ML20071B361

Twenty-Seventh Annual Progress Rept of PA State Univ Breazeale Nuclear Reactor,Jul 1981 - June 1982.

ML20071B361
Person / Time
Site:	Pennsylvania State University
Issue date:	07/31/1982
From:	Levine S, Totenbier R PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA
To:
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ML20071B356	List: ML20071B355 ML20071B361
References
PSBR-315-498296, NUDOCS 8302280192
Download: ML20071B361 (58)

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i Contract DE-AC02-76ER03409 TWENTY-SEVENTH ANNUAL PROGRESS P2 PORT OF THE PENNSYLVANIA STATE UNIVERSITY BREAZEALE NUCLEAR REACTOR

' July 1, 1981 to June 30, 1982 Submitted to

' United States Department of Energy and The Pennsylvania State University i

5 by Samuel H. Levine (Director)

Robert E. Totenbier (Editor)

Breazeale Nuclear Reactor Department of Nuclear. Engineering The Pennsylvania State University University Park, Pennsylvania July 1982 PSBR 315-498296 h

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4 ACKNOWLEDGMENTS The editor wishes to express his appreciation to all contributors for their timely research and project reports. Special thanks should be given to S. H. Levine for.the Introduction, I. B. McMaster and J. R. McKee for the Personnel section, J. J. Bonner for the Co-60

- Facility section, J. L.-Penkala for the Education and Training section, and W. A. Jester for the Radionuclear Applications Laboratory summary. In addition, this report would not have been completed on time wihtout the help of the nimble fingers of M. Beward and R. Murgas.

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9 TABLE OF CONTENTS Page ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . iii TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . v I. INTRODUCTION - S. H. Levine . . . . . . . . . . . . . 1 II. . PERSONNEL - I. B. McMaster, J. R. McKee . . . . . . . 5 III. REACTOR FACILITY - R. E. Totenbier . . . . . . . . . 11 IV. COBALT-60 FACILITY - J. J. Bonner . . . . . . . . . . 15 V. ELUCATION AND TRAINING - J. L. Penkala. . . . . . . . 17 VI. RADIONUCLEAR APPLICATIONS LABORATORY - W. A. Jester . 23 VII. FACILITY RESEARCH UTILIZATION - R. E. Totenbier . . . 27 A. University Research Utilizing the Facilities of the Penn State Breazeale Nuclear Reactor . . . 28 B. Industrial Research Utilizing the Facilities of the Penn State Breazeale Nuclear Reactor . . . 39 APPENDIX A: Faculty, Staff and Students Utilizing the Facilities of the Penn State Breazeale Nuclear Reactor - R. E. Totenbier. . . . . . . 41 APPENDIX B: Formal Group Tours - R. E. Murgas. . . . . . . 47 iv 1

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TABLES Table Page 1 Personnel . . . . . . .. . . . . . . . . . . . . . 7 2 Reactor Operation Data . . . . . . . . . . . . . . 13 3' Reactor Utilization Data. . . . . . . . . . . . . . 14 4 Cobalt-60 Utilization Data. . . . . . . . . . . . 16 5' High School Nuclear Science Program . . . . . . . . 19 FIGURES Figure h 1 Organization Chart. . . . . . . . . . . . . . . . . 9 V

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I. INTRODUCTION The Twenty-seventh Annual Progress Report of the operation of The Pennsylvania State University Breazeale Reactor is submitted in accordance with the requirements of Contract DE-AC02-76ER0349 with the United States Department of Energy. This report also-provides the University administration with a summary of the operation of the facility for the past year.

Administrative responsibility for the Breazeale Reactor facility resides in the Department of Nuclear Engineering in the College of Engineering. It is operated, primarily, as a facility of the University that is available to all colleges of the University for their education and research programs.

In: addition, the' facility is made available to Commonwealth industries to provide services that are essential in solving their research and development ,

problems.

One of the concepts that resulted from obaerving the neutron detector response of the Three Mile Island Unit-2 (TMI-2) accident is the Non-Invasive Liquid Level Density Gauge for nuclear power reactors. To date there is no satisfactory way of determining the water height in the pressure vessel of a Light Water Reactor. As described in Section VII, Facility Research Utilization, this' technique shows promise for solving the water height measurement problem. There are many other interesting research problems being studied using the PSBR-facility. Among them are determining the non-homogeneities in a soil system, the archeological study of prehistoric trade relationships in the Easterr. United States, study of reptiles, and the study of digestive processes in ruminants, to name a few. This report lists 9

researchers covering a wide range of technical disciplines that use the PSBR to advance knowledge in'their field of expertise.

The Radionuclear Applications Laboratory is continuing to provide excellent analytical capability. Utilization of the laboratory has increased during the past year. This can be partially explained by the new equipment and facilities placed into operation during the past year. This includes an automatic sample changer, a multichannel analyzer-computer system, and a 20%

' efficient High Purity Germanium Coaxial Detector with shield. The Low-Level

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Radiation Monitoring Laboratory (LLRML) has received an Interim Certification

'for monitoring radioactivity in water as required by the National Safe Drinking Water Act. Of particular importance to the PSBR is the awarding of a radiation monitoring contract to this laboratory by Pennsylvania Power &

L1ght Company. The activities of the Radionuclear Applications Laboratory are making a major contribution to the PSBR.

Education and Training has become a most important factor in the use of the Breazeale Reactor. The number of courses taught using the reactor, the Nuclear Concepts and Energy Resources Institute (NCERI) in educating high school science teachers, high school student experiments, and the industrial training of reactor operators for nuclear power plants continues to grow impressively. During this period, four industrial training programs were offered to 51 operations personnel providing needed income to the facility and the Nuclear Engineering Department. There were 137 groups totaling more than 2,125 people who visited the facility on guided tours during the year.

, This total does not include visitors for business purposes, small groups, and many casual visitors who are also guided through the facility.

It is also important to recognize that the reactor provides experimental facilities that are necessary in the performance of some contracts; otherwise, faculty and students would either conduct their reactor experiments out of the Commonwealth of Pennsylvania at additional costs to them or eliminate this portion of the work from their contracts. During the year, 39 Penn State-University faculty and staff and 21 graduate-students made use of the facility for research.

The reactor staff and the Nuclear Reactor Safeguards Committee continue to review the operation of the facility in an effort to maintain the safety and' improve the efficiency of its operation and to provide conditions conducive to its utilization. The Nuclear Reactor Safeguards Committee met four times to confer with the staff on unusual experiments, to review operational records, sud to consult on special operational problems. No NRC inspections were conducted during the period covered by this report.

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.. ,s Messrs. J. J. Bonner, D. R. Shaulis, and A. R. Carusone successfully passed the NRC reactor operator examination; J. J.(Bonner is now a Senior ~

Reactor Operator and the other two are Reactor Operators.

An independent audit of the Breazeale Reactor operation was conducted by.Mr. P. M. Orlosky of the State University of New York at Buffalo, on April 16 & 19, 1982. The purpose of the audit was to determine the University's ability to meet the licensing requirement as required by technical specifications, government regulations and established procedures.

A formal written report of this audit was received and will be reviewed by the Nuclear Reactor Safeguards Committee. No violations of compliance were found; however, the audit will probably-result in constructive changes in the operation of the facility. Dr. S. H. Levine conducted a similar audit of the Buffalo reactor facility'on a reciprocal agreement.

Last, but not least, is the recognition of a member of the facility who has worked and served The Pennsylvania State University for twenty-five years with loyalty and distinction. Mr. Robert E. Totenbier was recognized by the University for having attained this landmark. During the next -year two other members of the staff will receive recognition for

their twenty-five years of service.

