ML20111B587

Tx A&M Univ Nuclear Science Ctr 1995 Annual Rept

ML20111B587
Person / Time
Site:	05000128
Issue date:	12/31/1995
From:	Okelly S TEXAS A&M UNIV., COLLEGE STATION, TX
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-0123, 96-123, NUDOCS 9605140521
Download: ML20111B587 (48)

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TEXAS ENGINEERING EXPERIMENT STATION TEXAS A&M UNIVERSITY

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COLLEGE STATK)N, TEXAS 77841 3575 J

n a NUCLEAR SCIENCE CENTER 409/845-7551 8 May 1996 96-0123 Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, DC 20555

SUBJECT:

Annual Report for Nuclear Science Center Reactor REF:

Reactor Facility License R-83, Docket 50-128

Dear Sir / Madam:

Attached you will find the 1995 Annual Facility Report for the Texas A&M University Nuclear Science Center.

Please contact me if you have any questions.

Respect ly i

Sean O'K NSC Assistant Director 4

SOK/sjm

Attachment:

1995 Annual Facility Report xc File 17122, NRC/R-83 NRC Region IV 12110/ Central File 9605140521 951231 PDR ADOCK 05000128 PDR R

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RESEARCH AND DEVELOPMENT FOR MANKIND

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Texas Engineering Experiment Station F.E. Box 89 College Station, Texas 77843-3575 a

i Reactor Facility License R-83 Docket 50-128 DOE University Reactor Fuel Assistance DE-AC07-76ER02426 4

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' Contents 1.0 Introduction 3

1.1 Nuclear Science Center Staff 4

2.0 Reactor Utilization for 1994-1995 5-6 2.1 Research Enhancement Program 7

2.1.1 Introduction 7

2.1.2 Research Projects Supported 7-17 2.2 TAMU Academic Support Program 18 2.2.1 Introduction 18 2.2.2 Research Projects Supported 18-20 2.3 DOE University Reactor Sharing Program 21 2.3.1 Introduction 21 2.3.2 Research Projects Supported 21-32 2.4 Commercial Activities 33 3.0 Facility and Procedure Changes 34 3.1 Facility Modifications 34 3.2 Experiment Modifications 34 4.0 Reactor Maintenance and Surviellence 35 4.1 Scheduled Maintenance 35 4.2 Emergency Planning and Review 35 4.3 Unscheduled Shutdowns 35 4.4 '

Reportable Occurences 36 h

5.0 Health Physics Surviellences 37

5.1 Radioactive Shipments 37 5.2 Personnel Monitoring 37 5.3 Facility Monitoring 37 5.4 Particulate Efiluent Monitoring 37 5.5 Gaseous Efiluent Monitoring 38 5.6 Liquid Efiluent Monitoring 39 6.0 Environmental Monitoring 41 6.1 Environment Survey Samples 41-42 6.2 Site Boundary Monitoring 43 6.3 Radioactive Waste 44 7.0

. Reactor Safety Board 44 l

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- 1. O Introduction-The Nuclear Science Center is operated by the Texas Engineering Experiment Station as a 2

service to the Texas A&M University System and the state of Texas. The Nuclear Science Center (NSC) is a multi-disciplinary research and education center supporting basic and applied research in all nuclear related fields of science and engineering as wee as providing j

educational opportunities for students in those fields. In addition, the NSC provides -

services to commercial ventures requiring radiation or isotope production services.

This annual repon has been prepared by the NSC staff to satisfy the reporting requirements of Technical Specification 6.6.1 of the facility operating license R-83 and of the Depanment of Energy University Reactor Fuel Assistance Program subcontract No.

C87-101594 (DE-AC07-76ER02426). The facility operating license currently extends to March, 2003.

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The NSC increased the diversity ofits services during this reporting period. A Fast Flux 1

l Irradiator for the support of"Ar/"Ar dating of geologic samples was designed, built and l

tested as a Master's thesis project. Users of this new facility have been very impressed j

and consider it to have excellent fast neutron activation characteristics. The completion of a radioactive material handling cell in the chemistry lab will let researchers perform on-site radiochemical separations. The NSC has also begun providing gamma irradiation services on a regular basis using the facility Irradiation Cell. The total operating hours of the reactor and the number of experiments increased this year from those of 1994.

In the past, NSC reactor maintenance and fuel inspections were performed in January following the University Christmas Break. This has impacted experimenters and commercial users because it resulted in the reactor being shutdown for several consecutive weeks. To reduce these extended shutdowns, the maintenance period was moved to i

September. Therefore, there were two periods of maintenance and fuel inspections in 1995.

There were no changes to the NSC operating license or the Security Plan this period. A change to the Emergency Plan has been submitted to the NRC and is still under review.

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let Nuclear Science Center Staff The staff at the Nuclear Science Center is split into four primary work groups; Operations, Health Physics, Maintenance and Administration. Personnel directly involved with the operation and maintenance of the reactor are NRC-licensed operators. The NSC is committed to its educational responsibilities and many of the staff are part or full-time students at Texas A&M Universitye "E '."."

