ML20028B822

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Annual Progress Rept of Univ of Fl Training Reactor, Sept 1981-Aug 1982
ML20028B822
Person / Time
Site: 05000083
Issue date: 11/30/1982
From: Diaz N, Vernetson W
FLORIDA, UNIV. OF, GAINESVILLE, FL
To:
Shared Package
ML20028B818 List:
References
ORO-4014-12, NUDOCS 8212070009
Download: ML20028B822 (26)
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ANNUAL PROGRESS REPORT

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OF THE E

UNIVERSITY OF FLORIDA TRAINING REACTOR F

SEPTEMBER 1, 1981 - AUGUST 31, 1982 u

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NUCLEAR FACILITIES DIVISION

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DEPARTMENT OF NUCLEAR ENGINEERING SCIENCES College of Engineering

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H University of Florida L-Gainesville hbR DO O 83 l R PDR

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Contrac't # DE-ACO5-76ERO4014 Report # ORO--4014-12 ANNUAL PROGRESS REPORT OF THE UNIVERSITY OF FLORIDA TRAINING REACTOR September 1, 1981 - August 31, 1982

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Submitted to the

[ Department of Energy Nuclear Regulatory Commission

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and b University of Florida E

By Dr. Nils J. Diaz Professor and Director of Nuclear Facilities and

{ Dr. William G. Vernetson .

Peactor Manager Department of Nuclear Engineering Sciences College of Engineering University of Florida Gainesville, Florida November, 1982 k m Al i ud

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l TABLE OF CONTENTS Pagi Number l

I I. INTRODUCTION 1 II. UNIVERSITY OF FLORIDA PERSONNEL ASSOCIATED WITI!

THE REACTOR 3 M III. FACILITY OPERATION 5 I IV. MODIFICATIONS TO THE OPERATING CHARACTERISTICS OR CAPABILITIES OF THE UPTR 12 V. SIGNIFICANT MAINTENANCE AND TESTS OF UFTR REACTOR SYSTEMS 13 VI. CilANGES TO TECHNICAL SPECIFICATIONS AND STANDARD OPERATING PROCEDURES 15 VII. RADIOACTIVE RELEASES AND EtiVIRONMENTAL SURVEILLANCE 16 VIII. EDUCATION, RESEARCH AND TRAINING U2TLIZATION 19 THESES, PUBLICATION, REPORTS AND ORAL PRESENTATIONS I

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OF WORK RELATED TO THE USE AND OPERATION OF THE UFTR 23 I

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I 1. INTRODUCTION l

The University of Florida Training Reactor's overall utilization for I

the past reporting year has decreased by about 50% compared to the previous year, approaching the low levels of utilization characteristic of the previous two reporting years ending in August, 1979 and August 1980 respectively. The energy generation also continues to be far below average historical levels and represents a drop of nearly 50% from the improved level of the previous year.

An analysis of the facility utilization shows that most of the decreased usage and energy generation from the previous year is attributable to the lack of training programs. Reactor use by University of Florida courses and labora-tories continues at close to the substantial level established in the previous year; however, the complete lack of training programs conducted for nuclear utilities during the current reporting year has severely curtailed facility utilization and energy generation. In addition, research utilization remains casentially unchanged at a low level, though several investigators have inc'icated an interest in using the facility during the upcoming year, especially after the new ' rabbit' system becomes functional.

As noted in the 1981 report, the new Final Safety Analysis Report (FSAR) and Physical Security Plan (PSP) for the UFTR were submitted to the NRC during the previous reporting period. It was expected that the reactor staff would be able to dedicate themselves to enhancing facility utilization since the large administrative work load was expected to decrease significantly following FSAR and PSP submittal. However, the facility administration was hampered by the untimely resignation of the Reactor Manager during the year while the Director of Nuclear Facilities was on sabbatical leave. A suitable Acting Reactor Manager was appointed and is presently awaiting the SRO license. The Director of Nuclear Facilities has returned from the sabbatical leave and it is expected

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that this new administrative structure will be conducive to improved reactor utilization.