The following sections of this report are intended to provide an outline of the various aspects of the operation of the facility. Personnel, operation and utilization, statistics and research are summarized in the various sections that' follow.

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_ II. _ PERSONNEL There have been no changes in reactor operating staff during the year.

Licensing activities during the year have included the successful completion of Re:ctor Operators Examination and the licensing of both D. R. Shaulis and A. R. Carusone. Their additional assistance to the operation is most welcome. Mr. J. J. Bonner successfully completed a Senior Operators Examination during the year, but because of administrative delays within the NRC, has not yet received his license.

NW. B. C. Ford's fixed-term appointment as a Project Assistant to assist W. A. Jester in the Water Analysis Laboratory and Neutron Activatica Laboratory has been extended for an additional year.

I We had the pleasure this year of honoring another staff member for 25 years of service at the facility. R. E. Totenbier received his 25-year service award from the University-through the College of Engineering.

-The Reactor _ Safeguards Committee was under the chairmanship of Dr. Robert Bland this year. As with each passing year, some members' terms expire and new members were appointed to replace them. The complete listing

~'of the present committee membership is found in Table-1.

Dr. K. K. S. Pillay, a member of the PSBR staff and Nuclear Engineering faculty for 11 years, resigned to accept a position at Los Alamos National

. Laboratory. His academic talents and friendship will be missed. He has, however,' agreed to remain "as active as 2000 miles - -it" by accepting an Adjunct Associate Professor appointment.

In February 1982, Gary L. Catchen joined the Nuclear Engineering faculty as an Aseistant Professor to fill'the position vacated by K. K.-S.

Pillay.

Mr. J. J. Bonner has assumed the dual role of Reactor Supervisor and Faculty Associate. He is the first in the College to receive such an appointment. In this role he will continue to be a PSBR staff member but will also-be able to teach and do research as a principal investigator.

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Table 1 lists the personnel associated with the operation of the

{ reactor facility. An organization chart, Figure 1, reflects the present area of responsibility of the permanent reactor staff. .,

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Table 1 PERSONNEL Faculty and Staff

• J. J. Bonner - Reactor Supervisor / Auxiliary Operations Specialist B. C. Ford - Project Assistant

• • T. L. Flinchbaugh - Reactor Supervisor / Nuclear Education Specialist

• A. R. Carusone' - Reactor Supervisor / Nuclear Education Specialist G. L. Catchen -

Assistant Professor W. A. Jester -

Associate Professor

• • S. H. Levine - Professor / Director J. R. McKee - Coordinator, Energy Education Programs

• • I. B. McMaster - Research Assistant / Deputy Director

• • J. L. Penkala -

Research Assistant K. K. S. Pillay (Resigned 8/31/82)' - Associate Professor

• • D. C. Raupach - Reactor Supervisor / Reactor Utilization Specialist

• K. E. Rudy - Senior Engineering Aide-Nkchanical Services

-J. K. Shillenn - Energy Education Specialist /

Technology Transfer

• • R. E. Totenbier - Research Assistant / Operations

' Supervisor

• D. S. Vonada - Electronics Designer Technical Service Staff W. A. Davy -

Custodian / Driver R. L. Eaken - Experimental and Maintenance Mechanic

• D.'R. Shaulis -

Maintenance Worker / Reactor Operator

' Clerical M. D. Beward - Facility Secretary

.R. E. Murgas - Secretary and Receptionist s

• Licensed Operato

• • Licensed Senior Operator 7

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Table 1 (continued)

Graduate Assistants j D. Chang- -

Graduate Assistant M. A. Gibbs -

Graduate Assistant-H. Y.'Hwang -

Graduate Assistant M. Y. Khalil - Graduate Assistant S. S. Kim' - Graduate Assistant E. W. Okyere -

Graduate Assistant C. R. Savage Graduate Assistant / DOE Fellow T.~T. Tseng - Graduate Assistant C. Yu -

Graduate Assistant Health Physics E. C. Augustine -

Health Physics Assistant N. M. Dougherty (resigned 12/31/81) - Associate Health Physicist R. W. Granlund - Un. rsity Health Physicist D. H. Hollenbach -

Hea;ch Physics Assistant Nuclear Reactor Safeguards Committee A. J. Baratta, Assistant. Professor, Nuclear Engineering R. E. Bland, Associate Professor, Engineering Research, ARL (Chairman)

R. W. Granlund, Health Physicist, Intercollege Research Programs and Facilities F. Helfferich, Professor, Chemical Engineering W. P. Kovacik, Westinghouse Research Laboratories S. S. Lestz, Professor, Mechanical Engineering S. H. Levine, Professor and Director,'Breazeale Nuclear Reactor J. R. McKee, Coordinator, Energy Education Programs, Nuclear Engineering (Secretary)

- I. B. McMaster, Research Assistant and Deputy Director, Breazeale Nuclear Reactor W. W. Miller, Professor Emeritus of Chemistry R. T. Perry, Assistant Professor, General Engineering, Altoona Campus 8

NUCLEAR ENGINEERING DEPARTMENT - HEAD W. F. Witzig ADMINISTRATIVE AIDE J. R. McKee l

NUCLEAR REACTOR UNIVERSITY HEALTH ___

BREAZEALE NUCLEAR REACTOR __ SAFEGUARDS COMMITTEE PHYSICS Director - S. H. Levine Deputy Director - I. B. McMaster 1

e SECRETARIAL STAFF RADIONUCLEAR APPLICATIONS M. D. Beward LABORATORY R. E. Murgas W. A. Jester G. L. Catchen INSTR. & CONT. TRAINING FACILITY OPERATIONS MACHINE SHOP & BLDG. MAIN.

J. L. Penkala R. E. Totenbier K. E. Rudy D. S. Vonada T. L. Flinchbaugh D. C. Raupach R. L. Eaken J. J. Bonner W. A. Davy A. R. Carusone '

l ORGANIZATION CHART Figure 1

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

Utilization of the Reactor. falls into three major categories:

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

L Training programs for Reactor Operators and Reactor Supervisors are l continuously offered and can be tailored to meet the needs of the partici-pants. Individuals taking part in these programs fall into such categories l

as foreign t:41nees, graduate students, and power plant operating personnel.

I Research occupies much of the remaining reactor time for Radionuclear Applications and faculty and graduate students throughout the University

.who utilize the Reactor in a myriad of research programs.

The PSBR core, containing about 7 pounds of Uranium-235, in a form not applicable to weapons, is operated at a depth of approximately 18 feet in a pool of demineralized water. The water provides the needed shielding i and cooling for the operation of the reactor. It is relatively simple to expose a sample by merely positioning it in the vicinity of the reactor at a' point where'it will receive the desired radiation dose. A variety of fixtures and jigs are available for such positioning. Various containers and irradiation tubes can be used to k'eep samples dry. Three pneumatic transfer systems with different neutron levels offer additional possibilities.

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In normal steady state operation at 1000 kilowatts, the thermal 13 neutron flux available varies from approximately 1 x 10 n/cm2 /see at the edge of the core to approximately 3 x 1013n/cm 2/sec in the central region of the core.

When considering the pulse mode of operation, the peak flux for a 18 maximum pulse is approximately 6 x 10 n/cm2 /see with a pulse width of 15 maec at is maximum.

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

A comparison of the operation and utilization data for the past two years, as listed in Tables 2 and 3, indicates relatively small changes except-in a few areas. The hours apent in adjusting fuel was higher in 80-81 because two annual fuel inspections were performed during this period. The hours critical and consequently the energy releases were higher during 81-82 as a result of an increase in demand for long-term irradiations. Although the number of samples more than doubled, most of the increase was for pneumatic transfer system samples which are short duration runs. Thus the overall sample hours total actually decreased slightly.~ . Variations in the remaining data are relatively insignificant.

