Howmedica, Inc.,13 pages, March 1995.

Sponsor: Howmedica, Inc. $20,000 Nuclear Engineering SEPARATION OF STRONTIUM AND CESIUM FROM REACTOR ION EXCHANGER RESINS, AND THEIR QUANTIFICATION, USING HIGH PERFORMANCE LIQUID CHROMATOGRAPHY AND BETA AND GAMMA SPECTROSCOPY

Participants:

W. A. Jester U. P. M. Senaratne Services Provided: Radiation Counters, Laboratory Space, Low Level Radiation Monitoring Laboratory and HPLC Unit Nuclear reactor ion exchanger resins, once spent, contain a variety of cations and anions adhered to them. Among the host of cations are strontium (notably 89Sr and 90Sr) and cesium (notably 137Cs).

The object of current research is to perfect a technique by which this strontium and cesium may be extracted from the resins, separated from the other cations present in the resulting extract, and quantified. The proposed methodology is briefly described in the following paragraphs.

Initially, all the cations adhering to the resin are extracted using a solvent such as potassium nitrate ]

or hydrochloric acid, of suitable concentration. This results in an extract comprising all the cations I in a solvent matrix. A sample of this extract is then injected into a High Performance Liquid Chromatograph (HPLC) unit, and with the use of an appropriate eluent, the strontium and cesium fractions are separated and collected. Since the concentrations of these cations in the extract are !'

invariably low, the addition of a non radioactive carrier may be necessary to separate each cation by detecting them conductivity-wise using the HPLC unit. Finally, the fractions are counted using a i suitable radiation detector, so that quantification may be accomplished.

Currently, the extraction of cations from the resins has been successfully accomplished. The j eluent and the regenerant required for the separation of strontium from the other cations in the !

presence of the solvent matrix have been identified, together with the optimum concentration of the eluent and the regenerant. At present, the possibility of using a scintillation counter to quantify the ;

893r and 90$r present is being investigated. This is to be followed by perfecting similar techniques for separating and quantifying cesium.

Master's Thesis:

Senaratne, U. P. M., and W. A. Jester, advisor. Separation of Strontium and Cesium from Reactor Ion Exchanger Resins, and their Quantification, Using High Performance Liquid Chromatography and Beta and Gamma Spectroscopy.

52

Sponsor: CB Tech, Valley Forge, PA $1,018 Nuclear Eneineerine l CALIBRATION OF NEW DIFFUSION BARRIER CHARCOAL CANISTERS FOR THE LLRML RADON MONITORING SERVICE

Participants:

W. A. Jester H. Senaratne Services Provided: Radon Calibration Chamber, NaI(tl) Radon Counter and Laboratory Space During this year, Ms. Harsha Senaratne has been calibrating the LLRML's diffusion barrier i chan:oal canisters that have better radon adsorption characteristics then the current open face !

charcoal canisters. This work involves the exposure of canisters to a known radon concentration for a known amount of time and a known relative humidity. The resulting data will be used to generate a set of calibration curves that will be used to convert the lead-214 and bismuth-214 activity detected on the filters along with the canister weight gain information to determine the average radon concentration of the monitored location.

l Nuclear Engineerine l

A STUDY OF THE RADIATION LEVELS IN AND NEAR THE PENNSYLVANIA '

STATE UNIVERSITY BREAZEALE NUCLEAR REACTOR FACILITY

Participants:

W. A. Jester N. K. Umisedo R. W. Granlund Service Provided: Laboratory Space Ms. Nancy Umisedo is a visiting scientist from the Institute de Fisca da Universidade Sao Paulo, Brazil. She is working at the Low Level Radiation Monitoring Laboratory on a project designed to i

determine the sources of radiation fields at certain locations near the Pceazeale Nuclear Reactor Facility. Health Physics TLD Measurements indicate that certain locations have higher than expected activity and that this activity does not seem to be related to the operation of the Nuclear Reactor. This project is designed to determine the sources of these low intensity radiation fields.

Nuclear Engineering RESEARCH IN ENVIRONMENTAL MONITORING FOR IODINE-129 NEAR POWER PLANT AND WASTE DISPOSAL SITES

Participants:

W. A. Jester R. H. Yahner J. Kwon l

Services Provided: Neutron Irradiation, Radiation Counters, Laboratory Space and Low Level Monitoring Laboratory The objective of this project is to develop a method for the detection ofiodine-129 in the radioactive environment near nuclear power plants and waste disposal sites. Iodine-129, the longest lived radioisoup of iodine, has a half-life of 1.57 x 10 years. Because ofits very slow 53

rate of decay, and since Iodine-129 emits only very low energy beta and gamma radi anoa, a. wate detection and measurement are difficult and tedious. It can be detected most readile in animai and human thyroid glands, since these endocrine organs exhibit the highest concentrations of iodia -

Accordingly, the thyroids of the environmental animals can be suitable samples for the detection s.f radioactive iodines.