The NRC review of the SAR for the Safety Evaluation Report (SER) was performed by a joint NRC/LANL review team during March 1982 which produced a l series of formal questions requiring answers by UFTR staff. The UFTR staff answered the NRC Staff formal questions relating to the SER/SAR and as a result of these questions and other comments raised by the NRC Staff, Revision I to the I UFTR SAR dated May,1982 was also submitted to the NRC.

This review process and associated submittals cleared the way for final relicensing of the UFTR facility. Preparation of the UFTR Facility Emergency Plan has also involved considerable administrative effort for the last reporting year.

The UFTR continues to operate with an outstanding safety record and in full compliance with regulatory requirements. The reactor and associated facilities continue to maintain a high in-state visibility and strong industry relationship.

It is hoped that more direct industry training will be accomplished in the upcoming year.

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  • The NRC issued the new, 20-year operating license for the UFTR on August 30, 1982. New technical specifications were also issued.

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l l II. UNIVERSITY OF FLORIDA PERSONNEL P

ASSOCIATED WITH THE REACTOR I

A. Personnel Employed by the UFTR N.J. Diaz - Professor and Director of Nuclear Facilities W.G. Vernetson - Assistant Professor / Reactor Manager (Acting) January, 1982 A.W. Marvin - Reactor Supervisor (terminated December, 1981)

H. Gogun - Senior Reactor Operator (full-time)

G. Fogle - Reactor Operator (full-time)

M. Constable - Student Reactor Operator (1/2 time)

B. Gibson - Student Reactor Operator (1/3 time)

B. Radiation Control Office D. Munroe - Radiation Control Officer (October 81 - August 82)

H.G. Norton - Assistant Radiation Control Officer

- Acting Radiation Control Of ficer (September 81 - October 81)

G.R. Renshaw - Radiation Control Technician G. McCranie - Radiation Control Technician (September 81 - August 82)

W. Coughlin - Nuclear Technician (1/2 time) (September 81 - April 82)

H. Newman - Nuclear Technician (1/2 time) (January 82 - August 82)

P. Holden - Nuclear Technician (1/2 time) (January 82 - August 82)

B. McCully - Nuclear Technician (1/4 time) (September 81 - June 82)

A. Gody - Nuclear Technician (1/3 time) (August 82)

C. Reactor Safety Review Subcommittee G.R. Dalton * - Chairman W.G. Vernetson - Member (January 82 - August 82)

N.J. Diaz - Member I

  • M.J. Ohanian replaced G.R. Dalton on October 22, 1982 as chairman of the Reactor Safety Review Subcommittee.

4 7 A.M. Jacobs* - Member E

W.E. Bolch - Member

[ D. Munroe - Member (October 81 - August 82)

H.G. Norton - Member (September 81 - October 81)

I D. Line Responsibility for UFTR Administration R.Q. Marston - President, University of Florida W.H. Chen - Dean, College of Engineering A.M. Jacobs* - Chairman, Department of Nuclear Engineering Sciences N.J. Diaz - Director of Nuclear Facilities A.W. Marvin - Reactor Supervisor (September 81 - December 81)

H. Gogun - Acting Reactor Supervisor (December 81 - August 82)

E. Line Responsibility for the Radiation Control Office R.Q. Marston - President, University of Florida W.E. Elmore - Vice Presient, Administrative Affairs T.R. Turk ** - Acting Director, Environmental Health and Safety (August 82)

D. Munroe - Radiation Control Officer (From October 81)

H.G. Norton - Assistant Radiation Control Officer (September 81 - August 81)

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  • J. A. Wethington replaced A.M. Jacobs on September 1,1982 as he assumed I the position of Acting Chariman, Department of Nuclear Engineering Sciences.
    • T.R. Turk replaced Dr. B.G. Dunavant on August 21, 1982. Dr. Dunavant passed away on that date.

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III. FACILITY OPERATION

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The UFTR experienced a 50% decrease in its overall utilization when compared to the last year of use, with utilization approaching the levels of the previous two years. The change is attributed to the lack of industry educational and training programs.

( Research programs and irradiations continue to be at minimal levels. It is expected that the decision to develop the Nuclear Activation Analysis program will improve both research aid commercial irradiation utilization. Work is underway to implement a new remote sample - handling " rabbit" facility.