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The Nuclear Science Center reactor has been in operation since 1962. The reactor is a 1 Megawatt MTR converted to TRIGA fuel. The TRIGA fuel is high-enrichment uranium (HEU) with 70% enrichment, but will be converted to 20% enriched fuel when funds become available. Core VIII-A is the current core configuration and has been used since l

March,1986. The NSC reactor is pulse operational with nearly twice as many pulses performed this year as compared to 1994.

I The NSC reactor operated for 1963 hours0.0227 days <br />0.545 hours <br />0.00325 weeks <br />7.469215e-4 months <br /> in 1995 with a total integrated power of 80.4 Mw-Days. There were 671 irradiations and services performed at the N2C during the reporting period. The NSC provided services to TAMUS depcrtments, other universities, research centers and secondary schools in and outside the state of Texas. The reactor was f'

used by 12 departments at TAMU and 6 other universities.

I Reactor Utilization Summary

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l 1994-1995 l

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Days of Reactor Operation 225 l

Integrated Power 80.4 Number of Hours at Steady-State 1963 Average Hours of Operation a Week 37.8 l

Number of Pulses 28 Number of Reactor Irradiations 671 l

Beam Port Experiment Hours 64.4 l

Hours Irradiation Cell Use 4.2 Number of Visitors 2808 5

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i 2.1 Research Enhancement Program 2.1.1 Introduction The 70th Texas Legislature established the Research Enhancement Program (REP) in 1987 to " encourage and provide for research conducted by faculty members". The REP replaced the former " Organized Research" program.

The REP funds are administered by the TAMU Office of the Vice President for Research.

Due to a reduction in the state allocation in 1995, the REP funds allocated to the NSC were reduced to $22,000 from a nominal $42,000. Unused funding from the previous.

year of $1697.60 was brought forward. This sizable reduction in funding limited much of the normal faculty exploratory research. Several research programs were cunailed by the limited funds and a few required support by TEES and the NSC in order to complete projects after REP funds were expended.

A new disbursement plan was initiated this year to ensure REP funds allocated to NSC researchers are used prior to the end of the fiscal year. This reduces the chance of not expending the funds for research and bringing unused funds forward to the next fiscal year. Research projects are evaluated during the second and fourth quarters for use of REP funds. If by mid-fiscal year a researcher has not used or scheduled reactor services, his or her funding is reduced by one-half. These funds will then be available for other researchers who require funding. Early in the fourth quarter all unexpended REP funds

. administered by the NSC are made available to all qualified researchers on a case-by-case basis until all the NSC's REP allocation is expended.

i Funds for reactor services were made available to the individual colleges as follows; College of Science

$ 2,771.72 j

College of Engineering 495.30 i

College of Liberal Arts (Archeology)

$ 10,489.30 College ofGeoscience

$ 9941.28 Total

$ 23,697.60 i

2.1.2 Research Projects Supported Development and Evaluation of Recoil-Nucleus Time-of-Flight Neutron Depth Profiling (TOF NDP)

Emile A. Schweikert, John F. Welch Jr., W. Ricky Ferrell Center for Chemical Characterization and Analysis, Depanment of Chemistry

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. Objective of research is the development of a new method of analysis, recoil-nucleus TOFNDP. NSC provided support in the construction of TOF spectrometer for use with radioactive charged particle emitter, Po-210, an alpha emitter, will be used as a model for nuclides undergoing (n, charged particle) reactions for the purpose ofinstrumental development. The Po-210 will be used in two spectrometers. NSC personnel produced '

the Po-210 source by the activation of a Bismuth target.

Paper presented at 1995 Fall Meeting of Materials Research Society:

4 Characterization ofBismuth Deposits amtkeV1mplants Using Recoll-macleus Time-of-l flight Neutron Depth Profiling and Plasma Desorption Mass Spectrometry Polymerization of Silicon Oils Using Gamma Radiation for Artifact Conservation Donny L. Hamilton, C. Wayne Smith, R. Paul Gidden Nautical Archaeology Program (Department of Anthropology), Department of Nuclear Engineering A series of experiments were designed to develop a set of working parameters for using a variety of molecular weights of polymer silicones for the purpose of bulking and stabilizing waterlogged archaeological materials. Once these parameters are established, additional experimentation will be conducted to address issues of types of cross-link bonds, process reversibility and scission.

Neutron Activation Analysis Determination of the Effects of Alkaline Dithinote on Ancient Bronze Coins Donny L. Hamilton, Georgia L. Fox Nautical Archaeology Program (Department of Anthropology)

A Note on the Use ofAlkaline Dithionitefor Treating Ancient Bron:e Artifacts; Studies in Conservation, Vol. 40 (1995) 139-142 Research was carried out to determine the percentage of metallic copper and tin in solutions of alkaline dithinote. Alkaline dithinote is a chemical used in archaeological conservation to preserve cuprous metal artifacts. The efficacy of this procedure is confirmed through the conservation of several small bronze artifacts from Tel Nami, Israel. Tel Nami is located near the Mediterranean Sea, therefore the bronze artifacts suffered from cuprous chloride contamination. An experiment with bronze Chinese coins confirms that some metal is lost to solution when using alkaline dithionite; however, the i

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artifacts.

