ML20078S691

Forwards Thirty-Ninth Annual Progress Rept, of Penn State Breazeale Reactor

ML20078S691
Person / Time
Site:	Pennsylvania State University
Issue date:	12/16/1994
From:	Voth M PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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PENNSTATE a' C if a .

College of Engineering Breascale Nuclear Reactor Building Radiation Science and Engincenng Center The Penn33lvania State University Uniseruty Park. PA 16802-2301 Annual Operating Report, FY 93-94 PSBR Technical Specifications 6.6.1 License R-2, Docket No. 50-5 December 16,1994 U. S. Nuclear Regulatory Commission Attention: DocumentControlDesk Washington, D. C. 20555 Dear Sir; Enclosed please find the Annual Operating Report of the Penn State Breazeale Reactor (PSBR).

This report covers the period from July 1,1993 through June 30,1994, as required by technical specifications requirement 6.6.1. Also included are any changes applicable to 10 CFR 50.59.

A copy of the Thirty-ninth Annual Progress Report of the Penn State Radiation Science and Engineering Center is included as supplementary infom1ation.

Sincerely yours, hh0k Marcus H. Voth Director, Radiation Science and Engineering Center Enclostires cc: RegionI Administrator U. S. Nuclear Regulatory Commission D. A. Shirley 9412290132 9412'6 /

PDR ADOCK 05000005 R PDR p An Equal opportunity University I

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PENN STATE BREAZEALE REACTOR Annual Operating Report, FY 93-94 PSBR Technical Specifications 6.6.1 License R-2, Docket No. 50-5 Reactor Utilization 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:

EDUCATION utilization is 3rimarily in the form oflaboratory classes conducted I

for graduate and undergraduate stuc ents and numerous high school science groups.

These classes vary from neutron activation analysis of an unknown sample to the calibration of a retetor control rod. In addition, an average of 2000 visitors tour the PSBR facility each year. j RESEARCH accounts for a large portion of reactor time which involves l Radionuclear Applications, Neutron Radiograpy, a myriad of research programs by faculty and graduate students thmughout the University, and various applications by the industrial sector.

TRAINING programs for Reactor Operators and Reactor Supervisors are i continuously offered and are tailored to meet the needs of the participants. Individuals taking part in these programs fall into such categories as power plant operating personnel, graduate students, 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 Technical Soecifications reauirement 6.6.1.a.

Between July 1,1993 and June 30,1994, the PSBR was critical for 601 hours0.00696 days <br />0.167 hours <br />9.937169e-4 weeks <br />2.286805e-4 months <br /> or 2.4 hrs / shift suberitical for 362 hours0.00419 days <br />0.101 hours <br />5.98545e-4 weeks <br />1.37741e-4 months <br /> or 1.4 hrs / shift used while shutdown for 386 hours0.00447 days <br />0.107 hours <br />6.382275e-4 weeks <br />1.46873e-4 months <br /> or 1.5 hrs / shift not available 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> or 0.6 hrs / shift Total usuage 1511 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.749355e-4 months <br /> or 5.9 hrs / shift The reactor was pulsed a total of 48 times with the following reactivities:

less than $2.00 18

$2.00 to $2.50 30 greater than $2.50 0 The square wave mode of operation was used 68 times to power levels between 100 and 500 KW.

Total energy produced during this report period was 391 MWH with a consumption of 20 grams of U-235.

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Unscheduled Shutdowns .

Technical Soccifications reauirement 6.6.1.b.

The 3 unplanned scrams during the July 1,1993 to June 30,1994 period are described below.

Agust 9,1993 - Reactor scram (initiated by DCC-X control computer) at 1.05 MW.

The reactor operator noticed noise on the pool temperature dis 31ay when moving the transient rod (a problem previously noted). The three licensec. persons m the control room at that time decided to switch from 3-rod to 2-rod auto contml to see if the noise would appear when bumping the safety rod. Upon going to 2-md auto, the auto system began to unbalance rods by shimming out the safety rod. The operator then switched back to 3-rod auto, and as the safety inserted and the shim and reg rods withdrew, the power spiked enough for the scram to occur. A review of the function of the auto contml system was pmsented at a staff meeting, and SOP-1, Reactor Operating Pmeedure, was modified to require 3-rod auto when using auto above 900 kW.

I May 10,1994 - Reactor scram at 20 kW when the operator staned the N-16 pump prior ,

to a planned increase in reactor power. The N-16 pump breaker had been thrown earlier  !

in the day while the staff investigated the wiring to plan for the upcoming bridge  ;

modification. Although the pum ) normally starts automatically when approaching 200  :

kW, the operator wanted to test tle pump before increasing power since he knew the ,

breaker had been thrown and reset. For a few days, an administrative requirement was  !

imposed requiring the operator to start the pump manually at standby before starting up since it was thought that the pump coming on automatically could also cause a scram. l Effons, with the reactor shutdown or at standby, to duplicate conditions to cause a repeat of the scram were unsucessful.

May 17,1994 - While suberitical during an approach to critical experiment, the operator scrammed the reactor when high and broad spikes were noted on the Wide Range monitor. No cause for the spikes were found but moisture in the fission chamber  :

cannister was suspected; the cannister was pressurized with nitrogen gas and no further noise spikes have been noted.

Major Maintenance With Safety Significance I Technical Specifications requirement 6.6.1.c, l On June 3, while unloading the core as pan of the fuel inspection-bridge modification project, element # 205 in core position H-11 would only come one-third to halfway through the upper grid plate. At this time the remaining fuel elements and control rods were removed from the core. All efforts to remove the element were unsuccessful and it was obvious that the only other option would be to raise or remove the top grid plate.

On June 6, the reactor tower was removed from the reactor bridge and suspended in the reactor pool. The reactor bridge was dismantled and moved to the Cobalt-60 facility for modification. On June 9, the reactor tower was raised and supported across the instrument bridge at the pool divider wall to provide better access to loosen the to) grid plate. The top grid plate was about 50 inches under the water surface with the raciation reading at the water surface about 10 mrem /hr. The four hex nuts that hold the top grid plate were loosened and raised but not removed from threaded grid plate support posts.

The front part of the grid plate was loosened from the suppon posts but the back part of the grid plate was stuck fast. Several techniques were used unsuccessfully to try to loosen the grid plate; finally, jacks were inserted between the top and bottom grid plates to apply an upward evenly distributed force on the top plate while a slide hammer attached altemately to thejacks provided an impact. This method loosened the grid plate and the four hex nuts were then removed completely and the top plate raised enough to slide the element to the central thimble grid plate opening. The fuel handling tool was then used to remove the element from the core. Before the jack-slide hammer method was attempted,

3 the fuel element was placed in a weighted protective sleeve which also then allowed movement of the element to the central thlmble grid plate opening.

Major Changes Reportable Under 10 CFR S0.59 Technical Soecifications reauirement 6.6.1.d.

Facility Changes November,18,1993 - PROTROL configuration files (PROTROL is the language used in the reactor computer control system) related to the Local Area Network (LAN) were modified. This was to complete a ?roject to allow historical trends to be displayed on the LAN monitors in the west stairwell of the reactor building and the emergency support centerin a building next door.

June 1994 - the reactor bridge was modified to allow for rotational and lateral (east-west) motion to complement the original nonh-south motion. The purpose of the change was to  !

allow access for several permanent experimental facilities anc access to all of the seven ,

beam tubes, i l

To accomplish this modification, the reactor fuel was moved from the core to storage .  !

racks. Then all core detectors and associated equipment and wiring were removed. The reactor tower and grid plate assembly was then removed as a unit from the reactor bridge and supported across the pool divider wall. The floor and railing and other items were ]

them stripped from the reactor bridge so that only the sub-base and wheel assembly -l l remained. What remained of the reactor bridge was moved from the reactor bay and 1 modified by adding linear bearings to support translating beams to which a deck plate bearing support assembly was attached. The translating beams move on the linear i bearings to pmvide east-west movement. The deck plate bearing support assembly at the end of the translating beams holds the bearings to which a tower connection plate is i fastened. His allows the tower connection plate and the attached reactor tower to rotate. )

The old reactor tower and grid plate assembly were reused.

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l Safety analyses for structural safety margins were done for the reactor tower and grid I plate assembly and for all new bridge components. Previous radiation exposure history

! was taken into account in the analyses of the reactor tower and grid plate assembly. Load l tests were performed on the new reactor bridge, translating beams, and deck plate bearing i support assembly before the reactor tower was re-attached.

l The Penn State Reactor Safeguards Committee (PSRSC) approved the final design before i installation. Presently, reactor operation is limited to only the pool positions allowed by j

the previous bridge. As new experimental needs arise, PSRSC review and approval is required for operation in other pool positions.

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 requirement 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 I - -

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4 f recycled for pool water makeup. The evaporator concentrate is dried and the solid salt l residue is disposed ofin the same way as other solid radioactive waste at the University.

l Liquid radioactive waste from :he radioisotope laboratories at the PSBR is under the '

Umversity byproduct materia's license and is transferred to the Health Physics Office for i dis x> sal with the waste fmm other campus laboratories. Liquid waste dis x> sal

! tec miques include storage for decay, release to the sanitary sewer as per L0 CFR 20, and

solidification for shipment to licensed disposal sites.

Gaseous

, The only gaseous effluent is Ar-41, which is released from disolved air in the reactor pool  ;

i water, dry irradiation tubes, and air leakage from the pneumatic sample transfer systems. l

, The amount of Ar-41 released from the reactor pool is very dependent upon the operating ,

J power level and the length of time at power. The release per MWH is highest for l extended high power runs and lowest for intermittent low power runs. The concentration 1 of Ar-41 in the reactor bay and the bay exhaust was measured by the Health Physics staff 3

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 290 mci and 880 mci of Ar-41 is calculated for July 1,1993 to June 4 30,1994, resulting in an average concentration at ground level outside the reactor j j building that is 0.9 % to 2.8 % of the effluent concentration limit in Appendix B to 10  !

l CFR 20.1001 - 20.2401. The concentration at ground level is estimated using only i dilution by a 1 m/s wind into the lee of the 100 m2 smallest cross section of the reactor >

l j bay. The effluent concentration limit which came into effect in January 1994 was used in '

this estimate. The concentration limit was actually 4 times higher for the July - December

] 1993 period.

1 i During the report period, several inadiation tubes were used at high enough power levels j and for long enough runs to produce significant amounts of Ar-41. 'Ihe calculated annual j production was 97 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 l released to the reactor bay. The irported releases from dissolved air in the reactor pool i i are based on measurements made,in part, when a dry irradiation tube was in use at high 3

power levels; the Ar-41 releases from the tubes are part of rather than in addition to the j release figures quoted in the previous paragraph. The use of the pneumatic transfer  !

systems was minimal during this period and any Ar.41 releases would be insignificant l

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

j Environmental Surveys l Technical Specifications requirement 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 j miles away. This reporting year's measurements (in millirems) tabulated below represent

the July 1,1993 to June 30,1994 period. A comparison of the North, West, East, and South fenceline measurements with the control measurements at Houserville (1 mile l away) and Bellefonte (10 miles away) show the differences to be similar to those in the  !

1 past.

I j ist Otr 2nd Otr 3rd Otr 4th Otr Total i Fence North 24.7 26.2 18.7 20.2 89.8 i Fence West 21.8 21.7 15.5 18.9 77.9 Fence East 25.0 23.3 18.0 21.3 87.6 Fence South 21.1 22.5 16.6 18.4 78.6 s Control-Houserville 17.9 17.9 15.0 15.8 66.6 i

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5 Personnel Exposures .

Technical Soecifications rea.uirement 6.6.1.e.

No reactor personnel or visitors received dose equivalents in excess of 25% of the permissible limits under 10 CFR 20. ,

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PENNSTATE eme 1

I RADIATION SCIENCE AND ENGINEERING CENTER COLLEGE OF ENGINEERING THIRTY-: NINTH AXNEAL PROGRESS REPORT I l

AUGUST 1994 l CONTRACT DE-ACO7-761 DO 1570 SUBCONTRACT C88-101857 U.Ed. ENG 95-29 g y . p -- .- . . , - ,

S THIRTY-NINTH ANNUAL PROGRESS REPORT PENN STATE RADIATION SCIENCE AND ENGINEERING CENTER I

l July 1,1993 to June 30,1994 Submitted to:

United States Depanment of Energy and The Pennsylvania State University By:

i Marcus H. Voth (Director)

Terry L. Flinchbaugh (Editor)

Penn State Radiation Science and Engineering Center Depanment of Nuclear Engineering )

The Pennsylvania State University

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University Park,PA 16802 August 1994 l

l Contract DE-AC07-76ID01570 Subcontract C88-101857 U.Ed.ENG 95-29 l

l PENNSTATE University Park Campus i

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STATEMENT OF NONDISCRIMINATION '

j The Pennsylvania State University is committed to the policy that all persons shall have equal

! access to pr characterisu,ograms, cs not related facilities, admission, or to ability, performance, and employment qualifications without regard as determined to personal 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, ,

i religious creed, sex, sexual orientation, or veteran status. Direct all affirmative action inquiries to j the Affinnative Action Office, The Pennsylvania State University,201 Willard Building,

University Park, PA 16802-2801;(814) 863-0471.

i j 1his publication is available in altemative media on request.

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TABLE OF ' CONTENTS Easc PREFA CE - M . H. Vo th . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v I . INTRODU CTION - M. H. Voth . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 II. PER S ONNE L - T. L. Flin chbau gh ........ .. .. ... ........ .... ....... .... .... ................ 3 III. REACTOR OPERATIONS - T. L. Flinchbaugh . . .. . . .. . . .. . . .. . . . ... . .... .. ..... .. ...... 7 IV. GAMMA IRRADIATION FACILITY - C. C. Davison . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . .. 11 V. EDUCATION AND TRAINING - T. L. Flinchbaugh, C. C. Davison ................. 13 VL NEUTRON BEAM LABORATORY D. E. Hughes ..................................... 19 VIL RADIONUCLEAR APPLICATIONS LABORATORY - T. H. Daubenspeck ........ 21 VIIL LOW LEVEL RADIATION MONTIORING LABORATORY - M. Peagler ........... 23 )

IX. ANGULAR CORRELATIONS LABORATORY - G. L. Catchen ..................... 25 X. RADIATION SCIENCE AND ENGINEERING CENTER RESEARCH UTILIZATION - T. L. Flinchbaugh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 l

l A. Penn State University Research Utilizing the Facilities l 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 gineering Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 j APPENDIX A. Faculty, Staff, Students, and Industries Utilizing the Facilities of the i Penn State Radiation Science and Engineering Center - T. L.  !