The level of administrative work dedicated to regulatory activities should

{ be reduced to a more manageable effort this upcoming year following Emergency Plan submittal. The facility received its new operating license in early Septem-ber; the license was issued on August 30, 1982, the last reporting day for the facility.

Shown in Table I is a summary of the reactor utilization for this reporting

{ period. The list categorizes the twenty-six different research projects, test, teaching and training activities. The total reactor run-time was about 207 hours0.0024 days <br />0.0575 hours <br />3.422619e-4 weeks <br />7.87635e-5 months <br /> while the various experiments used over 330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> of facility time.

Table 11 summarizes the different categories of reactor utilization:

university teaching, research and UFTR operator's training and requalification,

( testing and surveillance, and demonstrations. The research utilization consisted of four projects using about 65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br /> of reactor run-time. The lack of any commercial utility training programs is primarily responsible for the decrease in total facility utilization from the level of the previous year.

Detailed in Table III are the monthly and total energy generation, as well

{ as the hours at full-power per month and totals for this past year. The UFTR generated 8.44 Mw-hrs during this twelve month reporting period.

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. 0 Deucribed in Table IV is the resson.and date for t!ie only unscheduled

[ shutdown for the reporting period. No repcrteble incidents occurred during this reporting year. No uncontrolled releases of-radioactivity have occurred

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fromthefacq11tyandcontrolledreldasesarewellwithinestablishedlimits.

[ The personnel radiation doses were n:ininel and averaged well under 3% of the allowable dose. , Environmential radioactivity surveillance continues to show no detectable of f-site dose dttributable to the UFTR facility.

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TABLE I

SUMMARY

OF FACILITY UTILIZATION (September 1981 - August 1982) l NOTE: The projects marked with a e indicate irradiations or neutron activa-

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tions. The projects marked with an ** indicate training / educational use. The projects marked with an *** indicate demonstrations of reactor operations. " Utilization Time" is total time that the facility dedicates to a particular use, it includes "Run Time." "Run Time" is inclusive time from reactor startup to shutdown.

RUN EXPERIMENT TIME TIME PROJECT AND USER TYPE OF ACTIVITY (hours) (hours)

Arson-41 Determinations Argon-41 Stack Concen-g -Reactor Staff trations itcasurements 31.43 32.07 3 Operator Training Training For URC License

-Reactor Staff on the UPTR 15.76 36.89 Operator Training NRC Requalification

-Reactor Staff Training Requirements 2.20 6.52 Systems Testing Testing and Calibration

-Reactor Staff of UPTR Systems 10.09 13.02 ENU 4103

-Dr. Vernetson Operations Demonstration 1.15 2.50 NAA (Radiation Survey) Radiation Survey of Radio-

-!!. McCoy/ Reactor Staff Chenistry Lab for NAA l Iaboratory Planned 0.82 1.0 NAA (Rabbit System) Checkout of feasibility

-Reactor Staff of using existing Rabbit System. 1.11 2.50

-Dr. G. Roessler Operation Demonstration 0.67 0.97 ENU 5615/4612 Nuclear Instrumentation

-Reactor Staff Course: Instrument Lectures and Reactor Operations 1.90 6.17 ENU 4201/5206 Environmental Radiological

-Dr. C. Roessler Health Course: Instruction 1 Related to UPTR Operations 1.13 1.25 ENU 4505L Undergraduate Nuclear

-Dr. Carroll Engineering Lab 10.75 20.26

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8 RUN EXPERIMENT TIME TIME PROJECT AND USER TYPE OF ACTIVITY (hours) (hours)

ENU 6516L Graduate Nuclear

-Dr. Ellis Engineering Lab 14.87 18.29 ENV 4241 Fundamentals of Radia-

-Dr. C. Roessler tion Protection:

Operations Demonstration 0.3 0.92 l

l EMU 6617 Experimenting Gamma Ray

-Dr. Ellis Spectrometry 1.pplications 0.62 0.80 ENU 6617 NAA/ Gamma Ray Spectro-

-Drs. Ellis/Cox scopy for Metal Samples Identification 1.50 2.92 ENU 4905 Studant Reactor Operations