4 Cr-Spinelin Depleted Basalts from the Lau Basin Backarc: Petrogenetic History j

from Mg-Fe Crystal-Liquid Exchange 4

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Texas A&M Ocean Drilling Program, Department of Geology Proceedings of the Ocean Drilling Program, Scientific Results, Vol.135 Cr-spinels in cores drilled during Ocean Drilling Program Leg 135 exhibit wide variation l

in composition and morphology that reflect complex petrogenetic histories. These Cr-spinels are found within basaltic lava flows that erupted in north-trending sub-basins i

within the Lau Basin backarc. Cr-spinels from Sites 834 and 836 occur as euhedral groundmass grains and inclusions in plagioclase, and range up to 300 mm in size. These Cr-spinels are similar in composition, morphology and mode of occun ence to Cr-spinels found within depleted, N-type mid-ocean-ridge basalts (N-MORB), reflecting similar crystallization conditions and host lava composition to N-MORB.

Cr-spinel-bearing rock samples were analyzed to provide a compostional framework for the mineralogical studies. Due to the rarity ofglassy material in the core and restrictions l,

on glass sampling, only whole-rock powders were available for major and trace element analysis. Instrumental neutron activation analysis was performed on powder samples and compared to shipboard X-ray fluorescence. Samples were mn in duplicate, with 2-hr counts obtained at 7-12 days,28-33 days, and 4 months using lead-shielded Ortec coaxial intrinsic germanium detectors at Texas A&M Center for Chemical Characterization and Analysis.

Petrologic Evolution of Lau Basin Sites 834 through 839 James W. Hawkins and James F. Allan Geological Research Division. Scripps Institution of Oceanography, La Jolla CA i

Texas A&M Ocean Drilling Program, Department of Geology i

I Proceedings of the Ocean Drilling Program, Scientipc Restdts, Vol.135 Ocean Drilling Program Leg 135 provided igneous rock cores from six sites drilled on a j

transect across the Lau Basin between the Lau Ridge remnant arc and the modern j

spreading ridges of the Central and Eastern Lau Spreading Centers. The drill cores sampled crust from the earliest stage of backarc extension (latest Miocene time, about 6 Ma), and younger crust (late Pliocene, about 3.8-2 Ma, and Middle Pleistocene, about 1

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l 0.64-0.8 Ma). Nearly all of the igneous samples are from tholeitic basalt flows; many of them are interbedded with arc-composition volcaniclasic sediments.

A major focus of study for Leg 135 was the long-standing problem of the petrologic / tectonic controls on backarc magmatism and the relationship between coeval are and backarc magmatism. Understanding these processes has implications to the nature of mantle sources for magmas and to magmatic processes in arc, backarc and forearc settings. It also can give insight to the nature of tectonic processes that form these wide zones ofcrustal extension at convergent intraoceanic plate margins.

i Instrumental neutron activation analysis was performed on bulk-rock powders split from samples analyzed by shipboard XRF. These bulk-rock samples give a fairly reliable r

y indication ofmagma evolution.

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Data Report: Trace Element Geochemistry of Leg 142 Basalts by Instrumental Neutron Activation Analysis James F. Allan Texas A&M Ocean Drilling Program and Department of Geology Proceedings of the Ocean Drilling Program, Scientific Results, V01.142 During Leg 142, two units of moderately evolved basalt were recovered from the East Pacific Rise axis at 9 30'N. Instrumental neutron activation analysis of seven samples from these units shows them to be light rare-earth-element (REE)-depleted, normal mid-ocean ridge basalt, with (La/Sm)w of 0.52-0.56, flat chondrite-normalized medium-to-i heavy rare earth patterns, and slight negative europium anomalies. Unit 2 contains slightly

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higher amounts of RE and Hf and lower amounts of Cr than Unit 1, with both units similar in composition to the most-evolved samples previously collected from this section of the l

ridge crest.

Drilling and coring at mid-ocean ridge spreading centers has been a long-standing goal in the earth science community. Site 864 located on the East Pacific Rise (EPR),

i represented the initial attempt in a long-range plan to core the entire crustal section at the i

EPR. The principle scientific goal of Leg 142 was to core 100 m into the uppermost crust of this fast-spreading center (llem/ year). Sample counting was performed at Texas A&M Center for Chemical Characterization and Analysis.

Petrology of Selected Leg 147 Basaltic Lavas and Dikes James F. Allan, Trevor Falloon, Rolf Pedersen, B. Shankar Lakkapragada, James Natland, John Malpas 1

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1 Texas A&M Ocean Drilling Program and Department of Geology University of Tasmania Department of Geology, Tasmania, Australia University of Bergen Geological Institute, Bergen, Norway University of Miami Rosenthiel School of Marine and Atmospheric Sciences, Miami, FL Memorial University of Newfoundland Department of Earth Sciences, St. John's NF Proceedings of the Ocean Drilling Program, Scientific Ressdts, Vol.147 i

Sites 894 and 895 of Ocean Drilling Program Leg 147 recovered a variety of basaltic material from the Hess Deep intrarift ridge, including cores of dikes that cut gabbroic and peridotitic wall rock and fragments of pillowed, surficial laval flows. The site 894 basalts are more depleted than EPR N-MORB in incompatible elements, with extreme depletions in both the light rare earth elements (LREE) and Ta and Nb. The intrusive relations, mineralogy, and geochemistry of these samples suppon an off-axis origin of these samples during opening of the Hess Deep.