Fli nch ba u gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 l APPENDIX B. Formal Group Tours - L. D. Large . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 iii

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E 1 Personnel..................................................................................... 4 l

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t 2 R e ac tor Opera tio n D at a . .. . . . . . . .. . . .. . . . . . . . . . . . . . . . . . .. . .. . . ... . .. . . . .. .. . . . .. . .. . . .. . . .. .. . 9 .

3 Reactor Utili zation Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4 Cobalt-60 Utili7a tion Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 5 College and High S chool Groups . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 FIGURES Eig n Eags 1 Organization Chart . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 i

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

! School. De reactor and associated laboratories are available to all Penn State colleges for

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

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The hirty-Ninth Annual Progress Report (July 1993 through June 1994) of the operation of The Pennsylvania State University Radiation Science and Engineering Center is submitted in accordance with the requirements of Contract DE-AC07-76ID01570 between the United States l Department of Energy and EG&G Idaho, Incorporated, and their Subcontract C88-101817 with The Pennsylvania State University. This report also provides the University administration with a summary of the utilization of the facility for the past year.

l Numerous individuals are to be recognized and thanked for their dedication and commitment in this repon, especially Terry Flinchbaugh who edited the report and Lisa Large 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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1 I. INTRODUCTION ne 1993-94 year was another year filled with significant accomplishments by the Radiation Science and Engineering Center staff and users. This report tabulates the number of users, experiments performed, and hours of operation along with summaries of the nature of work perfonned and its significance. Highlights among the year's accomplishments are discussed below: '

. A reactor bridge modification was completed which allows transverse and rotational motion of the reactor core in addition to the lateral motion allowed by the original design. This marked the culmination of four years of planning for funding (with assistance from the Department of Energy), design (with assistance from Dr. Dhushy Sathianathan and his i mechanical engineering students), and construction / installation (done entirely by the RSEC l staff). Dan Hughes managed the project from conceptual design through installation. The Breazeale Reactor now has unique experimental capabilities for an increased number of stationary experiments and for neutron beam research and bench marking.

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- Work continues on the Argonne National Laboratory sponsored cold neutron irradiation facility which utilizes the rotating core concept.

. He Bettis Laboratory flow studies using neutron radiography have produced impressive results. Studies for improved beam strength are planned using the rotated core and an optimized thermal column design.

• Arrangements were made to replenish the cobalt-60 inventory through shared funding with the primary users of that facility, the Colleges of Engineering, Science, and Agriculture.

. The RSEC hosted three International Atomic Energy Agency fellows, two who spent a full semester in training and research.

. Neutron activation analysis performed to identify remains found in lead-lined coffins in St.

Mary's City, MD, provided Penn State national media attention.

. A workshop showcasing Dr. Edward's research on advanced controls applied to a TRIGA reactor drew prominent attendance. As a follow-on, an American Nuclear Society topical meeting on Nuclear Plant Instrwnentation, Control, and Hwnan Machine Interface Technologies is planned for 1996.

. The Perturbed Angular Correlation group under Dr. Catchen's direction continued to generate prestigious publications and awards for student presentations. Five of the seven awards at the 1994 American Nuclear Society Student Conference--Central Region were awarded to Penn State Students, two of the winners being from Dr. Catchen's group.

• The NRC inspected the RSEC under each license; reactor, cobalt-60 facility, byproduct materials, and special nuclear materials. Their inspection reports were complimentary with no violations identified.

. An attempt by the NRC to remove the non-profit educational institution exemption from annual fees for regulatory services was successfully opposed, saving the university approximately $130,000 per year.

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I l De Low Level Radiation Monitoring Laboratory scaled back its operation by dropping the analysis services for dnnking water due to increased requirements for certification and the cyche nature of the work.

ne requests for radionuclide production for commercial tracer studies reached a new high.

The RSEC continues to be a major participant in testing borated polymer material which has been a problem for power reactor spent fuel storage racks.

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4 II. PERSONNEL Hermina Boyle resigned as supervisor of the LLRML on March 31,1994. Jana Lebiedzik was

terminated as environmental analyst at that time as the LLRML operation was downsized from a three person to one person operation. Jana had been promoted from wage payroll to environmental j analyst in the LLRML November 1,1993.

6 j Arlene Stewart resigned as Staff Assistant III on September 10,1993. Pam Stauffer, Staff

Assistant VII, returned from a personal leave of absence at that time. Pam had worked two days a

week during the leave, and Lisa Large, Staff Assistant V, had received a temporary promotion to

! assume Pam's duties three days a week.

Mark Grieb was hired as an engineering aide on November 22,1994, to work in the area of i electronic design and repair and as a reactor operator.

i l Eric Sipos resigned as reactor operator intern on March 25,1994. Bryan Vergato resigned as reactor operator intern on May 20,1994. Alex Mclellan was hired as a reactor operator intern on j Febmary 14,1994.

s j Several wage payroll personnel provided support during the year. Joy Moncil provided technical suppcxt in the LLRML. Imis Lunetta, Scott Anderson and Danielle Page provided j support in the educational programs area. Jeff Simons and Matthew Zubris provided clerical

support and Brian Marazi provided support to the engineering services group.

! On January 1,1994, Ward Diethorn (Professor, Nuclear Engineering, Penn State, retired) left

? the Penn State Reactor Safeguards Committee (PSRSC) after serving the maximum two terms

! allowed by the committee charter. His replacement was Warren F. Witzig (Professor and

] Department Head, Nuclear Engineering, Penn State, retired).

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. TABLE I i

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l Eaculty and Staff Ittis H. M. Boyle (resigned) Supervisor, I.ow-Level Radiation Monitoring Lab i

• • P. G. Boyle Reactor Supervisor / Nuclear Education Specialist  ;

• • M. E. Bryan Assistant Research Engineer G. L. Catchen Associate Professor T.Daubenspeck Reactor Supervisor / Reactor Utilization Specialist 1

• • 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 L. D. Large Staff Assistant V J.Lebiedzik (terminated) Environmental Analyst A. J. McLellan Reactor OperatorIntem

• • D. R. Miller Reactor OperatorIntern M. Q. Peagler Environmental Analyst

• K.E.Rudy Operational Support Services Supervisor

• • E. J. Sipos (resigned) ReactorOperatorIntem A. Z. Stewart (resir.,ed) Staff Assistant III P. J. Stauffer Staff Assistant VII B. D. Vergato (resigned) Reactor OperatorIntem

• • M.H.Ve$ 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 D. Page L. Lunetta B. Marazi J. Moncil J. Simons M. Zubris 4

l Penn State Reactor Safeguards Committee i

• W. S. Diethorn Professor, Nuclear Engineering, Penn State (retired) i E. W. Figard Supervisor of Maintenance, Pennsylvania Power and Light Susquehanna Steam Electric Station R. W. Granlund Health Physicist, Intercollege Research Programs and ,

Facilities, Penn State 1 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, 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 i Engineering Center

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

• Served through January 1,1994 l

• • Appointed January 1,1994 l

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L DIRECTOR MANAGER OF STAFF MANAGER OF OPERA 110NS ASSISTANT VII ENGINEERING AND'IRAINING SERVICES I

i STAFF WAGEPAYROLIJ ASSISTANT V WORK STUDY m REACTOR REACTOR SUPERVISOR ASSISTANT RESEARCH SUPPORT RESEARCH SUPERVISOR, SUPERVISOR, OFFACILITY RESEARCH TECHNICIAN-III LLRML ASSISTANT NUCLEAR REACTOR SERVICES ENGINEER EDUCKI1ON UTILIZA110N g SPECIALIST (2) SPECIALIST ENGINEERING AIDE WAGE PAYROLIJ WORK STUDY I I EXPERIMENTAL MACHINIST A AND MAINTENANCE REACTOR MECHANIC OPERATOR INTERN (2)

WAGE PAYROLIJ WORK STUDY FIGURE I RSEC Organization Chalt aS of 6/30/94 D

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III. REACTOR OPERATIONS l

1 l 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 l 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 fmm less than 1 KW to up to 2000 KW for j short (milliseconds) periods of time. TRIGA stands forTraining, Research, Isotope Production, i built by General Atomic Company.

Utilization of the PSBR falls into three major categories:

l 1 Educational utilization is pnmarily in the form oflaboratory classes conducted for graduate and

undergraduate degree candidates and numerous high school science gmups. Rese classes will l 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 l Applications, Neutron Radiography, a myriad of research programs by faculty and graduate j students throughout the University and various applications by the industrial sector.

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Training pmgrams for Reactor Operators and Reactor Suprvisors are offered and can be

tailored to meet the needs of the participants. Individuals takng part in these programs fallinto j such categories as PSBR reactor staff and power plant operating personnel i

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

! the needed shielding and cooling for the operation of the reactor. It is relatively simple to expose a j 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. nree pneumatic transfer systems with l different neutron levels offer additional possibilities. Core rotational, east-west, and north-south j movements provide flexibility in positioning the core against experimental apparatus.

In normal steady state operation at 1000 kilowatts, the thermal neutmn flux available varies

, from approximately 1 x 1013 n/cm2/sec at the edge of the core to approximately 3 x 1013n/cm2/sec j in the centralregion of the core.

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

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

I j STATISTICAL ANALYSIS i

! Tables 2 and 3 list Reactor Operation Data and Reactor Utilization Data-Shift Averages, j 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. He Suberitical time is the total hours that the reactor i key and console instrumentation were on and under observation, less the Critical time. Suberitical i time reflects expenment set-up time and time spent approaching reactor criticality. Fuel movement hours reflect the fact that there were minimal fael movements made this year.

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a j The Number of Pulses reflects demands of undergraduate labs, researchers and reactor

{ operator training programs. Square waves are used primarily for demonstration purposes for i public groups touring the facility, researchers and reactor operator training programs.

The number of Scrams Planned as Part of Expenments reflects experimenter needs. Two j Unplanned Scrams Resulting from Personnel Action occurred; the first was the result of operator

! error in using the auto control system while the second was operator response to a noisy power

! detector. The Unplanned Scram Resulting from Abnormal System Operation was caused by a j noise spike on a fuel temperature channel caused by the N-16 pump.

! Table 3, Part A, Reactor Usage, indicates Hours Critical and Hours Suberitical, and also j Hours Shutdown such as for instruction or experimental setup. Occasionally a component failure  :

1 prohibits reactor operation. The necessary repair time is included in Reactor Usage as Reactor Not j Available to reflect total reactor utilization on a shift basis.

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

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

} INSPECTIONS AND AUDITS i

During September of 1993, a Nuclear Regulatory Commission (NRC) routine inspection was i conducted of the emergency preparedness plan and health physics activities as they relate to the j zeactor R-2 license. No items of non-compliance were identified.

i j During October of 1993, Dennis R. Shaulis, Nuclear Engineer, Philadelphia Electric l Company, conducted an audit of the PSBR. This fulfilled a requirement of the Penn State Reactor l Safeguards Committee charter as described in the PSBR Technical Specifications. The reactor j staff has implemented changes suggested by that report, all of which exceed NRC requirements.

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! During October of 1993, a NRC routine inspection was conducted of activities authorized by 1

the materials license 37-00185-05 for the Cobalt-60 facility. No items of non-compliance were

! identified.

During March of 1994, a NRC routine inspection was conducted for the radiation safety program and other activities authorized by the R-2 license. No iterm of non-compliance were .

. Identified. I l

j During April of 1994, a NRC routine inspection was conducted of activities authorized by the j special nuclear materials license SNM-95 and of physical security items under the R-2 license. No 4

items of non-compliance were identified.

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TABLE 2 ReactorOperation Data July 1,1991 - June 30,1994 91-92 92-93 93-94 A. Hours of ReactorOperation

1. Critical 431 635 601

2. Suberitical 541 404 362

3. FuelMovement 37 8 31 B. Number of Pulses 90 77 48 C. Numberof Square Waves 68 60 68 D. Energy Release (MWH) 210 391 391 E. Grams U-235 Consumed 11 20 20 F. Scrams

1. Planned as Part of Experiments 24 20 27

2. Unplanned - Resulting From a) Personnel Action 2 2 2 b) AbnormalSystemOperation 7 1 1 9

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TABLE 3 Reactor Utilization Data Shift Averages July 1,1991 - June 30,1994 91-92 92-93 23d4 A. Reactor Usage

1. Hours Critical 1.7 2.5 2.4

2. Hours Suberitical 2.1 1.6 1.4

3. Hours Shutdown 1.7 1.6 1.5

4. ReactorNot Available -Q1 Ql Of TOTAL HOURS PER SHIFT 6.3 5.8 5.9 B. Type of Usage - Hours

1. Industrial Researth and Service 0.8 0.9 0.6

2. University Research and Service 1.5 2.3 2.1

3. Instmetion and Training 1.4 1.1 1.4 l 4. Industrial Training Programs 0.0 0.0 0.0

5. Calibration and Maintenance 2.4 1.4 1.8 l 6. FuelHandling 0.1 0.1 0.1 C. Users / Experiments l 1. Number of Users 2. 8 2.7 2.3

2. PneumaticTransferSamples 0 17 0.7 0.6

3. TotalNumber of Samples 2.4 3.1 2.3 l 4. Sample Hours 1.5 2.7 2.9 D. Number of 8 Hour Shifts 255 250 254 l

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IV. GAMMA IRRADIATION FACILITY he 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 1,1994 approximate total of 3700 curies.

In this facility, the sources are stored and used in a mol 16 feet by 10 feet, filled with 16 feet of demineralized water. The water provides a shield waich 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 severalirradiators 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.

De 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 138 KR/Hr in a 3" ID tube and 80 KR/Hr in a 6" ID tube are available as of July 1,1994.

Last year's report made reference to efforts to obtain 10,500 curies of Cobalt-60 in the form of 15 source rods from Battelle National Labs. These efforts were abandoned and the sources went to another university. Effons are now underway to transfer a GammaCell 220 from the David Samoff Research Center in Princeton, New Jersey to the RSEC. 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.