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Table 2 Reactor Operation Data July 1, 1980 - June 30, 1982 80-81 82 A. Hours of Critical Time

1. Hours Critical 493 614

2. Approaching Critical 145 238

3. Adjusting Fuel 81 48 B. Number of Pulses 161 217 C. Number of Square Waves 81 142 6- D. Energy Release (MWH) 271 302 E. Grams U-235 Consumed 14 16 F. Number of Scrams

1. Planned as part of. experiments 113 173

2. Unplanned - resulting from a) Personnel action

• 10 17 b) Abnormal system operation 2 5 The majority of these resulted from operation by trainees.

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Table 3 Reactor Utilitation Data (average per shift)

July 1, 1980 - June 30, 1982 80-81 81-82 A. Number of Users 2.8 3.0 B. Samples or Experiments

1. Pneumatic transfer samples 0.9 4.2

2. Total number of samples 4.3 9.7

3. Sample hours 17.9 15.9 C. Reactor Usage (hours)

1. Total operation 1.9 2.3

2. Shutdown in stand-by condition .1.4 2.0

3. Total usage.- 3.3 4.3

4. Subtotals a) Full power operation 0.8 0.7 b) Educational usage 2.2 3.0 c) Reactor operator training 1.6 2.6 d) Calibration and maintenance 0.8 0.7 D. Number of 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shif ts 254 267 14 i

IV. COBALT-60 FACILITY The University, in March of 1965, purchased 23,600 curies of Cobalt-60 to provide a pure source of gamma rays. In November of 1971, the University

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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 February 1, 1982 total of 19,000 curies.

In this facility, the sources are stored and used in a pool 16 feet x 10 feet, filled with 16 feet of demineralized water. The water provides a shield which is readily worked through and allows great fle:ibility in using the sot rees. Due tc the number of rods and size of the pool, it is possible to set up several irradiators at a time to vary the size of the sample that can he irradiated, or vary the dose rate. Experiments in a dry environmen assible by use of either a vertical tube or by diving bell type ar;as__as.

Radiation levels up to approximately 7.0 x 108 R/hr are available depending on the number of rods and source geometry used.

The Cobalt-60 facility is designed with a large amount of working space around the pool and has two laboratory rooms equipped with work benches, fume hoods, and usual utilities. Additional facilities include a Hot Laboratory consisting of two identical." Hot Cells." The two feet thick high density concrete walls provide sufficient shielding to allow up to 400 curies of radioactive materials to be safely handled through the use i of remote manipulators. A typical use of the Hot Cells during the past year was the irradiation of rats for biological studies of radiation damage.

Table 4 compares the past two years utilization of the Cobalt-60 facility in terms of time, numbers and daily averagea. There have been no dramatic changes in the facility utilization partly as a result of the relacively low dose rates available. Efforts are under way to obtain more Co-60 in order to increase the dose rates so that high exposures can be made over a shorter, more reasonable length of time.

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I Table 4 Cobalt-60 Utilization Data July 1, 1980 - June.30, 1982 80-81 81-82

- A. Time involved (hours)

1. Set-up time 33 30

2. Total sample hours 13.511 10,900 B. Numbers involved

1. Samples run 499 566

2. Different experimenters- 21 .30

3. Configurations used 3 3 i

C. Per-day averages

1. Experimenters 0.8 0.7

2. Samples 1.9 2.3 l

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V. EDUCATION AND TRAINING The' training and educational ability and adaptability of the Penn State Breazeale Reactor (PSBR) operating staff and the TRIGA Mark III reactor were manifested in the variety of formal laboratory courses, industrial

" training programs, inhouse training, and continuing education functions

, which were provided during this past reporting period.

3 Typical of the, cooperative effort provided by the PSBR operating staff were the guidance and supervision given to the 11 Nuclear Engineering ,

Technology (NET) students as part of their Reactor Technology Laboratory course, NucE 814. Under the surveillance of senior operators, I. B. McMaster, 5- R. E. Totenbier, D. C..Raupach, T. L. 711nchbaugh, and J. L. Penkala, each of the NET students logged in a minimum of 12 safe and informative operating hours at-the controls of the PSBR where they participated in all the routine operations which can be performed with the reactor. The experimentation portion of the NucE 814 course was taught by J. L. Penkala.

Rounding out the offerings of formal courses at the PSBR in the_ NET i

program, W. S. Diethorn, W. A. Jester, and G. L. Catchen joined efforts to teach the Nuclear Technology Laboratory course, Nuc812, in which the reactor was used to generate radioisotopes, and NucE 804 was taught-by J. J. Bonner of the reactor staff who also was appointed to the Nuc E faculty as an affiliate instructor.

The inhouse training this past year consisted of a complete license requalification program that was completed in early 1982 and a reactor operator licensing program. The annual requalification program included oral examinations cnt abnormal and emergency procedures and facility design (walk-around) which were conducted by R. E. Totenbier and I. B. McMaster, respectively. The written portion of the requalification examination was administered bf J. L. Penkala cnd T. L. Flinchbaugh. As in past years, the PSBR operating staff successfully requalified for their NRC operating licenses.-

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The inhouse operator licensing program resulted in D. R. Shaulis and A. R.-Carusone receiving NRC reactor operator's licenses and J. J.

Bonner being upgraded to a Senior Reactor Operator.

The Nuclear Concepts and Energy Resources Institute (NCERI) was

, offered as NucE 497 for the twelfth consecutive year during the Summer of 1981. . The 3CERI, a four week institute, was attended by 45 high school science teachers from nine states, in addition to Pennsylvania. As a result of their four weeks of intensive study, the participating teachers will return to their respective school districts and offer an elective course in Nuclear Concepts.

Drs. W. A. Jester and A. J. Baratra were co-directors of the institute which was sponsored by D.O.E., EG&G Idaho, the Edison Electric Institute, and a number of electric utilities. The major portion of the NCERI laboratory experiments was supervised by J. J. Bonner assisted by C. Yu.

Messrs. D. H.' Hollenbach, E. C. Augustine, and J. L. Penkala also helped in the laboratory exercises.

As .:bs previous institutes, the participants in the NCERI were

. encouraged to return with their high school classes for a one-day field trip to the PSBR. This past year, as a result of previous NCERI's,19 groups totaling 287 students participated in a full day of experimentation, observation, and touring at the PSBR. Mr. J. J. Bonner handled the

scheduling of-and lecturing to the high school tour groups with assistance from D. R.~Shaulis and A. R. Carusone. Table 5 summarizes the participation L of the high school tour program.

The laboratory course NucE 440 was taught in the Fall 1981 and Spring 1982 terms by A. J. Baratta with valuable assistance from W. A. Jester.

Three of the more important experiments were conducted for forty-two students at the PSBR with major assistance from the reactor operating crew.

During the Fall 1981 and Winter 1982 terms, E. S. Kenney taught the.

NucE 441 course with the assistance of the reactor staff. Thirty-five students were registerd for the NucE 441 course.

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Table 5 High School Nuclear Science Program 1981 - 1982 School No.'of Students Instructor Bedford 12 Emery Turner Bellefonte 35 Walter Young Berwick 15 Robert Foster Chestnut Ridge 6 Dave Popp Daniel Boone 31 Larry Tobias Delone Catholic 11 Marie Aimee Harbor Creek 11 John Petersen Horseheads 36 Larry Josbeno Jersey Shore 12 James Allen Marion Center- 16 John Petrosky North Schuylkill 12 Dan Welker Penns Valley 8 John Thompsen Red Land 10 George Farley Ridgeway 18 Ernest Koos State College 8 Maragrete Ciolkosz

-Villa Maria 10 Helen Ackerman Warren 12 Eugene Szul-

West Perry 14 Donald Stoops Wyomissing ~ 10 Charles Bell 19 Groups 287 Participants f

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The TRIGA reactor was used extensively when S..H. Levine taught NucE 502b, a graduate laboratory course, for five graduate students'the past Winter. term.and E. S. Kenney taught 502c for six graduate students in the Spring term.