The Site 895 basalts. sampled from both dikes and pillowed flows, are aphyric, more evolved and less depleted in LREE, Ta and Nb than the Site 894 samples. Unlike the Site 894 samples, these characteristics allow derivation from a mantle similar in composition to that underlying the EPR. Intrusive relations and geochemical characteristics suppon a mixed origin for the Site 895 samples, with some originating at or near the EPR crest, and 4

others representing volcanism associated with Hess Deep opening.

INAA was performed at the Texas A&M TRIGA reactor with counting performed at Texas A&M CCCA.

Uranium and Thorium in Paleozoic Aquifers Surrounding the Llano Uplift Area, Central Texas (Delayed-Neutron Counting)

Thomas T. Tieh, Youngic Kim, Earnest B. Ledger

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Texas A&M Department of Geology and Geophysics j

Stephen F. Austin State University Department of Geology Agulfer Mineralogy andNatural Radiomiclides in Groundwater-The Lower Paleo:cic of Central Texas (Gulf Coast Association of Geological Societies Transactions, Vol. XLV, 1995)

Uranium and Thorium in Paleo:oic Aquifers Surroimding the Llano Uplift Area, Central j

Texas (presented at 1995 Annual Convention of the American Association of Petroleum Geologists, March,1995, Houston, TX) l 11

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Water-mineral interactions in an aquifer may give rise to high levels of Ra and Rn in groundwater. An understanding of aquifer mineralogy is therefore essential to determine the sources of natural radionuclides and design possible means for improving water quality. Anomalous Ra and Rn concentrations have been detected in groundwater produced from the Cambrian Hickory and Cap Mountain aquifers in the Llano Uplift area ofcentral Texas.

Analysis of uranium in 123 samples by delayed-neutron counting at the Nuclear Science Center shows an average concentration of 3.8 ppm. Shaly samples generally contain i

significantly higher U. Gamma-ray analysis ofTh in 21 samples yields an average of 13.7 ppm. Fission-track imaging, also performed at the NSC, shows that U occurs predominantly in: (1) phosphatic fossil fragments and intraclasts, especially in the Cap Mountain; (2) thin shaly laminae which are more abundant in the Hickory; (3) authigenic minerals including hematite and clay minerals.

Trace Element Analysis of Prehistoric Ceramics from the American Southwest and Mesoamerica Harry J. Shafer, Dennis James Department of Anthropology, TAMU Center for Chemical Characterization and Analysis The research is to identify geographic loci of ceramic production in the prehistoric southwest and in Belize. The 94-95 research emphasized the American Southwest, specifically the production of Mimbres black-on-white pottery in the Mimbres and Gila River drainages. This phase raised a number of new questions regarding ceramic production and additional samples were selected and examined. Additional samples are now being prepared for a final analysis of Southwestern pottery and a new project will begin on ceramic craft specialization among the lowland Maya. The Maya study will examine a Late-Terminal Classic Period polychrome ware from sites in northern Belize.

This will be a very important contribution to the study of Maya ceramics and will be a pioneering effort to identify craft specialization through trace. analysis.

Interregional Networks in the Classic Mimbres Period: The Ceramic Evidence Robbie L. Brewington, Dennis James Department of Anthropology, TAMU Center for Chemical Characterization and Analysis Paperpresentedat the 60th Meeting of the Society ofAmerican Archeology, Minneapolois,1995.

Previous research indicates that Mimbres decorated ceramics exhibit spatial variation-specific designs were more commonly used in some areas than others. This finding 12.

-O suggests that Mimbres pottery was locally produced and used. At the same time, i

however, there is a consistent patterning in design that allows us to recognize Mimbres pottery wherever it occurs.' A social mechanism that might be responsible for this j

patterning is participation is a shared symbolic system.

Other research indicates that Mimbres ceramics were widely distributed-which would blur i

the distinctiveness oflocal design variation. Whether the regional homogeneity of Mimbres ceramic design resulted from distribution of vessels or a shared iconographic system, or both, the result is hetrogeneity in design at the local level and homogeneity at a regionallevel.

Neutron Activation Analysis was performed at the NSC and CCCA in order to establish distribution patterns for the 130- year Mimbres Classic Period from 1000 A.D. to 1130 A.D.

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Compositional Analysis of American Southwestern Ceramics by Neutron Activation

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Analysis W.D. James, R.L. Brewington, H.J. Shafer TAMU Center for Chemical Characterization and Analysis, Department of Anthropology Journal ofRadioanalyticalandNuclear Chemistry, Vol.192, No.1(1995) 109-116 l-Instrumental neutron activation analysis was used to perform compositional analysis on i

more than 200 potsherds from prehistoric ceramic pottery collected in or near the Mimbres Valley in New Mexico. Statistical evaluation of the data was used to identify samples of similar origin. Results indicate that at least two sites within the Mimbres heartland and one in the Upper Gilla Valley existed for the production of the characteristic Classic Mimbres pottery, i

Application of Neutron Activation Analysis Techniques to TAMU Research Problems at CCCA W.D. James TAMU Center for Chemical Characterization and Analysis REP funds were used for method development in NAA and to apply these techniques to wide range of problems. Often, CCCA funds were used to perform exploratory work for campus researchers. The following is a list of non-CCCA projects:

Dr. James Haw, Department of Chemistry 13

Determination oftransition metal concentrations in t,colite. Three separate student research projects on this related material were performed during this year Eleven separate NAA projects were performed during the year.