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TABLE 4 Cobalt-60 Utilization Data July 1,1991 - June 30,1994 2h91 22-21 219_4 A. Time Involved (Hours)

1. Set-Up Time 185 171 130

2. Total Sample Hours 12,549 10,975 6,547 B. Numbers Involved

1. Samples Run 740 684 510

2. Different Experimenters 35 35 36

3. Configurations Used 3 4 3 C. PerDay Averages

1. Experimenters 0.6 0.8 0.54

2. Samples 2.97 2.75 2.05 I

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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.

In-house reactor operator requalification during November of 1993 consisted of an oral examination on abnormal and emergency procedures given by K. E. Rudy and an operating test given by E. J. Sipos.

Staff members Thierry Daubenspeck and Mark Grieb and operator intem Alexander McLellan participated in the reactor operator training program during 1994.

He eighth session of the Pennsylvania Governor's School for Agricultural Sciences was heki at Penn State's University Park campus during the summer of 1993. Sixty-four high school scholars participated in the five wee c program at Penn State. The Governor's School for Agricultural Sciences includes introduction and experience in many different agricultural disciplines. Dere are several parts of the program which are considered " core courses". The core courses are fundamental instruction given to all panicipants. " 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 nuclear engineering students Scott Anderson and Joy Moncil. Hemuna Boyle, Supervisor of the Low-Level Radiation Monitoring Laboratory provided a session on detection of radiation in the environment including radon gas. He 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 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. He students were also given a tour of the reactor facility.

The Nuclear Concepts and Technological Issues Institute (NCTII) was conducted fmm July 12-30,1993 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 c,ight secondary science teachers participated in the program. The program was developed m 1970 and has been conducted every summer since that time. The 1993 program differed in that it was not four weeks, but a one week introductory course followed by a two-week applications course. His enabled flexibility in time and also course material for those who may have taken an introductory course in the past.

Support for the program included funding through a grant from the National Science Foundation for nine teachers. Sponsorship of the other nineteen participants was provided by Baltimore Gas and Electric Company, Chem-Nuclear Systems Inc., Edison Electric Institute, General Electric Company, Gilbert Associates, GPU Nuclear Corporation, New York Power Authority, the Organization for Korea Atomic Energy Awareness 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. Oxford Instruments Inc. provided a loan of educational counting equipment and hosted the evening reception for participants and sponsors.

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 govemment, research, and industry provided expertise for the technical and issues sessions. Guest speakers included Ms. Carol 13

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l l 1 Hanlon from the U.S. Department of Energy, Office of Civilian Radioactive Waste Disposal and Management, Dr. Walter Newcomb from Chem Nuclear Systems Inc., Mr. John Reddding from General Electric Company, Mr. Chris Davis from Westinghouse Electric Corporation, Mr. Jeff i Schmidt from the PA Sierra Club and Dr. Frank Olney from Radiology Associates. Several l Alumni including Charles Bell, Jim Allen and Mary Lou Gougar retumed to discuss I implementation of nuclear science into their curriculum.

Laboratory experiments are an imponant 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 I experiments and demonstrations included: characteristics of ionizing radiation, neutron activation l of Indium, complex decay of Silver-110 and Silver-108, neutron radiography, and the approach to i 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.

l Evaluations from the participants were very positive concerning the course. As in previous institutes, the participants in NCTH were encouraged to return with their students for a day of ex xriments at the RSEC. A follow-up program was conducted during the month of May and was held as part of the American Nuclear Science Teachers Association (ANSTA) annual conference.

Candace Davison, president of ANSTA, organized the conference in Toronto, Canada. A meeting was held with the Canadian Nuclear Society (counterpart to the US ANS) and die Canadian Nuclear Association (an industry lobbying group). The ANSTA also toured the Pickering CANDU nuclear power plant and the AECL SPEL laboratory, where fuel handling machines are fabricated along with other actisities.

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

The pmpose 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 colleges, technical schools and high schools.

1 Experiments were conducted at the RSEC for students from Juniata College, St. Vincent College, Indiana University of Pennsylvr.nia, University of Pittsburgh at Greensburg and Grove City College.

A total of 351 students and teachers from 30 high schools and 5 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 Eric Sipos, Thierry Daubenspeck, Jim Adams and Joy Moncil.

The RSEC staff and facilities provided educational opportunities 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 MOSET program and the Upward Bound program for minority and "at risk" students. Twenty-three teachers from the Harrisburg area panicipated in a full day of experiments as part of the course " Exploring the Nuclear Option". Thirty three 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, 14 l

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who toured the facility are listed in Appendix B. The RSEC operating staff and Nuclear Engineering Depanment conducted 102 tours for 1,720 persons.

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

Semester Course Instructor Students liQun i

Summer 1993 NucE 497B-Nuclear Concepts C. C. Davison 28 5 Summer 1993 NucE 444-Nuclear Reactor Operations D. E. Hughes 7 15 Fall 1993 NucE 451-Reactor Physics R. M. Edwards 12 55 W. A. Jester Spring 1994 NucE 497E (443)-Nuclear Digital Data R. M. Edwards 12 5 Acquisition, Processing and Control Spring 1994 NucE 444-Nuclear Reactor Operations D. E. Hughes 6 27 Spnng 1994 NucE 450-Radiation Detection and M. H. Voth 35 46 Measurement W. A. Jester Summer 1994 SciEd 497-Exploring the Nuclear Option C. C. Davison 23 4 In February of 1994, a total of 44 University Police Services personnel were given training and retraining sessions by C. C. Davison at the RSEC to ensure familtarity with the facilities and to meet Nuclear Regulatory Commission requirements.

During the 1993-94 academic year, the RSEC hosted two IAEA fellows under the guidance of Dr. Voth and Mr. Bryan and a third who was hosted by the Nuclear Engineering Department.

Mr. Ladislav Franc, of the Skoda Nuclear Machinery company in the Czech Republic, visited for the Fall Semester for special training on reactor instrumentation with emphasis on miniature, in- .

core, self-powered detectors. Mr. Franc is the head instrument engineer for the Temelin project, a 1000 MW VVER ty 3e (PWR) Soviet design power station under construction. He plant is being built with a Westing louse in-core detector system and core performance software in lieu of the Soviet-supplied version. Mr. Franc's program included the reactor physics laboratory course, a refresher course in reactor theory, and experimental work with in-core monitoring and automated data acquisition in the TRIGA reactor.

Dr. Abdelali Belhadj, of CNESTEN (National Center of Energy, Sciences, and Nuclear Techniques) in Morocco, visited for the Spring Semester for general training in research reactor mstrumentation applications in operation and research. Dr. Belhadj, a recent graduate, is assigned to head the instrumentation program of the Moroccan TRIGA reactor which is in the initial stages of construction. With the assistance of Mr. Grieb and others of the RSEC staff, Dr. Belhadj was acquainted with the routine surveillance, calibration, and repair of typical research reactor equipment. He augmented his electrical engineering background through the radiation detection and measurements laboratory course, an advanced reactor controls course, and a nuclear engineering theory course.

Dr. L. Erradi from the Department of Physics in the university in Rabat, Morocco, visited Penn State for one week in the Spring Semester as part of a four-week tour of the United States. He will be a user of the CNESTEN TRIGA reactor and was observing how US nuclear engineering programs are conducted.

During the past year, the RSEC operating staff has maintained reactor operator competence and safe facility operation through training and requalification. The RSEC and continuing education 15

. - - - . - . . _ . . . - = . . ._ _ _ _ . . . - - _ -

4 staffs have disseminated knowledge directly to the general public through tours and indirectly through programs such as Nuclear Concepts for high school teachers. In addition to the two Open House events, public education efforts included a question and answer segment on WRSC Radio from 9:00 - 10:30 a.m. on September 28,1993 and a segment about the reactor on the WTAJ television " Action News for Kids" program in November. Many educational opponunities have been provided to students in university courses both nuclear and non-nuclear.

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, TABLE 5 University Reactor Sharing Program l College and High School Groups 1 1993-1994 Academic Year i 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 ,

I Neutron Activation Analysis Relative Stopping Powers for ot, and yin Air, Aluminum and Lead Number of higoth School and Teacher Students & Teachers November 3 West Branch H.S. 29 Ron Matchock 10 Harmony HS 38 Chad Weiwiora 12 Lower Dauphin HS 10 Phil Green 22 Union City HS 15 Mike Zarger 23 St. Vincent College 11 Anis Maize December 1 Wyomissing High School 9 Charles Bell 10 South Carroll HS 35 Sue Christenbury 15 Carlisle HS 50 Robert Barrick l January 15 Jersey Shore High School 16  !

James Allen March 18 Daniel Boone HS 12 Larry Tobias 23 Peters Township HS 14  ;

Walter Jenmngs 30 Redland HS 19 Robert Lighty April 6 State College HS 16 Sara Bressler .

6 Juniata College 3 Norm Siems 8 Jersey Shore HS 9

. Gary Heyd 8 Indiana University of PA 9 Frank Fazio 17

i t TABLE 5 University Reactor Sharing Program l

i College and High School Groups 1993-1994 Academic Year (Continued)

Number of Month School and Teacher Snidents & Teachers April 11 Mt. Union HS 18 Janet Whitaker 15 Ridgway HS 22 Emest Koos 15 St. Mary's HS 22 William Scilingo 19 Grove City College 11 Jim Downey 20 Harborcreek HS 9 Dave Sidelinger 22 East Stroudsburg HS 10 K. Lubrecht, H. Skeldon 25 Camp HillHS 9 Philipp Schmelzle 29 Berlin Brothersvalley HS 9 J. Neil Crowell May 2 Northem Bedford HS 25 Keith Little 6 State College HS 22 John Ford 9 Muncy HS 34 Harold Shrimp 11 Dallastown HS 13 l Mark Ilyes 16 Twin Valley Middle School 47 Doug Mountz 17 Somerset HS 24 Jon Critchfield 17 University of Pittsburgh 5 at Greensburg Ted Zaleskiewicz 19 Bellefonte HS __ 24 National Honor Society 20 Chartiers-Houston HS 21 Helen Wicker 1 23 Danville HS 25 l Deb Slattery  !

24 Westmont Hilltop HS 14 i Tom Moore 24 Bermudian Springs HS 5 Jeanne Sucht J l8 l

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i i VL NEUTRON BEAM LABORATORY i

j 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 thennal 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. He beam is i also being used for static neutron radiography and neutron attenuation studies, and flash

radiography utilizing pulsing. Equipment is available to digitize the real time radiography images for image processing, and this system will be upgraded in the coming year. A photographic j laboratory facilitates the development and analysis of static neutron radiographs.

I j De NBL was established partially with funds from the U.S. Depanment of Energy (DOE) with matching funds from the University to:

1. Educate students and the public on an important use of neutrons from a research reactor, 4

I 2. Establish a demonstration center, " Neutrons in Action," to show that their use is j beneficial to mankind, and 4

{ 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 I science and engineering.

i Bettis Atomic Power Laboratory purchased time to utilize the neutron beam laboratory to

! evaluate two phase flow during the past year and the project continues. We continue to have 1 funded service work utilizing the beam to measure neutron attenuation of boraflex materials that i i have seen service in fuel storage pools. l l A recent project, using DOE and University matching funds, was completed to modify the J reactor bridge to add core rotational and east-west movements to the existing nonh-south core movement. The additional core motion will allow experimental setups using other beam pons in addition to the one associated with the D2 0 thermal column. DOE and University matching funds l

will also be used to build a new D20 thermal column to enhance the neutron beam in the NBL

) Dr. Sokol of the Penn State Physics Depanment, in conjunction with Argonne National

! Laboratory,is designing a Cold Neutron Irradiation Facility (CNIF) to study the moderating j properties of solid methane oflow temperatures. This project will initially benefit from the a versatility of the movable core and in later stages of the project will benefit from the ability to open j another beam pon for use.

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! VIL RADIONUCLEAR APPLICATIONS LABORATORY i i

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Personnel of the Radionuclear Applications Laboratory provide consulting and technical

assistance to those University research personnel who wish to utilize some type of radionuclear i technique in their research. The majority of these research projects involve neutron activation, but i the staffis able to provide services in radioactive tracer techniques, radiation gauging, radiation l' 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 water, air monitor filters, and other samples.

s

. Appmximately 150 irradiations of semiconductors were performed during the past year.

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

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] The facility performed 8 isotope production runs of Na 24, Br-82 and Ar-41 for industrial use.

j Interest in Ar-41 production has been increasing during the past year and it is expected that Ar-41 i production will pick up during the coming year. In addition to supplying Ar-41, interest has been

expressed in Kr-85. The production of Kr-85 will be looked at during the coming year.

3 i Penn State students and faculty members continue to use the services offered by the l radionuclear applications laboratory. During the past year, analysis work was performed for i graduate students in departments such as Geoscience and Metallurgy. Preliminary work has also l begun for a project involving the activation analysis of obsidian samples to determine ancient trade

routes in South and Central America.

The Penn State Radionuclear Applications Laboratory has been involved with the Armed Forces Radiobiology Research Institute in activation analysis work of artifacts from an historic site 1 in St. Mary's City, Maryland. NAA is currently being used to investigate the arsenic concentrations found in hair samples to determine the rate at which medicine was administered to

the person. De SMC project has gained national attention due to the unique circumstances.

Much progress has been made in leaming how to use the EG&G Ortec Omnigam neutron j activation analysis software. We are able to analyze samples using the Omnigam software; 1 owever, we are still in the process of determining how the software performs an analysis.

! Additional work is needed to better understand the capabilities of the programs, to understand how j each program works, and to gain confidence in the values obtained from using Omnigam.

}

De benchmarking of the reactor neutron energy spectrum following ASTM procedures is

! complete. Enriched uranium foils were obtained from Sandia National Laboratories in order to

! complete the necessary foilirradiations. The foils were irradiated and retumed to SNL for

analysis. A final SANDII spectral analysis report was provided to us by Sandia and we are j currently waiting independent verification of this data.

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• l I VIIL LOW LEVEL RADIATION MONITORING LABORATORY l

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On March 31,1994, the focus of the Low Level Radiation Monitoring Laboratory (LLRML)

was changed. Certification via the EPA program by the Pennsylvania Depanment of

, Environmental Resources (PA DER) to perform gross alpha, gross beta, radium-226 and radium-

228 analyses on danking water was dropped. The PA DER requires all public drinking water sup aliers serving more than 50 customers to have their supplies tested once during each four year

! cyc e. De tendency for most suppliers to wait until the last year of the four year cycle created a i boom and bust cycle in the lab, w sch in turn created staffing and budget problems. Also, I increasing PA DER regulatory requirements made the operation of the laboratory less than cost j effective. With this change in focus for the LLRML, personnel was decreased from three to one.

i j The laboratory will continue to participate in the Environmental Protection Agency's (EPA) i Environmental Radioactivity Laboratory Intercomparison Studies Program for gmss alpha, gross

beta, radium-226, radium-228, strontium-89, strontium-90, tritium, and other gamma emitters as ,

part of the laboratory quality assurance program and to maintain staff proficiency.