The thyroid usually contains iodine in the form of organically bound iodide. Several procedures are being considered for the separation ofiodine from organic materials and for preparing the resulting samples for neutron activation analysis. One of the possible methods being considered is to employ wet chemistry. The other new analytical approach involves the use of high performance ion chromatography (HPIC).

Once the iodine in the thyroid has been isolated it will be analyzed using neutron activation. The high analytical sensitivity for iodine-129 by neutron activation analysis permits concentration measurements at levels much lower than those obtained by the direct monitoring ofiodine-129 radiation.

Nuclear Engineerine NUCE 450, RADIATION DETECTION AND MEASUREMENT Panicipants: W. A. Jester M. H. Voth H. Gougar U. Shoop Services Provided: Neutron Irradiation, Radiation Counters and Laboratory Space NucE 450 introduces the student to many of the types of radiation measurement systems and associated electronics used in the nuclear industry as well as many of the mathematical techniques used to process and interpret the meaning of measured data. The major accomplishments of this year is the revising of five experiments in NucE 450 (and four experiments in NucE 451) to use i five new model 486 personal computers and interfaces. The radiation instruments studies in this l course include, GM detectors, gas flow proportional counters, NaI(tl) detectors, BF3 counters, ion chambers, wide range GM detectors, and surface barrier detectors. The data collection and analysis techniques studied include radiation counting statistics, gamma ray and charged particle spectroscopy, and the interfacing of computeres with nuclear instrumentation.

1 Publication: 1 Edwards, R. M., and W. A. Jester. Evolution of Nuclear Engineering Laboratory Courses at the Pennsylvania State University. Trans. of Am. Nucl. Soc. ISSN: 0003-018X, TANSO 70 1-458, 28-29, 1994.

Nuclear Engineering POST IRRADIATION INSPECTION AND TESTING OF NEUTRON ABSORBER MATERIALS

Participants:

D. Kline D. Vonada K. Lindquist Services Provided: Neutron Irradiation and Laboratory Space 54

1 The purpose of this work is to quantitatively characterize the in-service physical properties of neutron absorber materials used in spent fuel storage racks and shipping casks. Utilities use surveillance coupons of neutron absorber materials such as BORAFLEX, BORAL, borated j graphite and NEUTRASORB borated stainless steel to track the performance of these materials in (

l casks and racks. The coupons are tested with respect to dimensional changes, weight changes, hardness changes, density changes, changes in dynamic shear modules and neutron attenuation characteristics. The latter measurements are performed in the Neutron Beam Laboratory.

Sponsor: Various Electric Utilities l l

. i Nuclear Eneineerine 1

DISSOLUTION RATE OF THE NEUTRON ABSORBER MATERIAL BORAFLEX

Participants:

D. Kline D. Vonada K. Lindquist Services Provided: Laboratory Space and Technical Support This project's objective is to quantify the dissolution rate of Boraflex, a polymer-based neutron ,

absorber material, in simulated spent fuel pool environments. The test conditions include different temperature, irradiation exposure and the presence of solubility inhibitors. The data are used as the basis for a computer mcdel of Boraflex in the spent fuel pool environment.

Sponsor: Electric Power Research Institute Nuclear Eneineerine DEVELOPMENT / TESTING OF A DEVICE TO MEASURE THE BORON-10 AREAL DENSITY IN SPENT FUEL RACK NEUTRON ABSORBER MATERIALS

Participants:

D. Kline D. Vonada K. Lindquist M. Harris Services Provided: Neutron liradiation and Cobalt-60 Facility This project started with proof-of-principle testing in the Neutron Beam Laboratory. Based on the results of these tests, a proto-type measurement device was designed and fabricated. The proto-type equipment is being tested in the Cobalt-60 pool. After this initial testing, the device will be shipped to a utility for testing in a spent fuel pool.