An elective nuclear engineering course which was designed to give the student an opportunity to correlate classroom theory with actual reactor operation situations controlled by the student was offered a number of times i this past year. The NucE 444 course, Nuclear Reactor Operations Laboratory, was effered during Summer 1981,' Fall 1981, Winter 1982 and Spring 1982 terms for 28 students by J. L. Penkala. Each student performed a minimum of ten j

-reactor startups while logging approximately 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> of operating experience at the PSBR control console.

Three industrial training programs were provided for 15 reactor operator license candidates of the Cincinnati Gas and Electric Company. The senior reactor operating staff participated in these industrial training programs.

A fourth industrial training program was offered for 36 operations personnel from GPU Nuclear's Three Mile Island Unit-2. The GPU program was l conducted daring a six-week period with S. H. Levine, F. G. Helfferich, and G. B. Gockley providing the lecture sessions while G. L. Catchen and D. C. Raupach instructed the laboratory sessions.

The entire senior operating staff provided the start-up experience and the program was coordinated by J. L. Penkala.

-The PSBR and its operating staff continued to serve the nuclear engineering department in addition to other university departments and l colleges in the following manner:

i i A small group of W. W. Pratt's Physics 496 and 559 students utilized the PSBR for their respective projects this past year.

A group of 19 of G. E. Robinson's NucE 401 students were given a tour of the PSBR and a start-up and pulse demonstration.

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An' introductory course in Nuclear Engineering, NucE 200 was offered by J. L. Penkala to 42 sophomo,e students during the Winter 1982 term.

This course used the PSBR facilities for two experiments. Assistance was given by J. J. Bonner in the lab.

Approximately 30 University Police Services personnel were given training /retra ining sessions by J. J. Bonner at the PSBR to ensure familiarity with the facit les. Com ined with this training was an orientation lecture by the Health ." ysics staff.

When the electronic experiuentation equipment and the console instrumentation are always in operable condition, it is too easy to forget that it is D. S. Vonada who maintains the hardware and makes the hundreds of student instruction hours at the PSBR possible.

With well over 150 man years of safe, reliable reactor operating experience, the staff of the PSBR is obviously fulfilling its obligation to "the general public" to disseminate information concerning the pros and cons the do's and don'ts, the how's and how not's of reactor operations, irradiation services, and understanding of nuclear energy in general and nuclear applications in particular through the spectrum of educational and training vehicles described in this report.

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VI. RADIONUCLEAR APPLICATIONS LABORATORY The staff of the Radionuclear Applications Laboratory during this year consisted of W. A. Jester, G. L. Catchen, D. C. Raupach, and B. C. Ford.

Gary L. Catchen joined the Nuclear Engineering faculty in February 1982, as an Assistant Professor, to fill the position vacated by K. K. S. Pillay.

Several of Dr. Jester's graduate students assisted in conducting one or more of the projects associated with the laboratory. The purpose of the laboratory is to provide consulting and technical assistance to University research personnel who wish to utilize some type of radionuclear technique in their work.- While the bulk of these projects involves some type of i neutron activation analysis procedure, the staff is prepared to provide services-in such areas as nuclear medicine, radioact ve tracer techniques, radiation gauging and radiation processing; in fact, they have provided services in these and other fields in the past.

Utilization of the laboratory has increased during the past year. In part, this increase in utilization can be attributed to the ease of use of the new multichannel analyzer and the use of the automatic sample changer which was developed and constructed by members of the reactor staff during the past year. The automatic sample changer, in conjunction with the multichannel analyzer-computer system, can be loaded with up to 100 samples which can be analyzed over night or over a weekend, without the experimenter having to be present. The new analyzer processes the data and prints out the results while the next sample is being analyzed. Prior to getting the new analyzer, the results would not be available until the day after the last sample was analyzed.

In addition to the analyzer and the automatic sample changer, a new 20% efficient High Purity Germanium Coaxial Detector and shield have been added to the laboratory. The new detector is at lecst twice as efficient as any of the other detectors in the laboratory. This detector is being used primarily for_ counting environmental samples or other samples which I

contain very small amounts of radioactivity.

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During the last year, members of the radionuclear applications group have developed a technique for producing iodine-131 from NH 4Te. The iodine-131 is separated from the irradiated armonium tellurate (in an aqueous form) and counted on one of the Ge(Li) detector systems. Quantification of the amount of iodine-131 produced is thereby possible because the detectors are calibrated using volumetric standards purchased from the National Bureau of Standards. Once the solution is quantified for iodine-131 concentration, samples of any size or shape can be oroduced. This is of significant importance because secondary standards can be made up to simulate different sample geometries. For example: air filters, activated charcoal filters, and liter volumetrics can be produced to simulate actual samples being analyzed for iodine-131.

A new set of calibration standards (one point source and one volumetric source) have been procurred from the hotional Bureau of Standards and a recalibration of all the detectors in the laboratory will be undertaken in the near future.

During this year, work has continued in the development of the capabilities of the Low-Level Radiation Monitoring Laboratory (LLRML) . This Lab has been set up in rooms 103 and 116 of the Academic Projects Building which is located just east of the Breazeale Nuclear Reactor. The staff of this facility includes Dr. W. A. Jester, B. C. Ford and D. C. Raupach.

During the Spring term, Dr. G. L. Catchen joined this group.

Some of the activities and accomplishments of the year are as follows:

In June 1981 there was a visit by an EPA inspection team which has led to the labs Interim Certification (July 1982) for monitoring radio-o activity in water as required by the National Safe Drinking Water Act.

This certification includes gross alpha and beta analysis of evaporated water residues, tritium in water analysis, and gamma-ray spectroscopy of water.

Work has progressed during the year in the analysis of strontium-89 and strontium-90 in drinking water.

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i One of the most notable events of the year was the awarding of a radiation monitoring contract to the Laboratory by Pennsylvania Power &

Light Company. Under this contract, the lab will monitor radioactivity in samples collected from the environment in and around PP&L's Susquehanna plant.

Environmental radiation levels will also be measured using TLD dosimeters.

As part of this program an extensive procedures and quality assurance manual has been written.

In addition to University researchers, the laboratory has continued to perform analyses # c governmental agencies and for industry. During the past year, analyses have been performed for the Pennsylvania Department of Environmental Resources, Raytheon Company, Draper Laboratory, Kennedy Van Saun, Pennsylvania Power & Light, Gulf 011 Company, and others.

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VII. FACILITY RESEARCH UTILIZATION Research continues to utilize the major portion of the available operation tims of the reactor and the Cobalt-60 Facility. A wide variety of research projec's are currently in progress as indicated on the following pages. For convenience, the University oriented research projects are arranged alphabetically by authors under the various departments. Theses, publications and papers follow the'research descriptions to which they pertain. In addition, a section is provided with examples of industrial research utilizing the facility.

The facility continues to serve as a resear>:k tool available to all faculty, staft and graduate students of the various departments and colleges within the university. Thirty-nine faculty and steff members and twenty-one graduate students have used the facility in the past year for research.

This represents a usage by eleven different departments or sections in six colleges of the University. Names of the individual users are arranged alphabetically under their departmental and college affiliations in Appendix A.