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j De laboratory provides analyses for alpha and beta activity in reactor pool water, cobalt-60

. pool water, and the reactor secondary heat exchanger water. Gamma spectroscopy is performed j on these samples if alpha or beta action levels are exceeded. Analyses are also done for tritium j content in the reactor pool water and the D2O tank heavy water. I i

ne LLRML is maintaining its certification via the EPA National Radon Measurement j Proficiency Program to test for radon in air using activated charcoal canisters and both short and a long term electret devices. Environmental analyst Maurice Peagler and the lab's technical advisor, I William Jester, are certified via the RMP exam for radon test operators and are listed in the EPA i posting of certified radon testing labs / individuals. The lab also tests for radon in water, j eenification for this activity is not currently available.

4 j Current laboratory activity is focused on gross alpha, gross beta, and gamma analyses of materials used in producing femoral heads in hip-joint replacements. This work is performed for l Howmedica of New Jersey and their raw material supplier, Nonh American Refractones, 5

i Analyses to cenify the % Lithium enrichment for enriched LiOH samples continues for Isotec Incorporated of Ohio. Higher lithium enrichments are important in the nuclear industry to mmmuze tntmm producn,on m pressunzed water reactors.

I j Dr. Jester's nuclear engineering graduate students with the assistance of Maurice Peagler will 1 study environmental Iodine-129 and Iodine 131 as an indicator of radioactive contamination.

j Uditha Senaratne will use Dionex's isocratic chromatography technique to quantify iodine in i environmental samples. The Dionex-100 ion chromatograph has been moved from the reactor i facility to the LLRML to provide better access and control of the equipment. Junhyun Kwon will

focus his study on distinguishing the radioisotopes using the Breazeale Reactor for irradiation and j the LLRML's germanium detectors for gamma analysis.

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IX. THE ANGULAR CORRELATIONS LABORATORY

, ne Angular Correlations Laboratory has been in operation for approximately 8 years. The I laboratory, which is located in Room 116 and Room 4 of the RSEC,is under the direction of l 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 this year to accommodate the increased demand for measurement capability. The detectors and electronics provide a nominal time resolution of I 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 important electrical and opticalmaterials. 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 thcontical basis have been part of the fields of nuclear chemistry and radiochemistry for several decades. Two federal agemies, the National Science Foundation and the Office of Naval Research, are sponsoring this program.

He 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 properties, the nuclear (electric quadrupole and magnetic dipole) moments of these atoms can mteract with the electric field gradients (efgs) and hyperfime magnetic fields produced by the extranuclear environment.

StaliG 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.,

0.1-500 nsec. As a result, the measured efg appears to arise from the time-averaged positions of the atoms, and the sharpness of the spectral lines reflects this " motional narrowing" effect. In contrast to static interactions, time-varving interactions arise when the efg fluctuates during the i intermediate-state lifetime. These interactions can provide information about defect and ionic I

transport. 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 ferromagnetic and paramagnetic bulk and thin-film materials, are used to study the effects of defects and lattice distortions 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 distortions are produced, a quadrupole interaction arises that attenuates the usually-well-defined magnetic mteractions. Thus, the analysis of this attenuation can provide information, for example, about the type of defect that produced the quadrupole interaction.

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! Cunent Activities j During the last several years, the PAC technique has been used to investigate phase transitions

! and local ordenng in ferroelectric perovskites such as lead titanate and barium titanate. Rese i compounds and other related materials are widely used as dielectric materials for capacitors,

piezoelectric transducer materials, and thin-film elements for random access memones. Static i nuclear quadrupole interactions measured in these materials have provided new information about

! displacive (paraclectric-to-ferroelectric) phase transitions such as the critical behavior of the 1 (titanium-site) electric field gradient at temperatures near the transition tempeuture. In particular, i since few of the ABO3 :erovskites have been investigated, similar measurements need to be i performed on KNbO3, KraO3, and similar materials. The pnmary objective is to observe critical t

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 interpmt

the critical exponents that describe the power-law temperature dependence of the nuclear-

! quadrupole-interaction parameters at temperatures very close to the critical temperatum.

i Ultimately, measurements of critical phenomina in ferroelectric crystals can be compared to the j results of similar measuremetns on other kinds of highly-correlated crystals such as

! ferromagnetics. Rese comparisons could lead to a more fundamental understanding of the crystal i

instabilities that give rise to the phase transitions. The Office of Naval Research has been funding j this project.

1 l Another important area of research in electronic materials is the characterization of chemical 1 interactions on molecular-beam-epitaxy (MBE) produced surfaces. In principle, the PAC j technique can measure the strength and symmetry of the chemical bonding of the 111In probe atom i on MBE-produced surfaces of gallium arsenide and other III-V materials. Currently, electron j scattenng is the predominant technique that is used to evaluate the morphology of MBE-produced i III-V surfaces. But, these measurements do not provide any detailed, microscopic information j about for example, the effects of step edges and kinks on the chemical bonding ofimpinging atoms j 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 l project of this type requires a collaboration between an expert in MBE-produced surfaces and an 1 expert in PAC spectroscopy. Penn State has such an expert; namely, Professor David L. Miller of j the Department of Electrical and Computer Engineering. The Electronic Materials and Processing l 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 chamber is used to dope IV-V surfaces with t11In; 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 i maintained under ultrahigh vacuum. During the past year, the separate chamber and the PAC

] spectrometer have been placed into operation. Currently, expenments are being performed using j this new experunental capability. The National Science Foundation has been funding this project.

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l X. RADIATION SCIENCE AND ENGINEERING CENTER l RESEARCH UTILIZATION Research continues to be the major focus of the RSEC. A wide variety of msearch projects are currently in progress as indicated on the following pages. The University oriented research projects are arranged alphabetically by department m 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 infomiation to the editor of this report is at the option of the researcher, and therefore the research arojects in sections A and B are only representative of the mscarch at the facility. The projects c escribed involved 1 report,15 papers,17 publications,3 masters' theses,12 doctoral theses and 1 bachelor's thesis. 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 m sections A and B. Names of personnel are arranged alphabetically under their department and college or under their company or other affiliation. During the past year,46 faculty and staff members,44 graduate students and 9 undergraduate students have used the facility for research.

'Ihis represents a usage by 17 departments or sections in 5 colleges of the University. In addition, 44 individuals from 29 industries, research organizations or other universities used the RSEC facilities.

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A. PENN STATE RESEARCH UTILIZING THE FACILITIES OF THE RADIATION SCIENCE AND ENGINEERING  !

CENTER I

Anthronolorv NAA OF OBSIDIAN ROCK TO IDENTIFY ANCIENT TRADE ROUTES

Participants:

K. G. Hirth i T. H. Daubenspeck

ServiceProvided

GammaIrradiation j Several obsidian samples have been irradiated in a preliminary study to determine how activation a analysis can be used m a proposed project. This project involves tracing ancient trade routes in l Central and South America by using obsidian obtained fmm excavation sites. Sources of obsidian i are well charactenzed and therefore obsidian fotmd at various sites can be traced to their origin.

Chemistry Deno2 uirerit 4 LOW TEMPERATURE SYNTHESIS OF HYDROXYAPATITE AND POLYPHOSPHAZENE COMPOSITE MATERIALS l

Participants:

H. R. Allcock P. W. Brown C. S. Reed '

K. S. TenHuisen Service Provided: Gamma Irradiation 1

i Gamma Irradiation is used to cmsslink poly (organophosphazenes) with etheric side groups to form a three dimensional network. This network is then used as the support for the formation of an

'. inorganic matrix. The resulting composite material has improved properties over the individual

! components. This project is on-going.

l DoctoralThesis:

Reed, C. S., H. R. Allcock, advisor. Novel Polyphosphazene Materials. In progress.

Chemistry Department INCLUSION POLYMERIZATION WITHIN A TRIS (2,3-NAPHTHYLENEDIOXY)-CYCLOTRIPHOSPHAZENE CLATHRATE l

Participants:

H. R. Allcock E. N. Silverberg G. K. Dudley 1

S. R. Pucher Service Provided: Gamma Irradiation 29

Host-guest phenomenon has been known for many years. One type of these adducts are clathrates, or molecular inclusion compounds. Clathrates are crystalline solids in which guest ,

molecules occupy cavities or tunnels within the host lattice. Inclusion chemistry has been known I for many years. Urea, thiourea, cyclodextrins, perhydrotriphenylene, and zeolites have all been l shown to have inclusion behavior. I Cyclophosphazenes are a class of inorganic ring systems with alternating phosphorus and nitrogen atoms in the ring. It was found that certain spirocyclotriphosphazenes show molecular inclusion phenomenon. The synthesis and inclusion propern,es of tris (o-phenylenedioxy)cyclotriphosphazene (1), tris (2,3-naphthalenedioxy)cyclotriphosphazene (2) and tris (1,8-naphthalenedioxy)cyclotriphosphazene (3) are well known. Compounds 1-3 form clathrate adducts with organic molecules when recrystallized from or brought in contact with organic compounds.

. Polymerization of organic monomers within clathrates 1 and 2 by "Co tradiation has been reported. In many cases, macromolecules formed in this manner have been stercoregular. The structural aspects of compounds 1-3 as well as their clathrate adducts have been examined by x-ray single-crystal structure studies. The aim of this work was to synthesize spirocyclophosphazenes and further the investigation of polymerization of organic monomers within the clathrate tunnels.

The results of this have been submitted for publication.

DoctoralThesis:

Silverberg, E. N., and H. R. Allcock, advisor. Phosphazene Polymers and Inclusion Compounds. In progress.

Publication:

Allcock, H. R., E. N. Silverberg, G. K. Dudley and S. R. Pucher. Inclusion Polymerization within a Tris (2,3-Naphthylenedioxy)-Cyclotriphosphazene Clathrate. Submitted to Macromolecules, April 1994.

Chemistry Deoartment POLY (ORGANOPHOSPHAZENES) CONTAINING ALLYL SIDE GROUPS:

CROSSLINKINC AND MODIFICATION BY HYDROSILYLATION

Participants:

H. R. Allcock

, D. E. Smith Y. B. Kim Service Provided: Gamma Irradiation Poly (organophosphazenes) containing 4-allyloxyphenoxy and 4-(4'-allyloxy-phenyl) phenoxy side groups were synthesized. These polymers were crosslinked thermally and by UV and y radiation. It was proposed that the allyl group could be used as a functional site for further chemical modification. Hydrosilylation reactions were first investigated using a small molecule model compound, pentaphenoxy mono 4-allyloxy phenoxy cyclotriphosphazene.

Heptamethyltrisiloxane and dimethylethoxysilane underwent hydrosilylation reactions with the model compound. The dimethylethoxy silane group underwent hydrolysis and self-condensation reactions in the presence of acid. Hydrosilylation of high polymers containing unsaturated side gmups resulted in poly (organophosphazenes) with terminal dimethyl siloxane grafts. Control of the reactant ratios allowed siloxane-containing polymers to be synthesized with residual unsaturated sites to facilitate crosslinking by the previously mentioned methods.

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5 Publication:

. Allcock, H. R., D. E. Smith, Y. B. Kim and J. J. Fitzgerald. Poly (organophosphazenes)

]- Containing Allyl Side Groups: Cross-linking and Modification by Hydrosilylation.

Macromolecules, in press 1994.

) Chemistn Department POLY (ORGANOPHOSPHAZENE) POLYMER ELECTROLYTE ALLOYS: I l POLYMER BLENDS AND INTERPENETRATING POLYMER NETWORKS l

} l

Participants:

H. R. Allcock i S. M. O'Connor K. B. Visscher M. Naperiela 1

Service Provided: Gamma Irradiation ne synthesis of several new polymer blends and interpenetrating polymer networks (IPN) contaming poly (organophosphazenes) and various organic polymers including poly (vinyl ethers), poly (1-alkenes) and poly (vinyl benzo crown ethers) are reported. Polymer blends were i 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"-

l (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], l

. poly [ bis (2,3-di(2-(2'-methoxyethoxy)ethoxy) propoxy)phosphazene] or poly [ bis (2,3-di(2-(2'- i (2"-(methoxyethoxy)ethoxy)ethoxy)propoxy)phosphazene]. These materials were characterized by NMR and FT-lR spectroscopy, DSC, electron microscopy and x-ray microanalysis. The conductivity of these materials was measured by impedence analysis.

j Publication:

Allcock, H. R., S. M. O'Connor, K. B. Visscher and M. E. Naperiela. Synthesis and j Characterization of Poly (Organophosphazene) Polymer Electrolyte Alloys. To be submitted

. to Chemistry ofMaterials,1994.

Chemistry Department POLYPHOSPHAZENES FOR BIOMEDICAL APPLICATIONS i

Participants:

H. R. Allcock R. Ravikiran Service Provided: Gamma Irradiation l

ne work in this project involves use of polyphosphazenes for biomedical applications. Two different kinds of polymers are being studied for use as hydrogels - which will funher be studied i as controlled drug delivery agents and wound dressing materials. One of the polymers contains i

31

glucose side groups attached to the phosphazene backbone. These form excellent hydrogels, when crosslinked by gamma radiation.

l De other class of polymers are not water soluble but show water swellability in the uncmsslinked state. They are crosslinked by gamma radiation to increase dimensional stability.