Sponsor: Electric Power Research Institute J

55

B. OTHER UNIVERSITIES, ORGANIZATIONS AND COMPANIES UTILIZING THE FACILITIES OF THE RADIATION SCIENCE AND ENGINEERING CENTER 1

1 University or Industry Type of Use AmericanInspection Agency Environmental Analyses !

Armed Forces Radiobiology Research Institute Neutron Activation Analyses l Reactivity Computer l Bettis Labs, Westinghouse Neutron Radiography BH Labs Environmental Analyses ,

Biopore Inc. Gamma Irradiation l BoswellWater Authority Environmental Analyses CB-Tech Neutron Activation Analyses ,

Centre Analytical Environmental Analyses l Control for Environmental Pollution, Inc. Radiological Analyses E-Systems SemiconductorIrradiation l Gannett Flemming Environmental Analyses GeochemicalTesting Environmental Analyses Harris Semiconductor Semiconductor Irradiation Howmedica Radiological Analyses Indiana University of Pennsylvania Neutron Activation Analyses Isotec Incorporated Neutron Activation Analyses Macrobac Bradford Environmental Analyses Morgan Matroc Limited Radiological Analyses Muscle Shoals Minerals, Inc. Radiological Analyses North American Refractories Radiological Analyses Northeast Technology Corporation Neutron Radiography Nuclear Regulatory Commission Reactor-Reactivity Insertion Transients Pottsville Environmental Testing Lab Environmental Analyses Raytheon Semiconductor Irradiation SEhfIECH Gamma Irradiation ,

St. Mary's City Museum Neutron Radiography l Neutron Activation Analyses Tracerco Isotopes for Tracer Studies Tru-Tec Isotopes for Tracer Studies l United Water of Pennsylvania Environmental Analyses i University of Maryland Perturbed Angular Correlation j Neutron Activation Analyses US Bureau of Mines Gamma Inadiation I l

1 56 l

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.- APPENDIX A Personnel Utilizing the Facilities of the Penn State RSEC. l Faculty (F) Post-Doctoral (PD), Staff (S), Graduate Student (G), Undergraduate (U),

Visiting Faculty (VF), Visiting Staff (VS)

~

SCdLLEGEidF/AGRICULTUNE6 iCdLLEGE DF ENGINEERINds i

l Food Science Electrical Engineerine l Beelman, Robert (F) Garcia, Humberto (G)

Murinda, Shelton (G) Lee, K. Y. (F) i Roberts, Robert (F) Miller, David (F)

Wilson, Richard (F) Ramaswamy, P. (G)

Forest Resource Laboratory Mechanical Engineerine )

l Cole, Andrew (S) Kim, Byoung-Su (G) l Prescott, Patrick (F) l Plant Pathology Ray, Asok (F) l Singh, V. K. (G) <

Juba, Jean (S) Weng, Chen-Kao (G) l Nelson, Paul (F)

Nuclear Engineerine Wildlife Management Adams, James (G)

Yahner, R. H. (F) Alpan, Arzu (G)

Basha, Hassan (G)

Baratta, Anthony (F)

Boyle, Patrick (S) l Bryan, Mac (S)

Catchen, Gary (F)

L

$dDLLEGF) F EdRTH AND?

? Cumblidge, Steven (U) iMINERALLSCIENCES; Cecenas Falcon Miguel(G)

Daubenspeck,Thierry (S) I Davison, Candace (S)

Materials Science and Encineerine Edwards, Robert (F) !

Feltus, Madeline (F) ,

Purdy, Dave (G) Flinchbaugh, Terry (S) l Fowler, Dave (G) l Metals Science and Engineering Gougar, Hans (G) l Gould, Robert (F)

Ryba, Earle (F) Grieb, Mark (S)

Haghighat, Ali (F)

Fuel Science Harbach, Brian (U)

Hollinger, Ed (G)

Li, John (G) Hughes, Dan (F) i Idris, Faridah (IAEA)

Jester, William (F)

Johns, Richard (G) i Kahn, Saif (G) l Kenney, Edward (F) l Kenney, Stephen (G) l Kim, Young-Su (G) !

Klevans. Edward (F) l 57

APPENDIX A *

(Continued)

Personnel Utilizing the Facilities of the Penn State RSEC.

Faculty (F) Post-Doctoral (PD), Staff (S), Graduate Student (G), Undergraduate (U),

Visiting Faculty (VF), Visiting Staff (VS)

' TCdELEdFf0FkENGINEERINd;3 1 jiCDULEdEbfSdlENhEh %

Nuclear Eneineerine Biology Kwon, Junhyun (G) Lai, Zhi-Chun (F)

Lebiedzik,Jana (S) Li, Ying (G)

Lee, Kwangho (G)

Lunetta, Lois (S) Chemistrv

Meyers, Gary (U)

Miller, David (S) Allcock, Harry (F)

Morlang, Mike (G) Ambrosio, Archel (G)

Moyer, John (U) Dudley, Gary (G)

Norland, Mark (G) Morrisey, Chris (G)

Paesano, Andrea (VF) O'Connor, S. M. (PD)