-Dr. Vernetson/ Reactor Staff Laboratory Course 63.63 120.56 ENU 4905 Foil Activation For

-Dr. Ellis Gamma Ray Spectroscopy 2.35 3.50 ENV 6932 Special Problems in Snvir-

-Dr. B. Dunavant/ onmental Engineering:

-Mr. II. Norton Quarterly Calibration Check of Area Monitors 0.00 1.00 Tours-Reactor Staff Operations Demonstration 2.11 3.99 Irradiation Drs. Ellis/G. Roessler NAA Bio Dental Mater'al .93 1.64 Irradiation NAA of Marine Biological

-Drs. G. Roessler/Ellis Samples 7.34 8.14 Irradiation NAA of Iluman Biological

-Dr. G. Roessler Samples 1.69 2.17 Irradiation-Dr. G. Roessler NAA of Itair Samples 9.73 9.55 Irradiation-Dr. G. Roessler NAA Bird Tissue 19.45 22.59 Reactor Measurements

-Dr. Carroll /D. llenneke Neutron Noise Measurements 5.95 10.81

.I Survey Radiation Survey of UFTR

-Reactor Staff Cell and Environment at Steady-State Itigh Power 0.48 0.48 TOTAL 206.96 330.51

9 TABLE II UPTR UTILIZATION SUW4ARY Run Time Experiment Time (hours) (hours)

UF Courses and Laboratories 96.75 174.75 Research Activities 44.09 54.90

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UPTR Operator Training and Requali-17.76 43.41

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fication UFTR Testing and Surveillance

  • 43.93 49.07 Reactor Tours and Demonstrations 4.23 8.38 TOTAL 206.76 330.51

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  • Console checkouts excluded.

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10 TABLE III MONTilLY REACTOR ENERGY Gh.dERATION 1

I I Monthly Totals Kw-Hrs llours at Full Power September 1981 628.8 6.25 October 1981 1480.7, 12.80 November 1981 90.3 0.88 December 1981 487 7 4.87 January 1982 516.7. 5.17 February 1982 284.0 0.73 March 1982 414.7 2.45 April 1982 1454.5 14.17 May 1982 1330.0 13.30 June 1982 935.0 9.35 July 1982 145.7 1.00 August 1982 670.4 6.33 YEARLY TOTAL 8438.5 77.30 I l

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'IABLE IV UNSCilEDULED SCRAMS M

Date Occurrence May 25, 1982 power Failure r

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!. IV. MODIFICATIONS TO TIIE OPERATING CIIARACTERISTICS OR CAPABILITIES OF TIIE UPTR No significant modifications to the operating characteristics were made during the reporting period.

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13 V. SIGNIFICANT MAINTENANCE AND TESTS OF UFTR REACTOR SYSTEMS

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Date Description 14 September, 1981 Repaired motor on Linear Recorder 21 September, 1981 S-4 Measurement of etack Argon-41 concentration 21 September, 1981 Renewed Demineralizer Resins in

  1. 1 portable demineralizer

( 23 September, 1981 Repaired Air Particulate Detector (APD) Blower and Air Flow System 1 October, 1981 S-4 Measurement of Argon-41 stack

[ concentration 2 October, 1981 S-1 Measurement of Blade Drop Times 7 October, 1981 Q-3 Quarterly evacuation drill exercise

( 14 October, 1981 S-2 Blade worth determination 19 October, 1981 Q-1 Quarterly scram checks

[ 22 October, 1981 Q-2 Area Monitor checks 26 October, 1981 Replaced cracked filters on primary system

[ purification loop 1 December, 1981 Smear checked Sb-Be source for leakage

[ with negative results 16 December, 1981 Q-3 Quarterly evacuation drill with

{ participation by Emergency Agencies 22 January, 1982 Q-1 Quarterly scram checks )

11 February, 1982 Q-2 Area Monitor checks 15 February, 1982 Replaced resins in both portable

( demineralizers 1 March, 1982 S-1 Measurement of Blade Drop times

[ 18 March, 1982 Q-3 Quarterly evacuation drill exercise 18 March, 1982 A-2 Instrument Calibration and check of