Doctom! Thesis:

l Ravikiran, R., and H. R. Allcock, advisor Polyphosphazenes for Biomedical Applications. In l progress.

l l Chemistry Decartment SYNTHESIS AND CIIARACTERIZATION OF ANIONIC (POLYORGANOPHOSPHAZENE) HYDROGELS

Participants:

H. R. Allcock I

A. A. Ambrosio Service Provided: Gamma Irradiation A series of poly [(methoxyethoxyethoxy) propyl oxybenzoate)phosphazenes),2a-4a, was synthesized and characterized. These water-insoluble ?olymers were then hydmlyzed to yield the l anionic derivatives, poly [(methoxyethoxyethoxy)(oxy xnzoate)phosphazenes],2c-4c. The I resultant polymers were glassy and water-soluble. Their glass transition temperatures were approximately 70*C higher than those of the unhydrolyzed polymers. The polymers were crosslinked by MCo gamma irradiation and the swellability of the crosslinked polymers,2cx -4cx, were detemtined as a function of composition, pH, ionic strength and cation valency. Polymers 2cx-4c xformed hydrogels which and higher degrees of swelling in basic than in acidic buffer solutions. Moreover, the polymer with the higher loading of the oxybenzoate side group showed higher sweliability than the one with a lower loading of this side group. As predicted, the degree l of swelling of the polymers was reduced when the ionic strength of the swelling medium was increased. The degree of swelling was also affected by the valency of the cation present in the l swelling medium. A trivalent cation lowered the swelling of the gels more than a divalent or l monovalent cation did.

l Doctoral Thesis:

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

Chemistry Department SYNTHESIS AND CHARACTERIZATION OF ION COMPLEXING POLY (ORGANOPHOSPHAZENE) INTERPENETRATING POLYMER NETWORKS

Participants:

H. R. Allcock K. B. Visscher Service Provided: Gamma Irradiation he synthesis ofion-complexing interpenetrating polymer networks composed of the polyphosphazenes MEEP, (NP(OCH2 CH20CH2 CH20CH )2]n, 3 or (NP(OC6H4COOPr)2]n and 32 l _ _ _ - _ - . - _ _ _ _ _ _ ._ _ _ _ _ . - _ _ _ _ _---_ _

1 acidic, coonlinative organic polymers is reported. These latter polymers included poly (acrylic i acid), aoly(vinyl sulfonic acid sodium salt), poly [di(undecenyl phos? hate)] and poly [(p-

, methy immodiacetoxy)-styrene]. Several of these systems are capab ,e of selective coordination

of specific ions and are prototypes for ion selective membranes. Full, sec uential IPNs were i prepared, and these materials were characterized by NMR spectroscopy, cifferential scanning calorimetry (DSC), and transmission electron microscopy (TEM). After metal complexation, the conjugate IPNs were analyzed by electron microscopy and x-ray microanalysis. Metal coordination proved to be an excellent technique for enhancing domain contrast in these systems .

l' for electron microscopy studies. Because the IPN's based on MEEP are of particular interest for l ion selective membrane applications, the stability of MEEP in acidic, neutral, and basic aqueous media and the response of the polymer to aqueous salt solutions was also examined.

4 Publication:

3~

Allcock, H. R., and K. B. Visscher. Synthesis and Characterization Ion Complexing Poly (organophosphazene)Interpenetrating Polymer Networks. Submitted to Chemistry of Materials,1994.

Chemistry Department

! SYNTHESIS AND CHARACTERIZATION OF NOVEL POLY (ORGANOPHOSPHAZENE) INTERPENETRATING POLYMER l NETWORKS l

Participants:

H. R. Allcock

! K. B. Visscher j Y. B. Kim l Service Provided: GammaIrradiation i

! The synthesis and characterization of novel interpenetrating polymer networks (IPN) composed of poly (organophosphazenes) and organic or inorganic polymers is investigated. The phosphazene polymers form the cross-linked polymer matrix of the IPN within which the organic or inorganic l 2 monomers are polymerized. The phosphazene polymers may be cross-linked thermally or by i exposure to UV radiation, which cross-links the polymers either through a double bond or by the

loss of H-SiOEt. These IPNs are characterized byI H NMR,31P NMR and FT-IR spectroscopy, l DSC and TEM.

j DoctoralThesis:

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

and Interpenetrating Polymer Networks,1993.

I Publication:

I Allcock, H. R., Y. B. Kim and K. B. Visscher. Novel Poly (Organophosphazene) 2 Interpenetrating Polymer Networks. To be submitted to Chemistry ofMaterials,1994, i

Dairy and Animal Science j

HEAVY ELEMENT ASSAY OF CORN

Participants:

K. Kephart L. Hutchinson 33

i j Service Provided: Neutron Activation Analysis i The services of the RSEC facility were sought to assay a sample of corn for heavy elements. The corn sample originated from a Montgomery County farm on which swine were suffering from

! health problems of undermined causes. The com sample was fmm the 1992 harvest year. During i the previous year, in the same field, the corn was injured following a commercial apph' cation of

herbicide. The growth problems in the corn that were evident following the spraying incident in 1991, persisted in 1992-. The pattern of swine health problems on the farm corresponded to the

! feeding of the affected corn from both 1991 and 1992. Because the health problems resembled i l

those of a trace element interaction, and because the problems did not appear to be of a pathological nature, the authors suspected heavy element contanunation. According to the report from T. H. I Daubenspeck, dated November 17,1993, the com sample was irradiated at a power of 1 MW for 1 l hour, after which the sample was counted over a period of 25 days. Of the six elements detected in l the sample, only It was judged to be unusual. However, the concentration (.0003 ppm) was so l

low, it is our opinion that the elements detected (including Ir)in the corn were not related to the i problems on the farm. Efforts to resolve the health problems in the swine herd are continuing.

Food Science EVALUATION OF COCOA MICROFLORA

Participants:

R. F. Roberts Service Provided: Gamma Irmdiation Used y irradiation to sterilize two samples (100g each) of cocoa powder to serve as controls in

" inoculated peck" experiment.

Materials Science and Encineerine LOW TEMPERATURE SYNTHESIS OF NOVEL COMPOSITES

Participants:

K. S. Tenhuisen P. W. Brown i C. S. Reed H. R. Allcock Service Provided: Gamma Irradiation This study was based on forming ceramic / polymer composites at low temperature to be used as synthetic bone. In theory, the reinforcing phase (a polyphosphazene) was to be formed via y irradiation crosslinking prior to matrix phase formation. After crosslinking, the porous composite was to be reacted in water at physiological temperature to induce the formation of the matrix phase, hydroxyapatite, via a solid-solid acid-base reaction. In theory, the crosslinked polymer should toughen the composite.

Due to processing problems, this project is no longer being pursued. The polymer swelled upon water infiltration resulting in the cracking of the composite. The kinetics of matrix phase formation was also greatly reduced making this system unsuitable for use in vivo.  ;

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Mechanical Ennineering NEUTRON RADIOGRAPHIC ANALYSIS OF MACROSEGREGATION IN BINARY METAL ALLOYS 1

l

Participants:

P. J. Prescott j V. K. Singh

! Service Provided: Neutron Radiography Convective transport phenomena are important during solidification of metal alloys. Fluid flows in j the two-phase (mushy) and the fully melted regions are caused by thermally and solutally induced 1 buoyancy forces during solidification of alloys. Fluid flows in the mushy and the melt regions have a profound influence on the metallurgical structure and chemical homogeneity of the final i

casting. Moreover, convection in the solidifying alloy is nsponsible for macrosegregation, a maldistribution of solute in castings.

l 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 i thermal boundary condition have been considered. Experiments have been yrformed in a vertical i square cavity, which is cooled from a side wall while keeping the other wal, insulated.

i Ex periments are underway to analyze the solidified ingot for any macrosegregation using neutron j radiography.

4 Neutron radiography uses a collimated beam of neutrons to penetrate a specimen. The intensity of

the neutron beam exiting the specunen depends on thickness and neutron absorption characteristics i of the specimen. There is a large difference in neutron absorption coefficients for gallium (Ga) and i indium (In). In other words, gallium is relatively transparent to the neutron beam while Indium is j 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.

A

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 coming days, films of the 4

solidified ingot will be taken and the distribution of Ga-In constituents will be determined i

analyzing the film.

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Master's Thesis:

i

! Singh, V. K., and P. J. Prescott, advisor. A Combined Numerical and Experimental Study of Convective Transport Phenomena During Solidification of Binary Metal Alloys. In progress.

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i Nuclear Engineering i MECHANICAL PROPERTIES OF BORATED STAINLESS STEEL TO BE USED j IN SPENT FUEL RACK ASSEMBLIES i

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Participants:

A. J. Baratta i J.He 1

l Services Provided: Neutron Irradiation, Hot Cell Lab, Radiation Counters, Machine Shop, j Low Level Monitoring Lab and Electronics Shop j 35 i

.- _m

The purpose of this project is to perform test and analysis of the mechanical prope,rties of several types of borated stainless steels manufactured by Carpenter Technology Corporation. Test specimens in either neutron irradiated or umrradiated conditions are used to investigate potential neutron irradiation effects on the mechanical properties of the borated steels. Our experiment

determined that neutron irradiation effect on these materials is in most cases statistically insignificant. In the few cases where neutron irradiation effects are observable, the change in the

affected properties represent small percentages of the total values. The main concern was that

neutron-boron interaction would aroduce large amounts of helium even at low fluence, since the

amount of boron present in the al oy is far greater than the trace present in regular 304 stainless i steel. Our research addressed such concerns through the results of fracture toughness test, tensile

test, and compression test of model cask channels.

1 i Our results show good performance of the borated stainless steels by CarTech even after irradiation

, to the fluence of 1.E17 neutrons /cm2 . Such results are consistent with earlier research by Youchinson and Soliman on the same materials through different testing techniques (i.e., CVN

] impact test, hardness test, ets.) These results lend strong support for the borated steels as spent 4

fuel cask candidates. Currently, final analysis of the fracture mechanism for these materials are being conducted. Metallographic and SEM studies will be used to investigate the void nucleation and linking process responsible for the fracture. With the understanding of the fracture mechanism, the mechanical performance of the borated steel can be comprehended thoroughly so that better engineering judgment can be made in applying these materials to their intended tasks.

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q DoctoralThesis:

He, J., and A. J. Baratta, advisor. Mechanical Properties of Borated Stainless Steel to be Used in Spent Fuel Rack Assemblies,1994.

1 Sponsor: Carpenter Technology

! Nuclear Enpneering i

ANOMALOUS CRYSTAL CHEMISTRIES OF TIIE titin-+111Cd AND l 1811Ifais1Ta PROBES IN RUTILE TiO2 STUDIED USING PERTURBED.

] ANGULAR-CORRELATION SPECTROSCOPY 1

Participants:

G. L. Catchen J. M. Adams i

Services Provided: Angular Correlations Lab, Laboratory Space and Isotope Production

We have used perturbed-angular-correlation (PAC) spectroscopy to measure nuclear-electric-

quadrupole interactions at the Ti-site in ceramic samples of rutile, TiO2 . To investigate differences

! in the probe crystal chemistry, we used two chemically-different PAC probes, IllIn-4111Cd and j 181Hf-+181Ta, and we measured the temperature dependences of the electric field-gradient (EFG)

parameters, Vu, q, and 6 over a temperature range from 290 K to 1300 K. The results of these

PAC measurements are compared to the results of 47 49Ti nuclear-magnetic-resonance measurements. Significant differences are found in the temperature dependences of Vu, and a that cannot be ex?l ained in terms of simple considerations such as ionic size and charge. These effects are discussec in terms of differences in directional bonding that the PAC probes could exhibit.

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Publication:

Adams, J. M., and G. L. Catchen. Anomalous Crystal Chemistries of the IllIn--+111Cd and 181HfatstTa Probes in Rutile TiO 2Studied Using Perturbed-Angular Conelation Spectroscopy. Phys. Rev. B, S1,1264-1267 (1994).

Nuclear Eneineering CRITICAL EFFECTS IN BaTiO3 MEASURED BY PERTURBED ANGULAR-CORRELATION SPECTROSCOPY

Participants:

G. L. Catchen R. L. Rasera T. M. Rearick E. F. Hollinger D. W. Esh J. M. Adams Services Provided: Angular Correlations Lab, Laboratory Space and Isotope Production We have used perturbed-angular-correlation (PAC) spectroscopy via the 181Hf-+181Ta probe to measure critical effects at the Ti site in ceramic BaTiO3. We measured the temperature dependence of the electric-field-gradient (EFG) parameters Vu, y,6, and f at temperatures very near the tetragonal-txubic transition. As temperature increases toward the transition temperatures, the EFG component Vu, which represents the primary, low-frequency Ti-site interaction, and the corresponding site-occupancy fraction f both decrease rapidly. The decrease in fis accompanied by a corresponding increase in a second site-fraction that undergoes a "zero-frequency" interaction.

The parameters Vu and f both show very similar power-law temperature dependences. The decrease in Vu that occurs as Te is approached can be explained by analogy to magnetic transitions. But the corresponding decrease in f does not yield a conventional explanation and may be an artifact that arises from the analysis model.

Baccalaureate Thesis:

Esh, D. W., G. L. Catchen, advisor. A Study of PbTiO3 and PbZrO3 Using Perturbed-Angular-Correlation (PAC) Spectroscopy. 1993.

Publication:

Catchen, G. L., T. M. Rearick, E. F. Hollinger, D. W. Esh and J. M. Adams . Critical Effects in BaTiO3 Measured by Perturbed-Angular-Correlation Spectroscopy. Ferroelectrics 156/1-4.

2123-2131 (1994).

Sponsor: Office of Naval Research $249,416 Nuclear Engineering HIGH-TEMPERATURE PHASE TRANSITIONS AND LOW TEMPERATURE MAGNETIC ORDERING IN SrRuO3 AND CaRuO3 CERAMICS MEASURED USING PERTURBED ANGULAR CORRELATION SPECTROSCOPY Panicipants: G. L. Catchen D. G. Schlom T. M. Rearick 37

Services Provided: Angular Correlations Lab, Laboratory Space and Isotope Production Penurbed-angular-correlation (PAC) Spectroscopy was used to measure nuclear-electric-quadrupole interactions in the orthorhombically-distorted perovskites SrRuO3 and CaRuQ over tem ratures ranging from laboratory to very high temperatures. At 77 K, PAC spectroscopy was u to measure combined electric-quadrupole and magnetic-dipole interactions in magnetically-ordered SrRuO3 and pure electric-quadrupole interacuons in paramagnetic CaRuQ. The tillnwillCd PAC probe was used for these measurements, and it substituted into the Ru site in SrRuO3 and very likely into the Ru site in CaRuO 3. The temperature dependence of the electric-i field gradient (EFG) parameters for SrRuO3 ndicates the onset of a structural phase transition at approximately 800 K. The presence of this transition indicates that the laboratory-temperature structure of SrRuO3 has lower than-cubic symmetry. At very high temperatures > 1600 K, the structure of CaRuO3, as given by the EFG parameters, becomes very similar to the laboratory-temperature structure of SrRuO3. At 77 K in SrRuO3, the measured Ru-site supertransferred hyper 6ne field is 39 i3 kOc. Using 99Ru and 57Fe M6ssbauer-effect informauon and other IIIIn-+111Cd PAC measurements, the magnetic hyperfine fields at the Ru site in SrRuO3 and at the Fe site in PrFeO3 are compared.