- Graduate students: David Murray, Mike Krawitz and Timothy Howard.

Dr. Abraham Clearfield, Department ofChemistry Determination ofelemental components ofpillared clay samples. These are aluminum oxide rich clays, one being saponite containing about 15% zirconium.

Dr. Kevin Burgess, Department ofChemistry Searchfor adsorbed markers on microbeads. Potential is for the development of a method of tracking individual beads in chemical reactions.

Dr. Timothy Phillips, Veterinary Anatomy and Public Health Multi-element trace analysis of ammonium-exchanged montmorillonite clays,

under investigation as possible natural ion exchange materials.

Graduate student: Kent Washburn Dr. GeraldBratton and Dr. Raymond Tarpley, Veterinary Anatomy andPublic Health Multi-element determination of trace constituents in whale liver and blubber.

Potential for adding the method to a suite of techniques used in an existing survey program for marine environmental measurements.

An Instrumental Neutron Activation Analysis of 18th Century Lead-glazed Earthenwares from Four Spanish Missions in Texas S.D. Carlson, W.D. James Department of Anthropology and Archaeology, TAMU Center for Chemical Characterization and Analysis Submitted to J. RadioanalyticalandNuclear Chemistry (1995) andpresented as an imitedpaper at the 1994 WinterMeeting of the American Nuclear Society in Washington, D.C.

Neutron Activation Analysis was performed on pottery sherds at the NSC for multi-element trace analysis. The research was performed to determine relative manufacturing 14

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centers of these earthenwares in 18th century Texas. Some of the results of the study indicate that some " Mexican" lead glazed earthenwares were likely made by Indians at the individual missions.

d Characterization of Guatemalan Ceramics by NAA S.D. Carlson, W.D. James TAMU Center for Environmental Archaeology, TAMU Center for Chemical Characterization and Analysis 359 samples of Guatemalan ceramics were studied this past year. These samples were obtained from the Guatemalan southern highlands, in an area around Lake Atitlan.

f Provenance Determination of Guatemalan Obsidian Artifacts by NAA H. J. Shafer, M.R. Woodward Department of Anthropology 214 obsidian samples were analyzed to determine sources oforigin. Sixty-six samples were source material from volcanic outcroppings that were used to produce prehistoric tools. Three outcroppings were used and considered to be sources. It was found that the majority (95%) of the tools were produced from the so-called San Martic Jilotepeque outcropping and none came from the Ixtepeque location. It is hypothesized that the 4

Ixtepeque outcrop had not been exposed early enough to be used to produce stone / obsidian tools.

Texas A&M University Trace Element Research Laboratory Department of Oceanography P.N. Boothe, B.J. Presley, Robert Taylor The Trace Elemen't Research Laboratory (TERL) is considered to be one of the premier inorganic environmental chemistry laboratories in the United States. TERL has an international reputation, earned through numerous blind intercalibration exercises and documented project performances, for consistently producing the highest quality trace element data for any type of environmental sample. TERL specializes in low detection level measurements of trace metals in environmental samples (including water, wastewater, sediment and biota) conducted under a comprehensive quality assurance /

quality control program.

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The following is a list of TERL projects performed using REP funds, but many of the TERL projects are externally funded.

. Intercalibrations g

TERL participates in national and international intercalibration exercises each year._

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U.S. GeologicalSurvey. Evaluation Program for Standard Reference Water Samples. TERL placed fourth among the 137 laboratories l

participating. NAA was used to confirm the analysis ofseveral elements in the unknown sediment sample.

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NationalResearch Council ofCanada and U.S. NationalInstitute of Standards and Technology. Annual NOAA National Status and Trends Trace Element Intercalibration Exercise. TERL received honors and a long-term proficiency award for superior ratings in Exercise #8 in 1994.

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Quality Assurance ofInformationfor Marine EnvironmentalMonitoring j

in Europe (GUAS/MEME). TERL is the only U.S. laboratory participating in this European Community sponsored low detection level intercalibration 1

exercise for tissue and sediment. In the latest round, TERL received the highest possible rating for both matrices.

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Quality Assurance Program Neutron Activation Analysis is performed as an independent check of other methods of analysis. This helps to identify and correct problems with other TERL spectroscopy-based methods. NAA is also used to do an annual method detection limit study on sediment and tissue samples.

Methods Development TERL is constantly developing new methods or applications for NAA in research. This past year considerable eTort went into developing and refining NAA methods for marine tissue analysis. These new methods were applied to a externally funded NOAA National Status and Trends program. The methods developed are now routinely used in determining Ag, As, Cr, Fe, Sb, Se, and Zn concentrations in bivalve tissue for the NS&T i

program.