Page, Danielle (U) Olmeijer, D. (G)

Peagier, Maurice (S) Olshavsky, M. (G)

Power, Mike (G) Primrose, Aaron (G)

Rearick, Todd (G) Silverberg, Eric (G)

Rudy, Kenneth (S) Visscher, Karyn (PD)

Sanchez, Roberto (G)

Senaratne, Harsha (VS) Biochemistrv and Molecular Bioloey Senaratne, Uditha (G)

Shabalin, Evgueni (VF) Abmayr, Susan (F)

Shoop, Undine (G) Bour, Barbara (G)

Soucy, Scott (U) Erickson, Mary Ruth (G)

Turso, James (G) Grill, M. (S)

Umisedo Nancy (VS) Heyser, Deidre (S)

Voth, Marcus (F)

Wulsch, Dan (G) Phvsics Witzig, Warren (F)

Wright, Bob (U) Dimeo, Rob (G)

Xu, Xiangjun (G) Fu, Jiaming (G)

Zhao, Yangping (G) Sokol, Paul (F)

School of Engineering Technology and S th a a an ushy F Health Physics ICOLLEGE OF;LIBERAD ARTSL Boeldt, Eric (S)

Granlund, Rodger (S)

Hollenbach, Donald (S)

Anthroooloey Hirth, Kenneth (F) 58

- APPENDIX A (Continued) l l

, 1 L. INDUSTRIES American Inspection Agency ........................ Harris, George Armed Forces Radiobiology ........................ George, Robert Research Institute ........................ Miller, Steven

........................ Moore, Mark Bettis Labs, Westinghouse ........................ Glickstein, Stan

........................ Murphy, Jack BH Labs .............. . ....... Brunk, Scott Biopore, Inc. . ................ . ... Gill, S.

CB-Tech ... ............ ....... Bleistein, Charles Centre Analytical ........................ Robb, Shawn Control for Environmental Pollution, Inc. ........................ Acres, Samuel E-Systems ........................ Dobson, Robert Uber, Craig Gannett Flemming ... ............. .... Lane, David

.......... ........ .... Abbe, Dough GeochemicalTesting ..... . ................ Gearhard, Susan Harris Semiconductor . .. ....... .. . . .. Borza, Peter

...... . .. .... .. Kalkbrenner, F.

Howmedica .... ...... . . ... .. Wang, Kathy Isotec Incorporated .. ... ..... ..... . . Smith, Keith Microbac Bradford .... . .. .. ... .. .. Anderson, J. L.

Morgan Matroc Limited ...... ..... ......... Murray, Michael l Muscle Shoals, Inc. ... . ............... . Kreig, Mitch North American Refractories .. .. ... .............. Wealand, L.

Northeast Technology Corporation .... ........... ....... Harris, Matt

..... ........ ........ Kline, Don

..... ........ ......... Lindquist, Kenneth O.

............ ...... ... Vonada, Doug Nuclear Regulatory Commission ..... .................. Ebert, Dave Pottsville Environmental . .. ............ .. Sobian, Michael Raytheon ..... . .. .. ....... Bibalt, Jacques

. . ..... ........ . Black, Bruce

.... .................. Diette, R.

.. .. ........... ...... Enriquez, Guido

. ...................... Guravage, John

.... ................. . Lieto, Tony

........... ........ . Mulford, Stewart

........................ Stransky, D. F.

SEMTECH ............ ........... Manders, Sharon St. Mary's City Museum ....... . ........ . .. Harry, Silas D.

..... ... ...... .. .... Miller, Henry Tracerco . ... ... ....... .. Bucior, Dave Tru-Tec .. .. . .......... Bothe, Mike

. . . ..... .. ...... Kolek, Jerome

. . . .... . .. .. . Flenniken, Mike US Bureau of Mines .... . . .. . ... . Brickett, Lynn 59

APPENDIX A .,

(Continued) -

. s w:@

y' ? UNIVERSITIES '.. - - + < T University of Maryland Ondov, John Professor of Chemistry University of Maryland Rasera, Robert L. Professor of Physics Indiana University of Pennsylvania - Fazio, Frank Professor of Chemistry Indiana University of Pennsylvania Hanwig, Quentin Professor of Biology

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=w LLRML - Radon in air and water analyses for various individuals Various Cobalt - 60 irradiations for high school classes' research projects.