Publication:

Catchen, G. L., T. M. Rearick and D. G. Schlom. High-Temperature Phase Transition and Low-Temperature Magnetic Ordering in SrRuO 3and CaRuO3 Ceramics Measured Using Penurbed.

Angular-Correlations Spectroscopy. Phys. Rev. B 42,318-326 (1994).

Sponsor: Office of Naval Research $249,416 Nuclear Engineerine 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: Neutmn 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 Calven, 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.

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 arsenic and silver in one of the hair samples. It was determined that the silver concentration was due to jewelry wom in the hair. The arsenic concentration led to an investigation which has now focused on the use of arsenic in medicines in colonial days. The hair analysis is continuing in an attempt to determine the rate of arsenic administered as a function of time.

38 I

Nuclear Engineering ISOTOPE PRODUCTION FOR TRACER STUDIES

Participants:

T. Daubenspeck M. Bothe J. Kolek M. Flenniken J. Owens Services Provided: Neutron Irradiation Seven isotope production runs were performed for Tru-Tec during the past year. These runs included 2 Na-24 runs,4 Br-82 runs, and 2 Ar-41 runs. A total of 1 Ci of Na-24,550 mci of Br-  !

82, and 625 mci of Ar-41 were produced.  ;

l Nuclear Eneineerine SEMI-CONDUCTOR IRRADIATIONS

Participants:

T. Daubenspeck F. Kalkbrenner R. Dietta Services Provided: Neutron Irradiation Semi-conductor irradiations for commercial and military applications numbered 150 for the year.

There were 114 inadiations for Harris Semiconductor,22 for Raytheon, and 14 for Honeywell.

Nuclear Eneineering TRITIUM CONTAMINATION OF METALS

Participants:

W. S. Diethom A. R. Dulloo Services Provided: Neutron Irradiation, Radiation Counters, Laboratory Space, Machine Shop, Isotope Production and Electronics Shop Tritium contamination of equipment creates problems in waste control, radiological safety and tritium accountability at large tritium-processing facilities in the U.S. The purpose of this study is

, to investigate tritium distribution in materials of interest to the tritium-processmg industry.

! Recoil injection and diffusion-charging will be used to impregnate materials with tritium, and the tritium distribution resulting from these two methods ofimpregnation will be compared. The effects of factors such as grain size and sensitization on the tritium distribution will also be investigated.

DoctoralThesis:

Dulloo, A. R., and W. S. Diethom, advisor. An Experimental Study of the Distribution of Recoil-and Diffusion-Charged Tritium in Metals,1994.

Sponsor: EG&G Mound Applied Technologies, fourth year.

. 39

Nuclear Eneineering UNDERGRADUATE LABORATORY ON REACTOR EXPERIMENTS

Participants:

R. M. Edwards ,

M. A. Power l M. E. Bryan i Services Provided: Laboratory Space, Machine Shop, Electronics Shop, Reactor Instrumentation and Support StatT 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-TRIGA experiments and each is the major responsibility of a ,

different professor. The non-TRIGA track includes 3 graphite pile,2 analog simulanon, and 1 power plant measurement experiment. In 1993, the TRIGA track included:

1. Digital Simulation of TRIGA ReactorDynamics

2. ControlRodCalibration

3. Large Reactivity Insertion (Pulsing)

4. ReactorFrequency Response

5. Neutron Noise i

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 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.

Paper:

Edwards, R. M., and W. A. Jester. Evolution of Nuclear Engineering Laboratory Courses at the Pennsylvania State University. Trans. Amer. Nucl. Soc.10:29-30, June 1994.

Nuclear Eneineering UNDERGRADUATE COURSE ON NUCLEAR DIGITAL DATA ACQUISTION, PROCESSING AND CONTROL

Participants:

R. M. Edwards M. A. Power J. A. Turso P. B. Walter C. M. Chavez M. E. Bryan 40

l Services Provided: Laboratory Space, Machine Shop, Electronics Shop, Reactor Instrumentation and Support Staff This one credit course was offered for the first time in the spring semester 1994 under the designation NucE 497E (future NucE 443). The course included an introduction to C language programming, demonstration of C applications, and a course project. Instruction and course projects using PC, Macintosh, and Bailey Network 90 microprocessor-based controllers for data acquisition and processing were conducted on the TRIGA reactor.

Nuclear Eneineerine NSF/EPRI:. EXPERIMENTAL DEVELOPMENT OF POWER REACTOR INTELLIGENT CONTROL

Participants:

R. M. Edwards K. Y. Lee D. E. Hughes 1

Services Provided: Laboratory Space, Machine Shop, Electronics Shop, Reactor  !

Instrumentation and Support Staff l 4

This is a major three year project supponed by the National Science Foundation and Electric Power Research Institute. Initiated in January 1993, the project is composed of five major tasks: I Advanced Direct Control Experiments, II Intelligent Control Research, III Multivariable Control Capability,IV Hybrid Reactor / Simulation, and V Dissemination of results. Specific activities during the 1993-94 academic year are summarized in the following descriptions.

Master's Paper:  ;

Shatto, K. L., R. M. Edwards and A. Ray, advisors. Modeling and Controller Design for the Pennsylvania State University TRIGA Reactor. A paper in Mechanical Engineering. May 1993.

Paper:

Edwards, R. M., K. Y. Lee, A. Ben-Abdennour, C.C. Ku and P. Ramaswamy. A Comparative Study for Nuclear Reactor Controller Design Using Optimal Control, Robust Control, Neural Network, and Fuzzy Logic Control. ANS Topical Meeting on Nuclear Power Plant Instrumentation, Control, and Man-Machine Interface Technologies, pp 153-160, Oak Ridge, Tennessee. April 18-21,1993.

Publication:

First Annual Progress Report on Experimental Development of Power Reactor Intelligent Control, ECS-9216504, Report to National Science Foundation. December 1993.

Sponsors: FERMI $12,000 (1992) NSF/EPRI (1993-1995) $300,000 for the FERMI $18,000 (1994) NSF/EPRI projects described below:

41

1 i

, Nuclear Engineering l - NSF/EPRI ROBUST CONTROL OF TRIGA REACTOR TEMPERATURE l

Participants:

R. M. Edwards

! M. A. Power i D. E. Hughes

! M. E. Bryan i

1 Services Provided: Laboratory S, pace, Machine Shop, Electronics Shop, Reactor l Instrumentation and Support Staff  ;

t

! Based on a prototype TRIGA Reactor Optimal Control, experiment conducted during the summer of i 1991, this area was expanded into a full range of expenments to verify the robustness

! charactenstics of this optimal control application. Initiated in 1992 as a FERMI project, this effort

! was continued into 1993 and 1994 as a part of the NSF/EPRI funded project.

a l A Bailey NE'IWORK 90 Distributed Control System is used to implement the optimal control

! algorithm which is implemented in the Bailey controller using general pur mse C language  ;

j programming. The Bailey system includes a Computer Interface Unit anc Pmeess Control View l Software. The Bailey drives the Secondary Control Rod (SCR) drive which travels in the central

{ thimble while the licensed control and safety system is in a manual mode of o nation. In 1993-94

) a more precise screw-drive mechanism replaced the previous pulley-cable SC 1 drive.

i l- Advanced control algorithms, such as this optimal control algorithm, req uire a dynamic model of j the process in order to achieve improved performance characteristics. Tw concept of ,

robustness relates to how far can the actual process deviate from the assumed process model and j still maintain required stability and desired performance improvement. Through extensive .

j simulation, this optimal controller, which is based on a one-delayed neutron group model, has i 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. Mike Power completed a masters thesis on the j experimental validation of the optimal controller robustness characteristics in December 1993.

i i Development of a robustness testing experimental program for LQG/LTR, H -based p-synthesis,

! and optimized feedforward / robust feedback was also initiated and will be continued into 1994-95.

i l Master's Thesis:

! Power, M. A., and R. M. Edwards, advisor. Experimental Validation of Robust Optimal Control of Nuclear ReactorTemperatures. December 1993.

j Papers: _

i j Power, M. A., R. M. Edwanis and D. E. Hughes. Experimental Verification of Robust Optimal i Nuclear Reactor Control. ANS Topical Meeting on Nuclear Power Plant Instrumentation, 4 Control, and Man Machine Interface Technologies, Oak Ridge, Tennessee. April 1993, i

j Weng, C. K., R. M. Edwards and Asok Ray. Robust Wide Range Control of Nuclear Reactors j Using the Feedforward-Feedback Concept. To appear in Nuclear Science and Engineering.

l Weng, C. K., R. M. Edwards and A. Ray, advisors. Automated Start-up, Shutdown, Wide-i Range Control of Steam-Electric Plants. A paper in Mechanical Engineering. December 1993.

l j i b

I 42 ,

i,

l Publication:

Weng, C. K., R. M. Edwards and A. Ray. Automation for Efficient and Safe Large Scale Power ,

Changes in Nuclear Power Plants. Trans. Amer. Nucl. Soc. 20:324-325, June 1994.

Nuclear Engineering j NSF/EPRI INTELLIGENT CONTROL OF TRIGA REACTOR TEMPERATURE

Participants:

R. M. Edwards K. Y. Lee S. J. Kenney

P. Ramaswamy l C.C.Ku i M. A. Power

! D. E. Hughes Services Provided: Laboratory Space, Machine Shop, Electronics Shop and Reactor Instrumentation and Support Staff 1

l 'Ihis is another major component of the NSF and EPRI funded project. Fuzzy logic and neural network algorithms for improving reactor temperature response were converted to the C language for implementation in the Bailey system desenbed in the previous section. Initial reactor expenments for the fuzzy logic controller were conducted and a complete set of robustness testing is planned for 1994-95. Development of a reconfigurable controller was also initiated and will be continued into 1994-95. The reconfigurable controller will evaluate the performance of the direct controllers (robust, fuzzy, neural, etc.) and make an automatic on-line decision as to which to enforce.

DoctoralTheses:

l Ku, C. C., and K.Y. Lee, advisor. Diagonal Recurrent Neural Networks for Control and System Identification. A Ph.D. dissertation in Electrical Engineering. May 1993.'

! Garcia, H., and A. Ray, advisor. A Reconfigurable Hybrid Supervisory Control System. A Ph.D. dissertation in Electrical Engineering. December 1993.

Papers:

i Ramaswamy, P., M. Riese, R. M. Edwards and K. Y., Lee. Two Approaches for Automating the Tuning Process of Fuzzy Logic Controllers. Pmceedings of the IEEE 32nd Conference on Decision and Control, pp 1753-1758, San Antonio, Texas. December 15-17,1993.

Ramaswamy, P., R. M. Edwards and K. Y. I.ee. An Automated Tuning Method of a Fuzzy logic Controller for Nuclear Reactors. IEEE Transactions on Nuclear Science, _40:1253-1262, August 1993.

Ku, C.C., K. Y. Lee and R. M. Edwards. Nuclear Reactor Control Using Diagonal Recurrent Neural Networks. Proceedings of International Federation of Automatic Control 12th World Congress 6:267-270, Sydney, Australia. July 19-23, 1993.

Ramaswamy, P., R. M. Edwards and K. Y. Lee. A Fuzzy Logic Controller Design for Nuclear Power Plant. Proceedings of International Federation of Automatic Control 12th World Congress,1:103-106, Sydney, Australia. July 19 23,1993.

i 43 i

Publications:

Kenney, S. J., M. A. Power, H. E. Garcia and R. M. Edwards. Temperature Performance I Feedback for an Intelligent Reconfigurable Reactor Power Controller. Trans. Amer. Nucl.

Soc.2Q:107-109, June 1994.

Ramaswamy, P., R. M. Edwards and K. Y. Lee. Fuzzy Logic Controller for Nuclear Power i Plant. Proceedings of the Second Intemational Forum on Applications of Neural Networks to Power Systems, pp 29-34, Yokohama, Japan. April 19-22, 1993.

Ku, C. C., K. Y. Lee and R. M. Edwards. Validation and Verification of Diagonal Neural Controller for Nuclear Power Plant. Proceedings of the Second International Forum on Applications of Neural Networks to Power Systems, pp 343-348, Yokohama, Japan.

April 19-22,1993.

Nuclear Eneineerine NSF/EPRI HYBRID SIMULATION OF BWR USING THE TRIGA REACTOR Panicipants: R. M. Edwards J. A. Turso D. E. Hughes Services Provided: Laboratory Space, Machine Shop, Electronics Shop and Reactor Instrumentation and Support Staff In this work, a low order simulation of a Boiling Water Reactor is operated in real-time in a PC computer and detennines the reactivity effect due to void dynamics of a commercial BWR. The reactivity is then induced in the TRIGA reactor using the Secondary Control Rod (SCR) described in the preceding research descriptions conceming robust and intelligent control. The resulting TRIGA reactor power fluctuation, which then corresponds to that actually observed in BWRs, drives the BWR void and reactivity dynamics simulation. 'ntis hybrid / simulation capability will be utilized in the coming year to develop and validate BWR stability monitoring techniques as pan of a FERMI project.

Paper:

Turso, J. A., R. M. Edwards and D. E. Hughes. Hybrid Reactor / Simulation Development for Commercial Power Plant Controller Testing. Proceedings of The 16th Biennial ANS Topical l

Meeting on Reactor Operations Experience: Present and Future Technologies-Applying Lessons Learned, pp 286-292, Long Island, New York. August 1993.

Publication:

Turso, J.A., R. M. Edwards and M. Bryan. Hybrid Simulation of Boiling Water Reactor (BWR)

Dynamics Using a University Research Reactor. Trans. Amer. Nucl. Soc. 20:323-324, June 1994.

44 i ._. _ _

j

i.; .

j Nuclear EnF ineerinF

). NSF/EPRI INTELLIGENT CONTROL WORKSHOP #1 j

Participants:

R. M. Edwartis 4

K. Y. Lee M. A. Power C. K. Weng i S. J. Kenney ,

l P. Ramaswamy l 1 J. A. Turso i s H. E. Garcia f l D. E. Hughes I i i i

Services Provided: Classmom and Laboratory Space, Reactor Instrumentation and Support Staff

)

A one day workshop for industry professionals was conducted on November 5,1993.