Exploratory Research REP funds allowed TERL to support small unfunded research studies and to expand funded projects. For example, the Minerals Management Service Gulf Offshore Operations Monitoring Experiment (GOOMEX) was a large study aimed at investigating the chronic impacts of offshore petroleum development and production in the Gulf of ~

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6 Mexico. This project involved a large amount of funded NAA analyses of marine sediment for BA, Cr, Fe, Sb, and Zn. There was no funding to analyze sub-surface sediments. REP funds were used to analyze selected sediment core material. This approach added a new historical perspect.ive to the study and was critical to the interpretation of the sediment data.

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2.2 Texas A&M University Academic Support Program 2.2.1 Introduction 1

Texas A&M University provides funding for at the reactor for such academic activities as nuclear engineering laboratories, neutron activation analysis demonstrations and laboratories, graduate student thesis research and undergraduate research projects. The program has been very successful and is crucial for many graduate students whose chosen research uses the NSC reactor in some way, but is not supported by any research grant.

The NSC's reputation as a multidisiplinary institution is reflected in the wide range of the academic users from the university.

2.2.2 Texas A&M University System Academic Projects Supported Trace Metal Contamination of Waters, Sediments, and Organisms of the Swan Lake Area of Galveston Bay (M.S. Thesis, Junesco Park, Department of Oceanography)

Swan Lake is a sub-bay of the Galveston Bay system. The area received mnoff from a tin smelter via the Wah Chang Ditch which ran through it in the past but the ditch is now cut off by a hurricane protection levee. An industrial waste disposal facility (Gulf Coast Waste Disposal Authority)is located north of the Wah Chang Ditch. Consequently there have been concerns about possible metal contamination in this area.

Trace metal concentrations in water, sediments, and organisms (oyster, mussel, snail, crab, fish, shrimp, and spartina) in the area were determined. Sediments were analyzed for total 4

Ag, Al, As, Cd, Cu, Fe, Hg, Mn, Ni, Pb, Se, Sn, and Zn. Water samples were analyzed for Cd, Cu, Fe, Mn, and Sn.

The variabilities and geographic trends in sediment trace metals indicated that waste disposal and airborne inputs from facilities located at the Tex Tin site were likely sources for metal pollution found in the sediments. Sediments in the study area showed elevated trace metals relative to Galveston Bay and other Texas bay sediments, Three different samplings of the Wah Chang Ditch showed no temporal patterns in metal distribution in the sediments. Lead concentrations were uniformly high from the three samples. Metal enrichments at depth in the sediment column indicated that the Swan Lake area has recently received less input of metal contaminated sediment than in the past.

Anthropogenic inputs did not greatly influence the natural concentrations of Fe, Al, and Ni in sediments either in the past or at present.

Most organisms showed very small spatial variations. However, the oysters in Swan Lake are enriched in most metals relative to Galveston Bay and other U.S. Gulf of Mexico oysters. The mussels in this study do not reflect the unusually elevated environmental i

metal concentrations in the sediments from which they were taken. Iron and Pb 18

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concentrations in oysters seemed to be directly related to sediment concentrations at each location. Oysters show higher concentrations in most metals compared to mussels. The Zn level was 113 times higher in oysters. For organisms collected from the Swan Lake area trace metal concentrations were generally oysters-snail-crab-shrimp-fish, from highest to lowest.

Metal concentrations in Wah Chang Ditch water were very elevated relative to those of the Brazos River and Galveston Bay. These concentrations closely reflect those in the sediments of the Wah Chang Ditch.

Spatial and Temporal Variations of Trace Metals in Bottom Sediments of Peter the Great Bay, the Sea of Japan.

i A.V. Tkalin, Fullbright Research Fellow at TAMU Far Eastern Regional Hydrometeorological Research Institute Vladivostok, Russia B.J. Presley, P.N. Boothe Trace Element Research Laboratory Department of Oceanography In 1994, the Russian Federation, Japan, the People's Republic of China, and the Republic ofKorea signed an Action Plan for the protection of the marine environment of the l

northwest Pacific Ocean. An initial step in the Plan was a characterization of the current environment in the Sea of Japan and the Yellow Sea. INAA was one of the methods used in this characterization program.

Cold Neutron Facility at Texas A&M Tim Goorley Nuclear Engineering Department i

An undergraduate research project was to design, constmet and test a cold neutron beam using the NSC Beam Port No.1. The student used liquid nitrogen cooled light water as the cold source. The project involved the construction of a simpic beam chopper system and the setup of the necessary electronics. The student found that the low beam flux was hidden by the background radiation.

Other Projects and Labs using Academic Support Funds Kim, Yongie, Thomas T. Tieh, " Uranium ard Thorium in Paleo:olc Aquifers surrourding the Llano Uphft Area, Central Texas", presented at 1995 Annual Convention of the American Association of Petroleum Geologists Nuclear Engineering 405, Reactor Experiments Laboratory 19

Nuclear Engineering 402, Nuclear Detection and Isotope Technology Laboratory Chemistry 464, Nuclear Chemistry Laboratory Burrows, Ron," Characterization of Nuclear Accident Dosimeter" (Master's Thesis) 4 f

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2.3 Reactor Sharing Program 2.3.1-Introduction The University Reactor Sharing Program provides funds for reactor experimentation to those institutions which do not normally have access to a research reactor. The Nuclear Science Center (NSC) has participated in the program since 1980 with great success.