' te following list of current research projects indicates the broad utilization enjoyed by the Breazeale Reactor Facility. The nineteen projects described involve three master's theses, one doctoral thesis, four publications and one paper. The examples cited are not to be construed as publications or announcements of research. The publication of research utilizing the facility is the prerogative of the researcher.

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. 3 A. UNIVERSITY RESEARCH UTILIZING THE FACILITIES OF THE PENN STATE BREAZEALE NUCLEAR REACTOR Agricultural E'ngineering Department Tracer Bteakt}vtough Cwtve Studies The Effects of Soit Nonhomogeneitia A. Jarrett W. A. Jester D. A. Lehman The reactor was used to irradiate samples of NH 4Br. This produced the radioisotope bromine-82. The bromine is being used as a tracer to study solute flow through a soil column. The hypothesis of this experiment is that the results of a tracer test (a breakthrough curve) can be used to identify the nonhomogeneities present in a soil system. This will be done quantitatively by relating the effects of dispersion coefficients to certain nonhomogeneities.

Anthropology Department Sowtce Analysis of Jasper, a Preh.ist.or.ic Raw Material J. W. Hatch P. E. Miller The goal of archaeology is the understanding of past human behaviors through the analysis of the material remains of prehistoric activities.

One means of deriving behavioral data from such remains is by determining the geographic source of raw materials used by particular groups of individuals. The presence at an archaeological site of materials from distant sources is indicative of exchange or trade relationships between groups. The directionality and importance of such relationships can vary through time. Materials which have been analyzed for source data include ceramics, copper and obsidian.

A specific problem in Northeastern U.S. archaeology is the apparent widespread occurrence of Pennsylvania Jasper, a crypto-crystalline quartz of high quality used throughout prehistory for stone tool manufacture.

The assignment of this jasper to a Pennsylvania source has been made on the strength of macroscopic appearance, despite the existence of other desposits of similar jaspers in the Eastern U.S. In order to cest hypotheses regarding trade relationships, it is necessary to assign Jasper artifacts to a source using an accurate and replicable technique. Studies of other geological materials suggest that chemical analysis is a successful approach to sourcing problems. Neutron activation analysis was selected over techniques such as atomic absorption and emission spectroscopy because of its high sensitivity and because a number of elements corld be analyzed simultaneously. Material from eight geological sources are being studied; 28

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discriminant analysis will be applied to the resulting data in order to At present, 130 provide a means of assigning future unknowns to a source.

of approximately 160 samples have been irradiated for one hour at 950 kilowatts. The samples have been analyzed for short half-lived elements af ter approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and for longer half-lived elements af ter approximately seven days. The automatic sample changer is now being used for the latter analysis. Projected coupletion data of the research is July 15.

Biology Department Sodium Loss in Amphibian Lannae Exposed to Low pH W. A. Dunson J. Freda Ambystomatid and ranid larvae placed in sulfuric acid solutions, at pH's between 3.0 and 4.0,'were unable to regulate their body sodium content.

Body sodium influx ceased and sodium efflux increased markedly. This resulted in a 50% or greater drop in body sodium. content / gram dry mass, at the time of death. The rate of net sodium loss was inversely related to su.vival time. A 20 foJd increase in water calcium concentration significantly slowed the rates of sodium loss, and increased survival times. This specific inhibitory ef fect of low pH on amphibian body sodium regulation is quite similar to that previously reported for fish. Thus a major cause of death in aquatic amphibians living in situations polluted by acid rain or acid mine wastes is depletion of body sodium.

Publication

" Specific Inhibition of Hatching in Amphibian Embryos by Low pH."

W. A. Dunson and J. Connell, Journal of Herpetology: in press, 1982.

Biology Department Asjmmettical Diffusion of Sodium and Waten. Tivtough the Skin of Sea Snakes W. A. Dunson G. D. Stokes Diffusion of water, Na, Cl, and ethanol were studied jb1 vitro across whole, fresh skins of six species of sea snakes placed between 1 M solute 2 solutions and distilled water. Water influxes varied from 60 pmoles/cm -h 2

in Pelamis to 240 pmoles/cm -h in Aipysurus laevis. In four species, including Pelamis cnd Aipysurus, influx exceeded efflux. This is a reversal of flux asymmetry as found in fresh-water snakes, measured under identical circumstances.

Na and Cl fluxes across whole skins were low, with effluxes exceeding influxes in A. laevis. In shed skins of A. laevis, Na fluxes were considerably higher than in whole skins, but the same asymmetry in direction of movement was observed, efflux exceeding influx by a factor of 2-16. This 29

_. - z-1 represents a reversal of the ion flux asymmetry seen in fresh-water snakes.

The directions of asymmetrical diffusion of water and Na are appropriate for regulating these materials in the respective marine or fresh-water environments. A model for snake skin is proposed in which observed asymmetries in fluxes are accounted for by the presence of lipid-lined channels of two sizes which change in diameter depending on different water and ion concentrations of the bathing fluids on the two sides.

Publication

" Asymmetrical Diffusion of Sodium and Water. Through the Skin of Sea Snakes," W. A. Dunson and G. D. Stokes, Physiol. Zool., In press.

Biology Department Passage of Water and Electtotytes Through Natwutt and Artificial Keatin Menbranes W. A. Dunson G. D. Stokes The feasibility of reconstituting dissolved a-keratin was tested by rekeratinizing bovine hoof into sheets through electrodialysis. At voltage densities of 10, 15, and 25 V/cm we were successful in forming thin, fragile membranes on the surface of a dialysis membrane. Mean Na diffusion rates across these membranes between 0 and 1M Nacl at atmospheric pressure were 121-291 umole/cm2-h. The rate dropped to 3 pmole/cm2-h.

after topical addition of linoleic acid to the membrane. Permeability characteristics of shed snake skin (Constrictor constrictor, Nerodia cyclopion floridana), sea turtle scutes (Chelonia mydas, Caretta caretta),

bovine hoof slices, and tarpon z scales (Megalops atlantica) were tested at pressures up to 300 lb/in and compared to the commercial reverse osmosis g membrane, SEPA 97. The first three membranes are composed of keratin and the latter two of collagen and cellulose, respectively. Shed snake skin and fish scale allowed passage of fluid with no salt rejection. Turtle scutes and thin (60pm) sheets of bovine hoof gassed no fluid or salt.

SEPA 97 had a mean fluid passage of 180 pl/cm -h with 16% salt rejection, both lower than expected. Reconstituted a-keratin has the potential for use in membrane separation of water and solutes. However, further work is needed in developing techniques for fabrication of thicker sheets (between 15 and 50 pm), which are likely to show the desired characteristic under pressure of passage of water but not solutes.

Publication

" Passage of Water and Electrolytes Through Natural and Artificial Keratin Membranes ," G. D. St( kes and W. A. Dunson. Submitted.

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Biology Department Pettmeability and Citannel StAuc.twte of Reptilian Skin W. A. Dunson G. D. Stokes A study of the permeability of shed epidermis from some terrestrial and fresh-water snakes was conducted. Permeability to Br, Na, and K ions was very low and showed a higher influx than efflux in most cases.

Permeability to the smaller water molecule was much greater, and in contrast efflux was higher than influx. Skins from aquatic snakes with larger water permeabilities also showed greater permeabilities to Na and K. The highly aquatic Regina opetemvittAta has the most permeable skin of any snake. Ethanol fluxes were higher than expected for a tracer of its size, perhaps due to its solubility in lipid. Na fluxes through whole live skins of NatAix cjclopion floridana in vitro were not significantly different from those of the shed skin alone. Isolated hinge regions snowed complete water impermeability, suggesting that channels through the skin are located only in the scale region. Dermal water efflux into dry air was considerably less than water-to-water efflux.