Re sentatives from two utilities, two national laboratories, the Nuclear Regulatory Commission, l j a reactor manufacturer attended. De workshop included presentations and TRIGA reactor 1 i demonstrations of the NSF/EPRI research.

i i i Publication: l' 1

Warhhap overheads and Reference Papers.

4 j NuclearEngineermg NEUTRON RADIOGRAPHY EXPERIMENTS FOR VERIFICATION OF i SOLUBLE BORON MIXING AND TRANSPORT MODELING UNDER NATURAL CIRCULATION CONDITIONS i lI

Participants:

M. A. Feltus

{ G. M. Morlang i i

! Service Provided: Neutron Radiography

?

i The major goal of this experimental research project is to provide separate effects tests in order to j hmch-rk baron transport models used in best-estimate thermal-hydraulic codes, such as RELAP -)

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

This research effort seeks to provide experimental results to quantify boron transport and mixing  !

I

! effects, and assess the boron mixing models used in the NRC RELAP and TRAC thermal-I hydraulics code series. The first series of experiments will model simple flow configurations to create baron 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 j Anticipated Transients Without Scram (ATWS) events and severe accident scenarios. De neutron i radiography visualization films and test results and analyses will provide sufficient information to j qualify t aermal-hydraulic boron tracking models, turbulent mixing assumptions, etc., to upgrade j NRC 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 45

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 penurbing the fluid flow stream with instrumentation or flow blockages. More conventional fluid flow measurements yield bulk mixing effects; however, the small concentration of boron and solute 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 rarliography technique provides significant advantages over more conventional fluid flov; methods:

1. There is no penurbation 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 effon will provide experimental benchmark information for boron transpon 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 simulate boron injection effects in ATWS conditions for BWR and PWR cores. Effects of turbulence and mixing can be simulated and measured to assess 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 Commission $56,406 Nuclear 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.

Sponsor: Bettis Atomic Power Laboratory $70,436 46

Nuclear Eneineering REACTOR BRIDGE CHANGE PROJECT

Participants:

D. E. Hughes T. Fritten D. Sathianathan M. Grieb R. Gould J. Inzeo J. Armstrong M. Pochet N. Bloser K. Rudy l M. E. Bryan K. Traver l R.Eaken t

! Services Provided: Neutron Radiography, Machine Shop and Electmnics Shop The Bridge Change Project increases the versatility of the RSEC by increasing the degrees of motion of the reactor core from 1 to 3. 'Ihe ultimate goal of the project is to allow a gmater number of xrmanent experimental facilities and to enhance the neutron beam entering the Neutron Beam l La xratory. This project was completed in June 1994. Actual use that takes advantage of the new l versatility has not occurred yet. There are four pending e,xperunental proposals that require the advantages afforded by the change; three of them will be unplemented in the next year.

Papers:

Hughes, D. E. Modification of the Penn State Reactor to allow Transverse and Rotational Core Motion. Invited Paper American Nuclear Society Annual Meeting, New Orleans, louisiana, June 19-23,1994.

Hughes, D. E. Modification of the Penn State Reactor to allow Transverse and Rotational Core Motion to Increase Operational Versatility. Presented at the 14th U.S. TRIGA Users Conference, General Atomics, San Diego, California, April 5-8,1994.

l l Sponsor: U.S. DOE $73,000 Penn State matching funds $85,000 Nuclear Eneineering l

PENN STATE BREAZEALE REACTOR MODERNIZATION PROJECT PHASE IV

Participants:

D. E. Hughes M. E. Bryan R. Gould M. Grieb Services Provided: Machine Shop and Electronics Shop The main thrust of this project is a new facility monitoring and alarm system. Over the years, due to regulatory and self-imposed controls the reactor facility is now responsible for monitoring and j maintaining a multitude of facility systems information. This monitoring and alarm system will give us the capability of monitoring these signals plus more importantly the flexibility to add additional alann and system status messages to the system as the need arises. The new system will consist of a Programmable logic Controller (PLC) located in the reactor control room and a distributed I/O system located in various laboratories throughout the facility. These remote I/O stations will be programmed individually to monitor and control equipment, sensors and associated reactor systems that are not presently monitored by the reactor control system. Each remote I/O I

station will be connected via a high speed network and remotely monitored by the PLC. The PLC l

47

i

! will communicate with a local com? uter that will allow for overall facility monitoring and alarm i logging. The logging computer will be located in the reactor control room and be utilized by the j f operations staff as a tool in determining facility equipment and alarm condition status.

! The majority of the equipment has been pun:hased and the system is undergoing design. Facility installation and testing of the completed system is planned for the last quarter of 1994 or 1st quarter l 1995. I l

Sponsor: DOE $44,036

! Penn State matching funds $23,712 i

l a

j Nuclear Engineering

! DEVELOPMENT OF A SOURCE HOLDER AND CONVERSION TABLES FOR i USE WITH EBERLINE RO-2'S TO ALLOW THE MEASUREMENT OF THE i SKIN DOSE RATES FROM BETA-GAMMA SOURCES i

Participants:

W. A. Jester S. H. Levine 1 T. J. Lin i

i Services Provided: Radiation Counters, Laboratory Space, Machine Shop, Isotope Production, 1

Low Level Monitoring Lab and Electronics Shop

!( In this project, technic ues are being developed to determine skin dose rates fmm beta-gamma i sources using an Eber ine RO-2 ion chamber. A pmgram called E13RO2 has been modified from j the ZEBRA code (a Monte Carlo pmgram developed by Martin J. Berger) for use in computing the j beta dose from an RO-2 measurement. The E13RO2 program is a two dimensional program i written in Turbo Basic and can be run on an IBM compatible microcomputer. It calculates the

energy deposited in the detector air volume and computes beta skin dose rates as a function of source type, source strength, source diameter, source-detector distances and shield between source and chamber. To fit the RO-2, the geometrical factors of that detector have been taken into j consideration.

1 l A table is being developed to evaluate the skin dose from RO-2 outputs as a function of the i measured dose ratio, which is the ratio of outputs obtained without and with a gradient shield of 7

) mg/cm 2mass thickness, various source radii and source-detector distances.

1

A source holder for the RO-2 chamber has been designed and finished to hold any kind of beta-

] gamma source at a fixed source-detector distance. 'Ihe holder has been used to measure many d

different sources to generate the conversion tables in cooperation with the E13RO2 program.

Measurements using 60Co,204T1,147Pm, and 90Sr/90Y sources under different conditions show good agreement with E13RO2 calculations.

i Papers:

! Jester, W. A., S. H. Ixvine, T. J. Lin and R. Hock. A Beta Skin Dose Monitor Using an

! Eberline RO-2. Abstracts 1994 Symposium on Radiation Measurements and Applications.

j Paper 2J9, May 1994.

j Jester, W. A., S. H. Levine, T. J. Lin and R. Hock. Eberline RO-2 Ion Chamber Used as a Beta j Skin Dose Monitor. Trans ANS,20:226,1994.

j Sponsor: Pennsylvania Power and Light Company $52,766 i

48

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t. .

j Nuclear Engineering i ENVIRONMENTAL BACKGROUND MONITORING USING ELECTRET PASSIVE ENVIRONMENTAL MONITORS Participant: W. A. Jester

! Services Provided: Radiation Counters, Laboratory Space and Low Level Monitoring Lab i

Rad-Elect Electret passive environmental monitors are a new type of monitor for the detection of gamma environmental radiation. For the past four years, quarterly measurements have been taken at ten positions in and near the Radiation Science Center. At the s ame time and locations, the university Health Physics staff has been making TLD measurements of the gamma background.

Results obtained from these two different methods of backgmund measurements are then compared.

Publication:

Kotrappa, P., and W. A. Jester. Elecuet Ion Chamber Radon Monitors Measured Dissolved 22Rn in Water. Health Physics fd (4):397-405. April 1993 Sponsor: Equipment donated by Rad-Elec $4,000 Nuclear Engineering NUCE 450 RADIATIO'e ="~'ECTION AND MEASUREMENT

Participants:

W. A. Jester M. H. Voth M. Dechaine Services Provided: Neutron Irradiation, Radiation Counters and Laboratory Space NucE 450 introduces the student to many of the types of radiation measurement systems used in the nuclear industry as well as many of the mathematical techniques used to process and interpret the meaning of measured data.

Nuclear Eneineering RADIOLOGICAL ANALYSIS OF THE MATERIALS USED IN THE +

PRODUCTION OF FEMORAL HEADS .

Participants:

W. A. Jester R. W. Granlund H. Boyle 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 three types of femoral balls used in hip joint replacement. The samples are composed of either zirconia, alumina, or 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.

I 49  ?

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Report:

Jester, W. A., and R. W. Granlund. Radiological Analysis of the Materials Used in the Production of Femoral Heads. Progress report submitted to Howmedica, Inc. February 1994.

Sponsor: Howmedica, Inc. $15,000 Nuclear Eneineering SEPARATION OF IODIDE IN REACTOR EFFLUENT USING ION CHROMATOGRAPHY AND ON LINE DETECTION

Participants:

W. A. Jester U. Senaratne Services Provided: Laboratory Space, Low Level Monitoring and Ion Chromatograph Unit Project involves separation ofiodide from other anions present in reactor effluent using ion chromatography, and development of an on-line detection system to quantify the iodide present.

Work on the project commenced it' early 1994. The analytical columns required for the chromatograph have been identified and a request for funding to purchase these has been identified and a request for funding to purchase these has been made. The radiation detectors required for detection and quantification of the different iodine isotopes are being looked into as well.

Nuclear Eneineering THE DETERMINATION OF SEVERAL KEY EXPOSURE PARAMETERS FOR LIGHT WATER REACTORS USING THE MATERIAL SCRAPINGS METHODOLOGY

Participants:

W. A. Jester H. S. Basha Services Provided: Neutron Irradiation, Hot Cell Lab, Machine Shop and Flux Monitoring The material scrapings technology consists of taking scrapings samples from critical vessel components and use the scrapings dosimetry data to accurately predict the neutron exposure of these components. This technique can be used to predict the service-life and integrity of many of these components and, thus, help nuclear utilities m formulating plans for plant life extension. To benchmark this approach, several flux monitors were irradiated in the TRIGA reactor at Penn State to a fast neutron fluence level of - 1017 n/cm2. The flux monitors were used to establish the neutron spectra at the irradiation position.

The dosimetry data from the scrapings samples were used in a spectral unfolding / adjustment programs to calculate the neutron spectra. Several parameters were used in the comparison meluding Q > 3 MeV, Q > 1.0 MeV, Q > .01 MeV, and Q > 0.01 MeV. The 54Fe(n,p) and 58Ni(n,p) reactions produced fast flux data within 7% of those determined using conventional techniques. Other reactions such as 58Fe(n,y),58Ni(n,2n), and 59Co(n,y) were used to improve the spectral coverage in the intennediate to thermal energy range. The overall difference in the flux data determined using the conventional and scrapings techniques in the intermediate energy range was approximately 12%. Other reactions currently under investigation include 95Mo(n,p),

64Zn(n,y),180W(n,2n),169Tm(n,2),181Ta(n,y),109Ag(n,y), and 50Cr(n,y). Additionally, in the 50

. . - -. . - - - . - - . _ - - .= -. . -- . .. . . - -

future, we will be investigating reactions that produce stable nuclides or nuclides with very long half-lives, since these reactions can be used for long term flux monitoring. Also, since the accuracy of our results depends in large part on the dosimetry cross section library being used, several recently released dosimetry cross section libraries will be investigated for their accuracy.

Den a single dosimetry cross section library will be established that includes cross sections for all the reactions that are going to be used in the scrapings technology.

DoctoralThesis:

Basha, H. S., and W. A. Jester. He Determination of Several Key Exposure Parameters for Plant Life Extension of Light Water Reactors Using the Material Scrapings Methodology.

Publication:

Basha, H. S., and W. A. Jester. Non-Conventional Approach for the Determination of Several Key Exposure Parameters for Light Water Reactors. Trans. Am. Nucl. Soc. Vol. 71, June 1994.

Nuclear Enrineering THE ESTABLISHMENT OF A CAPABILITY TO ANALYZE ENVIRONMENTAL SAMPLES FOR BACKGROUND LEVELS OF IODINE-129

Participants:

W. A. Jester J. Kwon Services Provided: Neutron Irradiation, Radiation Counters and Low Level Monitoring lodine-129 is present in the envimnment at very low levels. This nuclide has such characteristics .

as long half-life, high mobility, radiotoxicity and hard-to-detect. Especially, the emitted energy of  !

Iodine-129 is so low that the Neutron Activation Analysis (NAA) method is utilized to quantify the i Iodine-129. De highly analytical sensitivity by NAA permits concentration measurements at levels much below those required for radiation protection.

De radiations from Iodine-130 produced by neutron irradiation are more easily measured than the low-energy emission of Iodine-129 itself. However, natural environmental samples contain a lot of interfering elements. To minimize these effects, radiochemical separation of the iodine from the environmental samples is necessary to obtain reliable results.

Currently, the experimental procedures are established and chemicals and apparatuses are being purchased. The analysis of Iodine-129 concentration in water samples will begin at once.

Nuclear Eneineering PIPE WALL THINNING USING SCATTERED GAMMA RAYS

Participants:

E. S. Kenney X Xu R. Gould S. Kahn Services Provided: Hot Cell Lab, Radiation Counters, Laboratory Space, Machine Shop, Isotope Production and Electronics Shop 51

i i

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 that pipe wall thinning can be detected using scattered gamma rays. A combination of Monte Carlo studies and pilot experiments have confirmed the potential of such a technique. A laboratory 1 prototype gauge using up to 0.5 curies ofIr-192 was used initially. A field usable device was then l developed to use up to 0.5 curie of Hg-203. i Doctoral Thesis:

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

Paper:

Xu, X., E. S. Kenney, E. H. Klevans, R. Gould and S. Khan. A High Speed Compton Scatter Pipe Wall Imaging System. Symposium on Radiation Measurement and Instruments, Ann Arbor, Michigan, May 1994.

Sponsor: FERMI $30,000 Nuclear Engineering NEUTRON ATTENUATION MEASUREMENTS OF BORAFLEX

Participants:

D. Kline D. Vonada K. Lindquist Services Provided: Neutron Irradiation, Neutron Instrumentation and Neutron Beam Lab The purpose of this project is to measure the neutron attenuation of boraflex coupons that have been taken from fuel storage racks. It is a,part of a larger project to monitor the performance of the boraflex which is used to control the reactivity of spent nuclear fuel. The attenuation measurements are made by using a fission chamber instrument to compare the incident beam with the transmitted beam.