During the 1994-1995 contract year, eleven research institutions utilized the NSC with the support of the Reactor Sharing Program. Additionally, the funding provided reactor tours and " hands-on" projects to many secondary schools.

The research projects supported by the program range from geological dating to higher 4

current superconducting magnets. The funding gave small colleges and universities the i.

opportunity to use the NSC for teaching courses in nuclear processes; specifically neutron activation analysis and gamma spectroscopy. The Reactor Sharing Program supported the construction of a Fast Neutron Flux Irradiator for users at New Mexico Institute of Mining and Technology and the University of Houston. This device has been characterized and has been found to have near optimum neutron fluxes for A"/Ar" dating.

Funding this year was significantly reduced from previous years and several researchers were unable to complete research projects before all available funds were expended.

2.3.2 Summary of Projects Supported by Reactor Sharing Program "Ar/"Ar Geochronology at New Mexico Geochronology Research Laboratory

^

New Mexico Tech Dr. Matthew Heizler Department of Earth and Environmental Sciences Dr. Bill McIntosh 3

10 Graduate Students participated and 3 Undergraduate Students 20 presentations at professional meetings 4

3 dissertations and 7 theses in progress

- University Reactor Sharing Support Provided:

$ 5,314.59 i

"Ar/"Ar Geochronology at University of Houston

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i University of Houston, Department of Geosciences Dr. Peter Copeland Dr. Terry Spell

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1 Graduate Student and 1 Undergraduate Student participated 3 Presentations and 1 Thesis were the result of the work performed Thesis title:

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"Magnetostratigraphy and"ArfAr Armlysis of the Siwalik Group, Dhansar Khola, Southern Nepal: Constraining Dming of Uphft in the Greater Himalaya" University Reactor Sharing Support Provided:

$ 5,198.35 A Description of the "Ar/"Ar Dating Technique The conventional K-Ar dating technique involves the radioactive decay (half-life 1.25 Ga) of naturally occurring "K to Ar. This decay scheme is the most common'y used dating technique exploited by the geological community because of the ubiquitous occurrence of K in most geologic materials and because it is applicable to all time-scales relevant to the earth and solar system. A major drawback to the K-Ar method is the requirement to make two absolute measurements on very chemically distinct species. "Ar is measured on one aliquot using isotope dilution techniques and rare gas mass spectrometry and "K is commonly measured using flame photometry on a second aliquot. These methods limit

- the precision of the dating technique to - 1% and also provide no means to test some of the underlying assumptions required to calculate an apparent age.

In the middle 1960's it was recognized that irradiation of K bearing samples with fast

[

neutrons could facilitate the reaction "K(n,p)"r.Ar and thus potentially prov measuring K with non-naturally occurring ' A This led to the dating technique referred to as "Ar/"Ar ratio dating and has numerous advantages over the conventional K-Ar method; such as:

1.

A single analysis is conducted on one aliquot of sample thereby reducing the sample size and eliminating sample inhomogeneity.

2.

Analytical error incurred in determining absolute abundances is reduced by measuring only isotopic ratios. This also eliminates the need to know the exact weight of the sample.

3.

The addition of an argon spike is not necessary.

4.

The sample does not need to be completely fused, but rather can be incrementally heated.

5.

The "Ar/"Ar ratio (age) can be measured for each fraction of argon released and this allows for the interrogation of an age spectrum.

The age of a samp.le as determined with the "Ar/"Ar method requires comparison of the measured "Ar/"Ar ratio with that of a standard of known age. Also, several isotopes of other elements (Ca, K, Cl, Ar) produce argon isotopes during the irradiation procedure and require a correction.

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Neutron Activation Analysis of Aerosols from Antarctica Volcanoes

' New Mexico Tech, Department of Geoscience Dr. Philip Kyle 22

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l 1 Graduate Student Thesis. " Emission andDispersion ofCaseous S, Fand Cifrom Mt.

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Erebus, Antarctica" i

1 University Reactor Sharing Funding Provided:

$ 1,915.64 i

Mt. Erebus, Antarctica, provides a unique laboratory to study degassing behavior of a stable alkaline body. Sixty-four samples of the gas plume emitted from Erebus were collected on filter packs during the 1992,1993 and 1994 Austral summers. Filter packs 7

consisted of a 2 mm Teflon particulate filter followed by two LiOH-impregnated Whatman 41 filters. Filter packs were connected to a small vacuum pump at a site on the crater rim.

Filter samples were analyzed for Cl, In, and Na using neutron activatioe analysis. A method of detecting C1 and F using rapid counting techniques was perfo,med by the experimenter during a week-long stay at Texas A&M.