[ power supply voltages 16 April, 1982 Replaced dilution fan belts and tachometer

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20 April, 1982 A-2 Calorimetric check of Reactor Power 29 April, 1982 A-2 Calibration of Primary Coolant (PC) flow rate and PC temperature measuring system 30 April, 1982 S-2 Blade worth determination 30 April, 1982 Q-1 Quarterly scram checks 14 May, 1982 S-4 Measurement of Ar-41 stack concentration 21 June, 1982 Replaced canvas couplings on dilution fan ductwork 22 June, 1982 Q-3 Quarterly evacuation drill exercise 29 June, 1982 S-4 Determination of Argon-41 stack concentration 6 July, 1982 Replaced malfunctioning blade position indicator 8 July, 1982 A-1 Measured dilution fan air flow rate 26 July, 1982 Q-1 Quarterly scram checks 28 July, 1982 Q-2 Area Monitor checks 9 August, 1982 Replaced regulating blade position indicator I

l 15 I VI. CHANGES TO TECHNICAL SPECIFICATIONS AND STANDARD OPERATING PROCEDURES l

I A. There were no changes to the Technical Specifications during this reporting period. The new Technical Specifications for the UFTR were issued on August 30, 1982 and officially established on September 30, 1982. These new Tect I nical Specifications will necessitate considerable alterations and expansions of existing Standard Operating Procedures during the upcoming reporting period.

B. Revisions to Standard Operating Procedures

1. UFTR-SOP-A.2 - Reactor Startup
a. Pages 1-6 Rev. 7, 9/81
b. Pages 1-7 Rev. 8, 12/81
2. UFTR-SOP-A.3 - Reactor Operation at Power
a. Pages 3-4 I b. Pages 1-4 Rev. 7, 9/81 Rev. 8, 12/81
3. UFTR-SOP-A.4 - Normal Reactor Shutdotm
a. Page 1 Rev. 6, 9/81
b. Pages 1-3 Rev. 7, 3/82
4. UFTR-SOP-A.6 - Operation of Secondary Water System
a. Pages 1-6 Original, 9/81
5. UFTR-SOP-A.7 - Detetuination of Control Blade Integral or Differential Reactivity Worth
a. Pages 1-6 Original, 10/81
6. UFTR-SOP-C.3 - Fuel Inventory Procedure
u. Pages 1-3 Rev. 1, 5/82 I

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l VII. RADIOACTIVE RELEASES AND ENVIRONMENTAL SURVEILLANCE A. Caseous (Argon-41)

Month UCi Released Ccncentration 4.30 x 10 -10 ci/mi 6

September 1981 2.76 x 10 Ci/ Month 6

October 1981 6.60 x 10 "

1.04 x 10- "

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November 1981 4.03 x 10 6.31 x 10 6 ~

December 1981 2.13 x 10 "

3.34 x 10 7

January 1982 2.52 x 10 "

3.96 x 10 -9 "

February 1982 6 " -10 n 1.27 x 10 1.90 x 10 March 1982 1.b; x 10 6 "

2.90 x 10 -10 o April 1982 6.48 x 10 0 "

1.02 x 10 -9 "

May 1982 5.93 x 10 6 " -10 n 9.30 x 10 June 1982 3.04 x 10 6 "

9.96 x 10 -10 ,,

July 1982 4.73 x 10 5 " -10 n 1.55 x 10 6 " -10 n August 1982 2.18 x 10 7.10 x 10 TOTAL ARGON-41 RELEASES = 58.32 Ci I

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  • l There were 395,400 liters discharged to the campus sanitary sewage system during l this reporting period.

l'onth pCi/mlB September 1981 NDA**

I October 1981 NDA February 1982 NDA June 1982 NDA The UFTR normally releases approximately 1.5 liters of primary coolant per week to the holding tank due to waste from primary sampling. The average activity' for this coolant was 2.56 x 10-6 pCi/mi for the reporting period.

C. Environmental Monitoring I The UFTR n.aintains film badge monitoring in arens adjacent to the UFTR complex.

The following are the badge totals for this reporting period, September 1981 through August 1982.