Lipid extraction increased permeability markedly and eliminated the asymmetry of water and ion fluxes. Lipid replacement with linoleicProtein acid restored half of the water impermeability lost during extraction.

extraction did not significantly increase membrane permeability but did eliminate the permeability difference between dry and hydrated skins.

Two sizes of lipid-lined channels extending through a protein matrix are suggested as a possible model for snake skin. The diameter of the channels apparently varies in relation to the differing uater, Na, and C1 concentrations on opposite sides of the skin, but the mechanism of this adjustment is unknown.

Doctoral Thesis

" Permeability Characteristics and Possible Pore Structure of Reptilian and Artificial Keratin Membranes, G. D. Stokes (Zoology Department),

1981, W. A. Dunson, Advisor.

Publication

" Permeability and Channel Structure of Reptilian Skin," G. D. Stokes and W. A. Dunson, Amer. J. Physiol., 1982, in press.

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Chemistry Department The Design of Atanically Defined Catalys.ts P. Skell S. Niznik J. Schwartz J. Kennan J. Ross New types of heterogeneous catalysts are being made by adsorbing organo-metallic complexes on supports and then removing the organic liquids. These are novel, and possibly important new catalyst systems.

The metals that are currently being used in this study are iridium, palladium, platinum, and rhodium. In order to obtain accurate rate information we must know exactly how much metal is contained in our catalysts. It is for this reason that we have chosen neutron activation analysis for an accurate quantitative determination of metal content in our catalysts.

Dairy and Animal Science Department Deteenination of Particula.te Digesta Flow in Runinant Animals witJ1 Rare Eart]t EE.ements by Neutron Activation L. P. Muller G. A. Rogers T. J. Snyder G. Okwaro The use of rare earth elements as digesta markers attached to feed-stuffs has been receiving attention as a means of estimating feedstuff retention time and rate of passage in the digestive tract of ruminants.

Rare-earths are desirable as ingesta markers because they are not absorbed from the gastrointestinal tract and possess strong binding properties for particulate matter. The required analytical sensitivity for measuring these rare-earths is available through neutron activation analysis.

We have used La, Sm, Ce, Yb, and Co-EDTA as markers of fibrous, grain, and liquid fractions in three different trials. These markers are attached to the feedstuffs and placed into the digestive tract. Subsequent fecal samples are then analyzed at the Breazeale Nuclear Reactor. From these data, the estimated time of feedstuff retention in various segments of the gastrointestinal tract can be calculated. The Neutron Activation Analyalis allows us to obtain various measurements in large ruminant animals using nonradioactive elements, and has the advantages of sensitivity, ease of sample preparation, and simultaneous analysis of several rare-earth markers.

The use of these mhniques and the data obtained from these studies will provide us with a better understanding of the digestive processes in l

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ruminants. Ultiantely,.we can then modify the digestion and nutrient utilization to improve animal performance and productivity.

1 Analyses is completed from one of the studies in progress from two

~ other studies. Samples are currently being collected from two other studies.

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Effects of 0 and 1.2% NaHCO3 with Two Corn Silage: grain Ratios on Milk Production and Digestive Responses of Lactating Cows," T. J. Snyder, L. D. Huller, J. A. Rogers, and S. M. Abrams. Abstract of paper presented at American Dairy Science Assoc. Annual Meeting, 1982.

Entomology Department Determination of Etementai Composition of Semge Studge R. O. Mumma D. C. Raupach

.D. Lisk-

, J. Waldman Sewage sludge samples from many major cities across the United States were neutron activated for the purpose of determining the' elemental composition of the samples. These ~ data will be correlated with elemental

- composition data derived from alternate analytical methods. Also, these sludge samples will be analyzed for various toxic organic chemicals such as PCB's, PBB's and other mutagens.

a Geochemistry Department Modets of Formation for Cu-U Ocewvtences in tJte Uppen. Devonian Catskitt Forma. tion of PA A. W. Rose L. M..Cathles H. Ohmoto A. T. Smith One hypothesis for this phase of the study is that U-rich intervals in stratigraphic sections indicate favorable areas for U or Cu-U mineral-ization in the red-beds of the Upper Devonian Catskill Formation. It is.

Lthought that U-ions adsorbed on clays are a possible source for the uranium found in the many known localities in PA. The clays were formed during the erosion ~of a U-rich source, possibly a granite. They were transported into the Appalachian basin and were deposited.'in thick sequences of muds, which '

became shales upon lithification. In an oxidizing environment, the uranium was leached from the clays during early compaction. The U was concentrated in organic-rich zones in nearby sandstones.

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Approximately 100 shale samples (10 gr. each) from one stratigraphic section several kilometers from known U occurrences have been analyzed for U by Delayed Neutron Activation Analsysis (1 megawatt, 60 sec.

irradiation. 5 sec. delay, 60 sec. count).

A U-rich interval has been found, and the project is considered a success. Future plans include the analysis of the same samples for Th and possibly more U and Th analyses of shales from other stratigraphic sections.

Materials Science Department The Effects of Co-60 Gamma Radiation on ne Sttength Distributions of Simple Sorosilicate Glasses and Complex Naelear Waste Borosilicate Glasses R. C. Bradt P. Miriello The Co-60 facility at the reactor is being used to study the effects of gamma radiation on glasses of simple composition: window, pyrex, and a lead borocilicate; and more complex composition: Savannah River nuclear waste glass (defense type) and Pacific Northwest Labs nuclear waste glass (reprocessing type).

Primarily, the efteits of the radiation on the strength and density are being investigated. Three of the five compositions to date have been irradiated. The Savannah River glass is being prepared for irradiation this summer.

Nuclear Engineering Department Non-invasive Liquid Levet Density Gauge for Nuclear Power Reactors A. J. Baratta W. A. Jester E. S. Kenney A. H. Foderaro G. Imel I. B. McMaster E. W. Okyere J. W. Park The source range detectors of TMI-2 displayed anomolous behavior during the course of the accident. The behavior indicated a possible relation between the detector output and the density and level of coolant in the reactor. Using the data obtained from TMI-2, a concept for a non-invasive liquid level gauge has been developed.

It is the objective of the present experiments to simulate conditions in a partially voided reactor using the FSBR. The effort is intended to 34

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reproduce the outputs observed on the source range detectors during the TMI-2 accident and from that data predict the coolant level.

Experiments to date, using the Penn State Breazeale Reactor, have verified thsc the neutron level external to the pressure vessel is sensitive to water level variations in the reactor. Current efforts are directed towards verification of the predicted behavior, determination of system spatial resolution, optimization of detector packaging and computer simulation of experiments.

Nuclear Engineering Department The Development of a Monitoring Syst.em Capable of Det.ecting Low Levels of Radioactive lodine in .the Presence of High Levels of Radioactive Noble Gases W. A. Jester A. J. Baratta T. T. Tseng The monitoring system is used to detect the exact amount of radioiodine in the presence of high radioactivity of noble gases. Current commercial standard type iodine monitors cannot quantify the amount of iodine under such conditions. The simulated radioactive noble gas is achieved by irradiating a stream of air to produce argone-41. The radioiodine (iodine-128) is made by activating NHgI in the Rabbit I System of the Breazeale Nuclear Reactor. -This radioiodine is introduced into the air stream under controlled conditions.

The proof-of-principal has been completed and work is beginning on a system which will be installed in a nuclear power plant.

Masters Paper ,

" Concept Evaluation of a Radioiodine Monitor Which Can Operate in High Level of Radioactive Noble Gases," Tseng, Tung-Tse,120 pages, June 1982.