Nuclear Engineering PROPERTIES OF THE NEUTRON ABSORBER MATERIAL BORAFLEX

Participants:

D. Kline D. Vonada K. Lindquist Services Provided: Neutron Irradiation and Laboratory Space Boraflex is a composite polymer of polysiloxanes with a B4 C-filler used in maximum-density storage of fuel elements to control the reactivity. The performance of Boraflex over its expected service life has not, as yet, been determined.

Data from the literature conceming polydimethylsiloxane were evaluated a few years ago, and Boraflex coupon monitoring is currently being carried out at storage pool sites. It is also of academic interest to study some of the properties of the polymer using the nuclear reactor (PSBR),

and other facilities.

52 i

i It is hoped that results can be obtained to explain cenain aspects of the changes in properties, and

( that they can be used by utilities throughout Pennsylvania and the United States in estimating j and/or extending the service life of the B4C-filled polymer system.

An additional phase involves ascertaining property changes of in-service Boraflex. About once per year a surveillance coupon from a storage pool is sent to PSU and evaluated for radiation-induced changes. Fractions of deteriorated Boraflex with a substantial irradiation history are also monitored for possible post, irradiation deterioration in water baths held at controlled conditions which simulated the in-service envuonment of this material.

Nuclear Eneineering PROOF OF PRINCIPLE TESTS TO EVALUATE . NEUTRON ABSORBERS IN SITU

Participants:

D. Kline D. Vonada K. Lindquist Services Provided: Neutron Irradiation, Laboratory Space and Beam Hole Lab This research is applied to the use of neutron detector systems for evaluation of material performance in spent fuel racks of storage pools With time, the propenies of neutron absorbers can change and this can potentially cause concem with respect to the Keft of the fuel assemblies in the storage racks. Preliminary experiments using the neutron beam are part of proof-of-principle tests for delineating the effectiveness of the neutron absorbers.

Sponsor: Electric Power Research Institute Plant Patholorv BIOLOGY, MYCOTOXICOLOGY AND TAXONOMY OF FUSARIUM SPECIES Participant: P. E. Nelson

! J.Juba l

Service Provided: Gamma Irradiation Carnation leaf agar is irradiated in the Cobalt-60 facility in order to provide a sterile growing medium for Fusarium species in various studies at the Fusarium Research Center.

53

l B. OTHER UNIVERSITIES, ORGANIZATIONS AND COMPANIES UTILIZING THE FACILITIES OF THE RADIATION SCIENCE AND ENGINEERING CENTER University or Industry Tvos of Use l

American Inspection Agency Environmental Analyses Armed Forces Radiobiology Research Institute Neutron Activation Analyses Reactivity Computer Bettis Labs, Westinghouse Neutron Radiography CarpenterTechnology Neutron Irradiation CB-Tech Neutron Activation Analyses Fairway Laboratories Environmental Analyses Geochemical Testing Environmental Analyses GlobalTechnology Consultants MaterialTesting Harris Semiconductor SemiconductorIrradiation l Honeywell SemiconductorIrradiation I

Howmedica Radiological Analyses Isotec Incorporated Neutron Activation Analyses MPM Research and Technology MaterialTesting National Institute of Science and Technology Neutron Irradiation (NIST)

National Sanitation Foundation Environmental Analyses Nonh American Refractories Radiological Analyses

! NortheastTechnology Corporation Neutron Radiography l

Nuclear Research Corporation GammaIrradiation Pennsylvania Power and Light Radiation Dosimetry P. R. Hoffman Materials Processing Corp. CobaltIrradiation Q. C. Inc. Environmental Analyses 1 Rad-Elec Environmental Analyses l Raytheon SemiconductorIrradiation Sandia National Laboratory Neutron Energy Spectrum Analyses Seewald Laboratories Environmental Analyses SEMTECH GammaIrradiation St. Mary's City Museum Neutron Radiography Neutron Activation Analyses Tru-Tec Isotopes for Tracer Studies University of Maryland Perturbed Angular Correlation Wright Lab Services Environmental Analyses i

54

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APPENDIX A Personnel Utilizing the Facilities of the Penn State RSEC.

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

COLLEGE OF AGRICULTURE COLLEGE OFENGINEERING Animal Science  !

Electrical Engineering j Kephart, Kenneth (F)

Ben-Abdennour, A. (G)

Food Science Garcia, Humberto (G)

Ku, C. C. (G)

Roberts, Robert (F) Lee, K. Y. (F) ,

Ramaswamy, P. (G) 2 Plant Patholorv Riese, M. (G)

Juba, Jean (S) Engineering Science and Mechanics i Nelson, Paul (F)  !

Gabrys, Jon (G)  !

Veterinary Science Lenahan, Patrick (F)

Whary, Mark (G) Mechanical Engineering Hutchinson, Larry (F)

Bobulinski, Anthony (U)

COLLEGE OF EARTH & MINERALSCIENCES Bloser Nathan (U)

Cimbala, John (F)

Ceramic Science and Engineering Donato, Brian (U) l

Fritton, Tim (U)

Brown, P. W. (F) Inzeo, Jeremy (U)

Pochet, Marc (U)

Materials Science and Engineering Prescott, Patrick (F)

Ray, Asok (F)

Brown, Paul (F) Shatto, Kevin (G)

Schlom, D. G. (F) Singh, V. K. (G)

Tenhuisen, Kevor (G) Traver, Keith (U)

Metals Science and Engineering Nuclear Eneineering Cuddy, Lee (F)

Howell, Paul (F) Adams, James (G)

Irwin, Mark (G) Basha, Hassan (G)

Martinko, John (G) Baratta, Anthony (F)

Poduri, Ram (G) Belhadj, Abdelali(IAEA)

Ryba, Earle (F) Boyle, Hermina (S)

Boyle, Patrick (S)

Bryan, Mac (S)

Catchen, Gary (F)

Chang, Yi-Jui (G)

Chavez, Carl (G)

Cumblidge, Steven (U) 55

- _ . _. . - . -- . _ . ~

APPENDIX A (Continued)

Personnel Utilizing the Facilities of the Penn State RSEC.

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

Nuclear Engineering COLLEGE OF LIBERAL ARTS Daubenspeck,Thierry (S) Anthronology Davison, Candace (S)

Deithorn, Ward (F) Hirth, Kenneth (F)

Dulloo, Abdul(G)

-Edwards, Robert (F) COLLEGE OF SCIENCE Esh, David (U)

Feltus, Madeline (F) Chemistry Flinchbaugh, Terry (S)

Franc,Ladislav (IAEA) Allcock, Harry (F)

Grieb, Mark (S) Ambrosio, Archel(G)

Gould, Roben (F) Dudley, Gary (G)

Hollinger, Ed (G) Kim, Young Back (PD)

Hughes, Dan (F) Morrisey, Chris (G)

He, Jianhui(G) Naperiela, M. (G)-

Jester, William (F) O'Connor, S. M. (PD)

Kahn, Saif(G) Olshavsky, M. (G)

Kenney, Edward (F) Pucher, Shawn, (G)

Kwon, Junhyun (G) Ravikiran, R. (G)

Lee, Kwangho (G) Reed, Carey (G)

Lin, Tzyy-Jye (G) Silverberg, Eric (G)

Miller, David (S) Smith, Dawn (F)

Morlang, Mike (G) - Visscher, Karyn (PD)

Power, Mike (G)

Rearick,Todd (G) Molecular and Cell Biolony Rudy, Kenneth (S)

~

Senaratne, Uditha (G) Bour, Barbara (G)

Sipos, Rick (S)

Turso, James (G) INTERCOLLEGIATE PROGRAMS Vergato, Bryan (S)

Voth, Marcus (F) Health Physics Walter, Philip (G)

Xu, Xiangjun (G) Boeldt, Eric (S)

Yeh, Tsung-Kuang (G) Granlund, Rodger (S)

Hollenbach, Donald (S)

School of Engineering Technology and Commonwealth Camous Engineering Sathianathan, Dhushy (F) 56

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i APPENDIX A (Continued)

, INDUSTRIES l

AmericanInspection Agency ........................ Harris, George Armed Forces Radiobiology Research Institute ........................ George, Robert Miller, Steven Moore, Mark Bettis Labs, Westinghouse ........................ Glickstein, Stan Murphy, Jack I

CarpenterTechnology ........................ Balhett, Thomas CB-Tech ........................ Bleistein, Charles Fairway Laboratories' ........................ Markel, William L. Jr.

GeochemicalTesting ........................ Bergstresser, Tim GlobalTechnology Consultants ........................ Newman, Keith Harris Semiconductor ........................ Kalkbrenner, F.

Honeywell ........................ Hildebrand, K.

Howmedica ........................ Hizer, Jennifer Isotec Incorporated ........................ Smith, Keith MPM Research and Technology ........................ Manahan, Michael National Institute of Science and Technology ........................ Becker, Donald National Sanitation Foundation ........................ Miller, Michael P.

North American Refractories ........................ Wealand, L.

NortheastTechnology Corporation ........................ Kline, Don Lindquist, Kenneth O.

Vonada, Doug Nuclear Research Corporation ........................ Pagano, Frank Riggin, Fred Pennsylvania Power and Light ........................ Hock, Ray P. R. Hoffman Materials Pmcessing Corporation ........................ Casey, Ken

! Kingsborough, Lee Q. C. Inc. ........................ Dascoli,Je:n l

Rad-Elec ........................ Kotrappa, P.

l Raytheon ....... ................ Dietre, R.

Mikulski, C. V.

Mulford, S.

Roberts, K. S.

Stransky, D. F.

SEMTECH ........................ Manders, Sharon Sandia NationalLaboratory ........................ Kelly, John Seewald Laboratories ........................ Chianelli, Robert E.

St. Mary's City Museum ........................ Harry, Silas D.

Miller, Henry l Tru-Tec ........................ Boothe, Mike l

Kolek, Jerome Flenniken, Mike Owens, J. D.

Wright Lab Services ........................ Milnes, Jan I

57

I I APPENDIX A (Continued)  ;

i i  !

l UNIVERSITIES r

University of Maryland Rasera, Robert L. Professor of Physics MISCELLANEOUS LLRML - 43 laboratories representing 222 public water systerns (only 6 major laboratories are listed above)

Various Cobalt - 60 irradiations for high school classes' research projects.

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> . i APPENDIX B l FORMAL TOUR GROUPS l l

JULY 1993. NUMBER OF l JUNE 1994 DAY NAME OF TOUR GROUP P ARTICIP A NTS July 1 Renew 18 1 7 BM Kramer 2 l 8 Aerospace 11 13 Hite Company 965 14 Upward Bound 1008 16 M.O.S.E.T. 16  ;

1 16 ATOMS 27 17 NCTII Student Guests 2 19 Science and Engineering Research Center 10 21 BEST 24 23 MPM Consulting 2 28 Geoscience 7 30 Enter 2000 33

August 2 Summer Study Group 7

! 2 Govemmental Affairs 2 4 National Faculty Group 22 4 Boiler & HVAC Group 15 5 Aerospace 10 23 Undergraduate Students 6 24 NucE Freshmen 2 24 New NucE Graduate Students 7 27 PEMA 7 l September 2 Science and Technology 471 7 20 Westinghouse 3 21 EPRI 2 23 Philadelphia Electric-IPAC 1 28 WRSC 2 October 2 Open House Parent's Weekend-1993 77 7 Agronomy 5 11 University Scholars 3 22 PSEOP Members-Penn State 8 25 DER 7 l 26 FERhD 3 l 26 17

$$ Tour 27 Bio Science 3 17 l November 1 Jr. Science Symposium 27 1 Congressman Hasten-NRC Exemption Fee 4 3 West Branch High School 29 5 Control 14 10 Harmony High School 38 10 ASME, Math Sci 101 13 12 Lower Dauphin High School 10 12 WTAJ Action News 3 22 Union City High School 15 59

APPENDIX B FORMAL TOUR GROUPS

{

(Continued) 1 JULY 1993 NUMBER OF JUNE 1994 M NAME OF TOUR GROUP PARTICIPANTS November 23 St. Vincent College 11 December 1 Wyomissing High School 9 1 Material Science 101 10 2 Science Interest & Material Science 101 16 10 St. Carroll High School 35 14 Health Physics Tour 3 14 State College Delta Program 5 15 Carlisle High School 50 February 8 Police Services Training 15 9 MRL Graduate Students 12 -

15 Police Services Training 14 22 Police Services Training 15 25 CE 270 42 25 ANS Group 12 '

26 Engineering Open House 1994 194 March 18 Daniel Boone High School 12 23 Peters Township High School 14 25 Admissions Tour Group 3  !

28 German Students 48  ;

30 Redland High School 19 April 6 State College High School 16 6 Juniata College 3 8 Jersey Shore High School 9 8 Indiana University of PA 9 ,

8 Prospective Students 7 '

11 Mt. Union High School 18  ;

15 Ridgeway High School 22 15 St. Mary's High School 22 19 Grove City College 11 20 Harbor Creek High School 9 22 East Stroudsburg High School 10 25 Camp Hill High School 9 26 Bio Chem Students 7 28 Bring-Your-Daughter-to-Work Tour 6 29 Berlin Brothers Valley High School 9 May 2 Northem Bedford High School 25 6 State College High School 22 9 Muncy High School 34 11 Dallastown High School 13 14 NED Graduation Open House 32 16 Twin Valley Middle School 47 17 Somerset High School 24 60

a APPENDIX B FORMAL TOUR GROUPS (Continued)

JULY 1993 NUMBER OF

.IUNE 1994 DAY NAME OF TOUR GROUP PARTICIPANTS May 17 University of Pittsburgh 5 19 Bellefonte High School-National Honor Society 24 20 Chartiers Houston High School 21 23 Danville High School 25 24 Lithuania Tour Group 5 24 Bermudian Springs High School 5 24 Westmont Hilltop High School 14 24 DER Toup Group 13 i

26 Occupational Health MedicalGroup 5 i i June 1 Wingate Elementary School 23 2 College of Agriculture 1 21 Women in Engineering 1636 22 Women in Engineering 13  ;

23 Women in Engineering 12 29 Atoms Group 35 30 GPU Nuclear Concepts 24 l

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