Badge Designation Total Exposure (mrem)

Al 20 A2 M***

A3 M***

A4 10 I A5 A6 A7 10 M***

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  • The effluent discharged into the holding tanks comes from twenty labora-tories within the Nuclear Sciences Center as well as the UFTR complex.

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    • NDA - No detectable activity, MDA = 2.4 x 10 vCi/ml (Minimum Detect-able Activity)
      • Minimal

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18 D. Personal Radiation Exposure The following is a list of any personnel exposures greater than minimum detectable during the reporting period.

November, 1981 A. Marvin 30 mrem Beta-Camma April, 1982 M. Constable 20 mrem Fast Neutrons May, 1982 G.' Fogle* 20 mrem Beta-Camma Dosimeter exposure measurements for vicitors to the UFTR were all 6 mrem or less for this reporting period.

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  • Mr. Fogle received this dose while moving fuel at the University of Florida Spert Assembly Facility which is regulated under a separate license from the UFTR facility.

19 VIII. EDUCATION, RESEARCll, AND TRAINING UTILIZATION Note: The participating students are indicated with an *. Other partici-pants are faculty or staff members of the University of Florida, unless specifically designated'otherwise. A ** indicates those students working on theses or dissertati6ns.

1. NAA Research - Irradiation of Dental Biomaterials, Dr. W.H. Ellis, Dr. G.S. Roessler, M. McCoy*

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In this study of tooth decay, lactic acid enriched in 0-18 is administered to teeth having amalgam restorations. NAA determination of 0-18 content of

[ restored area internal surfaces is used for evaluating cavities activating lactic acid leakage around the amalgam. Results of this work are expected to provide information/ understanding of the true role played by lactic acid in

{ tooth cavities. Initial ef forts are being directed toward evaluation of the neutron activation that occurs for other extraneous materials produced in teeth exposed to neutron fields.

NAA Research - Neutron Activation Analysis of Marine Biole cal Samples, ' '

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Dr. G.S. Roessler, Dr. W.E. Bolch, K. Payne**, M. McCoy*

Various irradiation schemes were explored for instrumental NAA of biological sampics and standards which were analyzed using the TN-11 automated computer system. These NAA n.ethods were applied to determine radioactivity as well as trace element content of oysters grown in the intake versus the discharge canals

( of the FPC Crystal River Nuclear Power Plant. Specifically NAA is being used to relate elemental oyster composition to levels of activation products contained in the FPC plant effluent using activation products produced in the UFTR.

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3. NAA Research - Neutron Activation Analysis of Human Biological Samples, Dr. G.S. Roessler, Dr. T.J. Baumgartner, Garry Stewart **

In this study instrumental NAA methods are applied to biological samples (blood serum and urine) and compared with irradiated standards for both short irradiations

( (few minutes) and long irradiations (several hours). The objective of this research is to identify key controlling trace elements in the biological samples wh3ch may g then be related to various biological disorders and diseases.

r 4. NAA Research - Environmental Contaminant Levels in Birds From Phosphate - Mined Florida Wetlands, Dr. G.S. Roessler, Eduardo Barretto*, Gary McCranie*,

Kay Roessler*, Orrin Myers**, Michael McCoy*

The objective of this investigation is to compare radioactivity and trace element concentrations (such as V, Mn, Mg, A1, Ba, Th, U, F, Pb) due to phosphate mining in bird tissues and food items from selected avian species collected on various

( phosphate settling ponds and natural (control) wetlands in Florida. This project is particularly significant since phosphate mining is a widespread industry, especially in the central part of Florida.

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1 5. NAA Research - Analysis of IIair Samples for Trace Elements, W.!!. Ellis, G.S. Roessler, L. Ewald.*,P. Salas*.

Iluman hair samples are irradiated for various time periods. The activated

) samples are then spectral analyzed using minicomputer methodology to determine and identify abnormal and elemental composition.

6. Neutron Noise Analysis - Neutron Noise Measurement of 6/E for the UFTR, Dr. E.E. Carroll, Jr and D. IIenneke*
  • I For this research, two ion chambers were inserted into the UFTR thermal column.