Masters Thesis "The Prototype of Iodine Monitoring System," Tseng, Tung-Tse, 1982,

! W. A. Jester, Advisor.

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Nuclear Engineering Department .

Nuclean. Data-680 Activation Analysis Package Evaluation W. A. Jester K. K. Wu The goal of this p oject is to evaluate the accuracy of the ND-680 multichannel analyzer combined with a minicomputer. In this system, a LSI-ll microprocessor utilizes the neutron activation analysis software package to analyze the gamma ray spectra of different unknown samples, to find out their elemental concentrations. The apparatus that will be or has been used so far are: The ND-680 systems, the Ge(Li) gamma-ray detector and the Nu:: lear Reactor for irradiation of unknown samples.

Currently, the student has finished the task of learning to use the ND-680 system and is beginning to test the parameters set up for the neutron activatio.t analysis package. In the future, the student expects to create programs that can be connected to the neutron activation analysis package programs to improve the utilization and efficiency of the -

ND-680 system for this center.

Masters Thesis j

" Nuclear Data-680 Neutron Activation Analysis Package Evaluation,"

K. K. Wu, 1981, Nuclear Engineering, W. A. Jester, advisor.

Nuclear Engineering Department -<

Optbnum Hyd,togeologic Paramet.eAs P,tediction by tJte Tracer Steakthtougit Cu,tve Metitod W. A. Jester A. R. Jarrett C. Yu This research work uses the tracer breakthrough curve to estimate the hydrogeologic parameters such as diffusion coefficients, distribution coefficients, average velocities and effective path lengths, etc. From these parameters, we are also able to tell the nonhomogeneity of the geologic media.

By the method of least square approximation, the tracer breakthrough data are fitted by a uniform flow equation; the optimum effective hydro-geologic parameters are then obtained.

By the method of least square approximation, the tracer breakthrough data are fitted by a uniform flow equation; the optimum effective hydrogeologic parameters are then obtained.

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With a saturated column, different soils and traces can be used to estimate the hydrogeologic parameters including distribution coefficients of different nuclides in different soil media.

The reactor is being used to produce bromine-82 which is used as a water tracer to produce breakthrough curves in a soil column.

Nuclear Engineering Department Beta Dosimetty S. H. Levine D. Chang Two separate tasks are being conducted in parallel for this contract.

Beta dosimetry studies are being conducted in performance of one of these tasks and the other involves measurements of the neutron flux and its energy spectrum. A laboratory has been established in the facility for performing accurate beta dosimetry measurements.

Initial measurements have been performed with a newly constructed Lucite Beta Irradiation Platform (LBIP) using 0.011 curie strontium-90-yttrium-90 beta source.

T'nese measurements showed that the thermal luminescence detector Studies response can be more than a factor of 4 off if not properly calibrated.Only are to continue to develop accurate beta dose measurements.

analytical studies have been performed on the neutron spectrum determination. Future work vill involve neutron measurement in the facility.

Nuclear Engineering Department Dissolution of Cqstalline Waste Phases K. K. S. Pillay M. Y. Khalil The effect of amorphism on dissolution of waste phases is being examined. Some crystalline phases are doped with U-235 and irradiated to cause fission fragment damage which renders the phases amorphous.

After the radioactivity is reduced to . reasonable level, the dissolution processes will start.

The dissolution of technetium containing phases is also being examined.

The phases containing technetium are to be formed in aThe reducing liquid atmosphere.

A glovebox is being used for the reduction process.

B-scintillator will be used to detect the presence of technetium in the dissolving solution.

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Nuclear Engineering Department Radiation Damage 1.n Nuclear Waste Forms K. K. S. Pillay l M. Y. Khalil i

The effect of long term a-decay in crystalline radioactive waste forms ,

is being experimentally investigated. To simulate the a-decay damage, l

-some candidate phases were doped with Li-6 and irradiated in the reactor to produce lithium-6 hydrogen-3 reaction.

Physics Department Trace Element Analy446 of Coat W. W. Pratt The neutron activation analysis study of trace element impurities in coal, described in the previous annual report, is being continued.

Quantitative measurements have been made for arsenic, cobalt, iron, scandium, selenium, and uranium., Additional quantitative measurements have been started for other trace elements.

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B. INDUSTRIAL RESEARCH UTILIZING THE FACILITIES OF THE PENN STATE I BREAZEALE NUCLEAR REACTOR The facilities of the Penn State Breazeale Reactor (PSBR) are made available to state, federal, and industrial organizations for use in h; their research and development programs. Some typical examples follow:

The Charles Stark Draper Laboratory, Iac.

I R. B. Miller In the past year the Draper Laboratory has used the Breazeale Nuclear Reactor Facility to investigate the effects of neutron I environments on the functional and parametric characteristics of integrated circuits. Results of our experiments have yielded informa' tion which is useful in understanding neutron sensitive damage mechanisms in semiconductors. In addition, our research has allowed i us to develop damage coefficients necessary for predicting circuit response to neutron environments.

Gulf Research & Development Company E. G. Miller Research is continuing at Gulf in the area of shale oil as an alternative to crude oil. The primary element of interest is arsenic, although periodic checks are made for cobalt, tungsten, and bromine.

The responsibility of the Neutron Activation Group is to analyze for multiple elements through rapid computer analysis of Ge(Li) spectrums. At present, we are attempting to transfer the Ge(L1) spectrums into a small Digital Minicomputer ("MINC? LSI-ll) for peak search, identification and quantification. Data communication from the minicomputer to an AMDAhl ICF is also being pursued.

4 Raytheon Company R. N. Diette The irradiations performed by the reactor facility staff have been utilized in assessing damage to electronic corponents. Electrical test, pre- and post-neutron exposure, identify functional and parametric changes used for analysis of the nuclear vulnerability of diverse electronic circuits and systems. This analytical approach is applied to land and sea based radar, communications and missile systems.

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T. K. Kim The tieutron activation analysis capabilities of the Penn State Breazeale Reactor were utilized to determine the amounts of thorium, uranium, and other radioactive elements present in tungsten ore and tungsten ore sludge samples. These data will be utilized in developing a new tungsten chemical system and other tungsten processes.

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l APPENDIX A Faculty, staff, and students utilizing the facilities of the Penn State Breazeale Reactor.

COLLEGE OF AGRICULTURE Dairy & Animal Science Abrams, Stephen M.

USDA Pasture Research Laboratory Muller, Lawrence D., PhD Professor of Dairy Science Okvaro, Gilbert, MS Graduate Student Rogers, John A., PhD Research Associate Snyder, Timothy J., MS Research Assistant Entomology Mumma, Ralph O., PhD Professor of Chemical Pesticides Lisk, Donald, PhD Professor of Vegetable Crops Cornell Universicy COLLEGE OF EARTH AND MINERAL SCIENCES Geosciences Cathles, L. M., PhD Professor of Geochemistry Lustverk, Rigel L., BS Graduate Student Ohmoto, H., PhD Professor of Geochemistry 41

. Rose, Arthur U.,'PhD Professor of Geochemistry

-Smith,' Arthur T., MS Graduate Student-Materials Science-Bradt, Richard C., PhD Professor of Material Science Miriello,. Patricia S., BS Craduate Student COLLEGE OF ENGINEERING Agricultural Engineering Jarrett, Albert R., PhD Associate Professor of Agricultural Engineering Lehman, Dale A., BS Graduate Assistant Civil Engineering Nesbitt, John B., ScD Professor of Civil Engineering Nuclear Engineering Baratta, Anthony J., PhD Assistant Professor of Nuclear Engineering Bonner, Joseph J., MS Auxiliary Operations Specialist Catchen, Gary L.', PhD Assistant Professor Chang, Daren, BS Graduate Student Diethorn, Ward A., PhD Professor of Nuclear Engineering i Flinchbaugh, Terry L.