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APPENDIX B FORMAL TOUR GROUPS JULY 1994 NUMBER OF

.IUNE 1995 M NAME OF TOUR GROUP PARTICIPANTS l July 1 Vectour Group 20 8 Aerospace Engineering 9 11 Nuclear Concepts 23 l 13 IHI EPRI 5 14 Vectour Group 26 1 16 Alumni Reunion 36 20 BEST Program 26 21 Vectour Group 22 21 Atoms Program 49 21 Water Systems Group 15 25 Science Tech. & Soc. Class 18 27 SSPS Engineering 12 27 Upward Bound 44 28 Atoms Program 52 28 Vectour Group 9 29 Enter 2000 36 August 2 Human Resources 4 3 Aerospace Engineering 8 4 Vectour Group 20 4 Atoms Group 42 11 PSUTransportation Academy 11 ,

18 Denmark Physics Students 2 (

23 Fall 1994 Freshmen Tour 2 l 30 Emergency Plan Drill Critique / Police Services 2 September 8 Food Science 21 12 Harris Township Lions Club 18 13 Naclear Engineering Student Tour 7 21 DER /RRT 15 22 Alumni Fellow 2 22 Russian Guests 5 23 Programs Office Tour 2 26 Bio Science III Class 16 October 1 Fall 1994 Open House 145 4 Harrisburg Academy 29 6 Ben Ten 19 6 Science and Technology 420 18 7 Harmony High School 23 7 IU-9 50 10 Scholars and Parents 5 10 Outstanding Alumnus 1 17 Pennsylvania Planning Group 4 18 497-D Tour 7 19 497-D Tour 7 20 FERMI Meeting 5 61

APPENDIX B FORMAL TOUR GROUPS (Continued)

JULY 1994 NUMBER OF .

.IUNE 1995 M NAME OF TOUR GROUP PARTICIPANTS October 20 NRC Representative 1 26 Ferguson Elementary School 56 28 Ferguson Elementaty School 51 31 PA Jr. Science Symposium 41 November 3 Engineering 100 Freshmen 9 7 American Institute of Chemical Engineering 4 9 Glendale High School 53 t 14 State College High School-Chemistry Class 8 15 Science and Technology-200 Open House 82 16 IU-9 Gifted Students 7 18 Williamson High School 31 21 Greensburg Salem High School 39 December 1 Lock Haven University 4 12 Catchen's Research Group 5 15 DuBois Physics Class 3 16 Carlisle High School 70 January 19 College of Engineering Dean's Office Personnel 3 19 Police Services Training 22 19 PotentialGraduate Student 1 27 Evaluation Committee 5 February 1 NucE 444 Class Tour 19 2 Police Services Training 20 3 E-Mech 440 Class Tour 13 7 Civil Engineering 270 12 8 Civil Engineering 270 10 9 Civil Engineering 270 20 17 Com 486 4 March 1 Germantown Friends School 10 6 Redlands High School 19 13 Berwick High School 14 15 Bermudian Springs High School 16 e 18 Upward Bound 14 20 Daniel Boone High School 13 21 Intelligent Control Workshop #11 15 22 Eastem Lebanon High School 8 22 Peters Township High School 18 24 Nuclear Engineers - NE 401 3 28 NucE 401 Console ROT 5 28 State College High School 42 29 Cumberland Valley High School 10 31 Jersey Shore High School 10 April 1 Spring 1995 Open House 225 4 Graduate Tour 21 62 ;

APPENDIX B FORMAL TOUR GROUPS (Continued)

JULY 1994 NUMBER OF

.IUNE 1995 M NAME OF TOUR GROUP PARTICIPANTS April 5 Loyalsock High School 19 ;

5 Bradford High School 35 )

10 Portage High School 8 12 Lewistown High School 2 i 12 Harbor Creek High School 11 29 l 19 Carmichaels High School 21 East Stroudsburg High School 11 25 Boy Scout Tour Group 32 27 Franklin Area High School 22 28 Ridgeway and St. Mary's High School 47 i May 1 Nonhem Bedford High School 19 l 2 Indiana University of Pennsylvania 9 4 Marion Center High School 10 5 Camp Hill High School 10 8 Westmont Hilltop High School 13 10 Somerset High School 22 j 12 Berlin High School 8 12 Dallastown High School 16 15 Bensalem High School 1 l 15 Muncy High School 24 ;

17 PSU Computer and Information Systems 15 !

l 18 General Public Utilities 7 22 Sacred Heart Fifth Grade 25 23 State College High School 18 26 Bucks County (Council Rock High School) 4 29 Twin Valley High School 34 June 6 Clifton Fine High School 7 22 GPU Course 25 22 Vectour 23 23 Transpon Conference 6 28 MEA Project 6 29 Vectour 21 29 GPU NCTII 4 30 Wise Group 37 30 High School Summer Interns 10 63

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