The resulting signals at low power (1-10 Watts) were measured with picoammeters, digitized and stored in a microcomputer memory. The data were subsequently auto-I and cross-correlated and Fourier-transformed to yield the UFTR reactor transfer function. This project has resulted in the acquisition and ordered documentation of computer analysis programs which can be used in future graduate level UPTR I laboratory classes.

7 Neutron Noise Analysis - Extrapolation of liarmonic Signals to Improve Frequency Resolution, Dr. E.E. Carroll, Jr.,D. Bodette**

This research project involves the study of methods used to extrapolate time-series-data and the investigation of repeated auto-correlations and auto-convolutions I in comparison with the results obtained using the Maximum Entropy and Maximum Like-lihood Methods. Some UFTR noise data was generated and applied as input to this study which is expected to result in some unique methods of time series analysis to I allow extrapolation of limited signals with resulting improvement in frequency re-solution.

8. UPTR Core Redesign (LEU Program) - Neutronics Analysis for UFTR Core Redesign E.T. Dugan, W.G. Vernetson, N.J. Diaz, G. Kniedler**

As part of the DOE Iow Enrichment Uranium Program, investigations have been I performed on the UPTR to determine the feasibility of replacing the 93% enriched MTR plate type fuel with 4.8% enriched, cylindrical SPERT fuel pins. For this redesign, the only permanent structural modification is the insertion of new grid I assemblics into existing fuel boxes. Acceptable neutronic criteria (possible k eff range and degree of undermoderation) have been determined using industry-accepted, 4-group cross sections in one, two and three-dimensional diffusion theory calcula-I tions of k egg, flux profiles, power peaking factors and coefficients of reactivity.

First order perturbation calculations have been used to determine key kinetic para-meters. Neutronic results to date indicate that the UFTR/SPERT core redesign can l

B be accommodated to meet requisite neutronic criteria and with a minimal reduction in peak thermal flux levels.

9. UFTR Core Redesign (LEU Program) - Thermal-llydraulic Analysis for UPTR Core I Redesign, E.T. Dugan, W.G. Vernetson, N.J. Diaz, R. Ilommerson**i M. Miller.

As part of the DOE LEU Program, thermal-hydraulic analysis related to redesign 1 of the UPTR core using SPERT fuel rods is being performed. Computer analysis has been undertaken to evaluate the UFTR/SPERT design for Steady-state conditons as well as transients arising in response to a step insertion of reactivity, a loss of cool-ant flow, and a loss-of-coolant accident. Preliminary results to date indicate required safety margins and transient response conditions can be maintained with the UPTR/SPERT core design.

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10. UFTR Operator Training and Requalification - Dr. N.J. Diaz, H. Gogun

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Lectures and hands-on operations on the reactor are necessary to license

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operators for the UFTR. The requalification program establishes a required L number of startups, weekly checks, daily checks, drills, and lectures for each operator. Operator participation is mandatory in order to maintain requisite assurance of proficiency levels.

11. Reactor Operations Demonstrations Course Instructor

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ENU 3002 Dr. G.S. Roessler ENU 4103 Dr. J. A. Wethington, Jr.

[ ENU 4612/5615 Dr. W.H. Ellis Dr. C.E. Roessler ENU 4201/5206 ENU 4241 Dr. C.E. Roessler

12. NAA Research - Rabbit System Remote Handling Facility Development, Dr.G.S.

Roessler, Dr. W.G. Vernetson, M. McCoy*, Reactor Staf f Reactor power running was done to allow radiation survey in the radiochemistry laboratory where the new NAA Instrumentation and counting facility will be con-structed. Reactor power running was also done to allow checkout of the feasibility

[ of the existing ' Rabbit' facility.

13. Gaseous Release Determinations - Argon-41 Stack Measurements, Dr. W.E. Bolch,

.[ Dr. W.G. Vernetson, A. Marvin, M. Stafford, Reactor Staff A new cobalt-60 Standard Sample has been applied in measurements of radio-activity (Ar-41) in stack effluent. An annotated computer program and detailed

{ procedure is being developed along with applicable error analysis intended to provide the best possible estimate of Ar-41 releases from the UFTR f acility.