Nuclear. Education Specialist 1

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Foderaro, Anthony B., PhD Professor of Nuclear Engineering Ford, Bonnie C.

Project Assistant Imel, George, PhD Assistant Professor of Nuclear Engineering Jester, William A., PhD Associate Professor of Nuclear Engineering Kenney, Edward S., PhD Professor of Nuclear Engineering Khalil, M. Y., BS Graduate Assistant Levine, Samuel H., PhD Professor of Nuclear Engineering McKee, John R., BS Coordinator, Energy Education Programs McMaster, Ira B., BS Research Assistant Okyere, E. W., MS Graduate Assistant Park, Jaewoo W., BS Graduate Student Penkala, John L., S Research Assistant Pillay, K. K. Sivasankara, PhD Adjunct Professor of Nuclear Engineering Raupach, Dale C., BS Reactor Utilization Specialist Robinson, Gordon E., PhD Associate Professor of Nuclear Engineering Rudy, Kenneth E.

Senior Engineering Aide Shillenn, James K.

Energy Education Specialist 1

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t Totenbier, Robert E., BS

~Research Assistant Tsengi Tung-Tse, BS Graduate Student Waldman, Joseph ~ l Undergraduate Student

'Witzig, Warren F., PhD Professor of Nuclear Engineering Wu, Kwok Kwan, BS Graduate Student Yu, Charlie, MS Graduate Student '

COLLEGE OF THE LIBERAL ARTS Anthropology 1 Hatch, James W., PhD Assistant Professor of Anthropology Miller, Patricia E., BA Graduate Student COLLEGE OF-SCIENCE Biology Connell, Joseph P.

Undergraduate Student

. Dunson, William A., PhD Professor of Biology Freda, Joseph, BS Graduate Student Stokes, Glenn, MS Graduate Student Chemistry Kennan, John, BS Graduate Student 44

Niznik, Shelly, BS Graduate Student-Ross, Jeffery, BS Graduate Student-

, Schwarts, Jo-Ann, BS Graduate Student Skell, P. S., PhD Professor of Chemistry Physics Pilione, Lawrence J., PhD Associate Professor of Physics - Altoona Pratt, William W., PhD Professor of Physics INTERCOLLEGE RESEARCH PROGRAMS AND FACILITIES Health Physics Office-Granlund, Rodger W.,

^

BS

-University Health Physicist Hollenbach, Donald H.

Health Physics Assistant B

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APPENDIX-B FORMAL GROUP TOURS 1981 Participants.

July 6 Alumni Vacation College 23 7 Alumni-Vacation College 32 15 Energy: for the '80s (s)' 31 17 Youth Conservation Corps. 20 20 Harrisburg Hospital Technicians 20 l

22 Alumni Vacation College 27 23 Forest Chapel Senior High 30 29 Nuclear Concepts' Families 4 30 Upward Bound 7

[-

I Aug. 3 Waterworks Operators Association of PA (4)' 54 5- Intensive English Communications 13 i 11 Youth Conservation Corps 10 11_ Student Group ,

5 Sept. 1 Student Orientation 3 21 2 Student Orientation Student Orientation 18

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, 4 Student Orientation 19 5 Upciose 13 l

. 17 Pennsylvania Office Managers Association of United Electric Corporations 18 25 Science Technology & Society 14 Oct. 12 Food Science 521 8 16 Nuclear Engineering 401 14 20 Life Science Interest House 11 l

21 Girl Scouts 12 22_ Geological Sciences 303 15 27 Physics 100 (2) 49 i

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t Formal Group Tours (continued) i '1981 Participants  ;

Nov. 3 American Society of Mechanical Engineers 9 5 Engineering Graphics 50 32- ,

'6 Students from Altoona Campus 4 7 Union H S h., 11  !

10 State College Area Junior H S 6 11 Altoona NET Students 6 19 Pennsylvania Power & Light Company. 16-Dec.. 2 Nittany Dorm Students 8 i 3 Slippery Rcek State College 9 4 Dickenson College 11

'8 Bucknell~ University 12 15 Chestnut Ridge-H S 10.

15 Police Services. Orientation 7 15 State College Area Junior H S 21 17 Police Services Orientation-(2) 18 .

18 Police Services Orientation 6 1982 ,

I Jan. 6 Engineering Graphics 50 21 7 Police Services Orientation 5 8 Police Services Orientation- 4 12 Higher Education 101 10

'14~ Police Services Orientation 4 14 Arts and Architecture Interest House 3 19 Entomology 416 25 21 Nuclear Engineering Students 3 27 Jersey Shore H S 15 28 Human Development 4 48 t._

Formal Group Tours (continued) 1982 Participants _

.Feb. 4 Geological Sciences 303 27 9 Higher Education 101 12

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10 Future Farmers of America (2) 21

'LL Engineering and Applied Science Interest House 9 16 Plant Breeding 407 (2) 50 17.. Plant Breeding 407 6 18; Plant Breeding 407 14 19 Chemical Engineering 430 33

-Mar. 10 Student Group 4 12 Penn Cambria H S 21 17 Bedford H S- 18 18 Wyomissing H S 10 19 Coop Undergrad Education Program 16 19 Boy Scouts 25 20 Lion Ambassadors 20

, 20 Society of Women Engineers (2) 19 22 Bellefonte Scout Troup 20.

24 Bellefonte H S 27 26 Upper Saint clair H S 24 26 Ridgeway H S 13

-29 Villa Maria Academy 9 30 Society.of Physics Students - Dickenson College 12

'31 Delone Catholic H S 11 Apr. 1 Penns Valley H S 13 2 Berwick H S 11 2 Journalists 7 6- Red Land H S 10 7 Pennsylvania Rural Electric Association 8 15 Selinsgrove H S (2) 50 16 Pittsburgh Explorer Post 27 49

Formal Group Tours (continued) 1982' - Participants l

'Apr. 20 Engineering Graphics 50 73 1

20 State College H S (2) 43 l 21 West Perry H S 10 22 Society of Physics Students 3 22 PP&L Energy Educators 7 23 Horseheads H S 30 26 Physics 101 12 27 Physics 101 (2) 35 27 Selinsgrove H S (2) 45 28 Warren Area H S 34 29 Professor Fitz & Guests 7 29 North Schuylkill H S 16 29 Phi Tau Sigma - Mechanical Engineers 11 30 Punxsutawney Area H S 22 30 Chestnut-Ridge H S 9 May 5 Daniel Boone H S 27 6 Harbor Creek H S 13 6 PEA Relay Committee 10 6 Park Forest J H S 6 7 Marion Center H S 10

-7 Maple Avenue Middle School 25 11 Harrisburg Hospital 16 11 Geological Sciences 303 20 13 Metallurgy 412 4 14 Altoona 8th Graders (2) 60 14 South Park H S 14 17 Mifflinburg Area H S 29 18 Geological Sciences 303 22 19 Dickenson College 4 19 ' Altoona Campus (2) 50 i

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Formal Group Tours (continued) 1982 Participants June 1 ~ Inter American Executive Management Group 25 3 Visiting Mechanical-Engineering Students from i Iceland 12 P

3 State College High School - Chem. II 13 10 Elderhostel '82 10 15 Student Orientation 9 17 Student Orientation 22 22 Pennsylvania Vocational Conference 6 22 4-H Congress 26 23 4-H Congress 15 24 Students 2 137 Groups 2,125 Visitors l

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