14. Nuclear Engineering Laboratory I (ENU 4505L) - Dr. E.E. Carroll, Jr. , Reactor Sta ENU 4505 is the nuclear engineering laboratory for undergraduate senior level

[ students in Nuclear Engineering Sciences. The UFTR is used for a variety of exercises and experiments, including radiation dose measurements, measurement of induced radioactivity and reactor physics parameters as well as operational ,

measurements.

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15. Nuclear Engineering Laboratory II (ENU 6516L) - Dr. W.H. Ellis, Reactor Staff ENU 6516 is the main laboratory course for Nuclear Engineering graduate students. It involves radiation and reactor-related measurements and experimenta-tion on a more advanced level than ENU 4505L.
16. Reactor Operations Laboratory (ENU 4905) - Dr. W.G. Vernetson, Reactor Staf f Students of the Reactor Operations Lab (Spring Semester, 1982) spend 2-3 hours

( weekly at the controls of the UFTR performing reactor operations under supervision of licensed reactor operators. The lab encompasses training in reactivity manipul-

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22 ations, reactor checkouts, operating procedures, standard operations and all applicable regulations. Specific exercises directed toward development of understanding of light water power reactor behavior are included as this labor-7 atory course serves as basic preparation for students entering the utility in-L dustry in the test and startup area.

_. 17. Applied Gamma Ray Spectrometry Laboratory (ENU 6617) - Dr. W.H. Ellis, Dr. John Cox, G. Wang * ,

ENU 6617 is the graduate course which addresses the principles, tools and techniques of gamma ray spectrometry with UPTR laboratory applications to radio-nuclide and radioactivation analysis. Specific experiments include identifica-tion of unlabeled metallic samples using the techniques of Gamma Ray Spectroscopy.

I 18 Radiation Protection and Control Field Exercises (ENU 6932) - Dr. B.G. Dunavant, H. Norton, Reactor Staff This course provides students in various disciplines with practical experience in radiation protection and control such as performing radiation surveys in and I around the UFTR cell and environs, calibrating area radiation monitors, etc.

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IX. TilESES, PUBLICATIONS, REPORTS AND ORAL PRESENTATIONS OF WORK RELATED TO TIIE USE AND OPERATION OF TIIE UPTR

1. David E. Bodette, " Application of Correlations and Convolutions to the Extrapolation of flarmonic Signals to Improve Frequency Response," Masters' I Thesis in NES Department, Expected Completion December, 1982.
2. Dennis !!cnneke, " Measurement of 6/E for the University of Florida Training I Reactor," Masters' Degree Project, August, 1982.
3. Gregory S. Kniedler, "Neutronic Calculations for the Proposed Redesign of the University of Florida Training Reactor Using Spert Fuel," Masters' Degree Project, June, 1982.

I 4. Gregory S. Kniedler, "Neutronic Calculations for the Proposed Redesign of the University of Florida Training Reactor Using Sport Fuel," Oral report presented at the 1982 Eastern Regional ANS Student Confetence held at Georgia Institute of Technology, Atlanta, GA, April 16-17, 1982.

5. Rcbert !!ommerson, " Thermal Analysis for the University of Florida Training Reactor Using SPERT Fuel," oral report presented at the 1982 Eastern Regional ANS Student Conference held at Georgia Institute of Technology, Atlanta, GA, April 16-17, 1982.

I 6. Rober+ llommerson, " Thermal-!!ydraulic design of the University of Florida Train-ing Reactor using SPERT Fuel," Masters' Degree Project, Expected completion:

December, 1982.

7. U.R. Marion, C.E. Roessler, G.S. Foessler, !!. Van Rinsvelt, " Levels of Selected Environmental Contaminants in Birds From Phosphate - Mined Wetlands," Annual Report to Florida Institute of Phosphate Research, 1981 - 1982.

I 8. Kenneth W. Payne, " Concentration Factors of Crossostrea Virginica In the Vicinity of Crystal River," Masters' Degree Project, August, 1982.

9. Thomas J. Baumgartner, Genevieve S. Roessler and Garry Stewart, "Al/Cu Pre-cipitants in Total Parenteral and Enteral Nutrition Compounding Procedures,"

submitted for publication in Fall, 1982 in the Journal of Parenteral and I Enteral Nutrition.

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