L Model predictions as well as trace element data from atmospheric and snow sampling clearly show that measurable amounts of Erebus gases can reach the South Pole. Based i

on current levels of activity and the absence of a mechanism responsible for transferring I

significant amounts of SO2 and Cl to the stratosphere it is unlikely that gases from Erebus -

i play a major role in ozone depletion above Antarctica.

Effects of Shearing on Trace Element Mobility s

New Mexico Tech Dr. Kent C. Condie Department of Geoscience With increasing degree of deformation and retrogression of a granitoid in the Brevard shear zone in North Carolina, Ca and LOI (H2O) are enriched, and Si, Mg, K, Na, Ba, Sr, Ta, Cs, and Th are depleted at the ultramylonite boundary. Al, Ti, Fe, P, Sc, Rb, REE, Hf, Cr, and U, however, remain unchanged. A volume loss of 44% is calculated for the Brevard ultramylonite relative to an Al-Ti-Fe isocon. The increase in Ca and LOI is related to a large increase in retrograde epidote and muscovite in the ultramylonites, the decreases in K, Na, Si, Ba, and Sr reflect the destruction of feldspars, and the decrease in Mg, the destruction of biotite during mylonitization. In an amphibolite facies fault zone separating gray and pink granitic gneisses in the Hope Valley shear zone in New England, compositional similarity suggest the ultramylonite is composed chiefly of the pink gneisses. Utilizing and Al-Ti-Fe isocon for the pink gneisses, Sc, Cr, Hf, Ta, U, Th and 1

M-HREE are relatively unchanged, Si, LOI, D, Mg, Rb, Cs, and Ba are enriched, and Ca, Na, P, Sr and LREE are lost during deformation. In contrast to the Brevard mylonite, the Hope Valley mylonite appears to have increased in volume by about 70%.

Among the element ratios most resistant to change during mylonitization in the Brevard shear zone are La/Yb, HfTra and Hf7Yb. However, until more trace element data are b

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e available from other shear zones, these ratios should not be used alone to identify protoliths ofdeformed rocks.

i Mobilization of Major and Trace Elements During Progressive Weathering of a Granodiorite in Colorado (Published in January 1995, Geochimica et Cosmochimica Acts, v. 59)

New Mexico Tech Dr. Kent C. Condie i

Department ofGeoscience s

i A weathering profile on the Boulder granodiorite in northern Colorado provides an opportunity to trace the behavior of REE from parent rock, through a weathering profile, into unconforming overlying Permian sediments. With progressive upward weathering of the granodiorite, Na20, CaO, SiO2,Ta/Hf, Co/Th, Zr/Hf, La/Sc, Zr/Y and Laffh decrease; Al O3 and Fe2O3T increase; and TiO, MgO,K 0, P205, Rb, Zr, Sc, Cr, Co, Hr, Nb, Ta, 2

2 2

Y, Th, U, REE (rare earth elements), Ti/Nb, and Zr/Nb increase to maximum values and then either level offor decrease.

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L(light)REE enrichment is less in the weathering profile than in the parent granodiorite and although the parent does not have an Eu anomaly (or only a slight positive anomaly),

all samples from the weathering profile and overlying sediments have significant negative Eu anomalies. This observation is especially important in that it shows conclusively that a negative Eu anomaly can be produced during chemical weathering of granitoids. We suggest these Eu anomalies are due to relative enrichment of the other REE and partial i

ld hi fil l

h loss of Eu during the breakdown ofplag oclase. The Bou er weat er ng pro e a so as 3

a very minor negative Ce anomaly that is within error of a Ce anomaly in the parent. In the unweathered parent, >50% of the REE are contained in sphene, and in the case of La, also in allanite. From 10 to 20% of the REE are contained in apatite and biotite, and from 7-10% of the H(heavy)REE are in zircon. With exception of Eu, for which feldspars contribute about 8%, negligible amounts of REE occur in feldspars. In weathered samples, >75% of the REE are contained in clay minerals. The crossover between sphene and clay control of REE occurs over a distance of 1 m near the contact with fresh rock.

Except for their small negative Eu anomalies, the clay minerals have REE patterns very i

similar to those of the parent rock.

Isocon plots suggest apparent enrichments of many elements in the Boulder weathering profile result from losses of Na, Ca, and Si during plagioclase weathering. In addition, variable amounts of Sr, Eu, Ta, Nb, P, and Ba were lost during weathering. Although Th/U, Zr/Y, Th/Sc, Zr/Hr, Lu/Hf, and Ti/Zr may have been transferred relatively unchanged from granodiorite parent to the bulk weathering profile, most other element ratios and REE distributions were significantly changed during weathering. This i

observation implies that caution needs to be exercised when using REE patterns and j

element ratios to trace sediment provenance.

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1 The fact that most element ratios and REE distributions also differ between Fountain sediments and the bulk weathering profile may be related to one or a combination of four j

factors, listed in order of probable decreasing importance: contribution of other sources to the Fountain sediments, sorting of minerals during sediment deposition, remobilization j

of elements during deagenesis, and leaching of elements by water flow through the upper meter of the weathering profile.

Study of Optimum Use of Columnar Pinning Centers in High T, Superconductors Institute of Beam and Particle Dynamics Dr. Roy Weinstein University of Houston Dr. Yanru Ren Dr. Jay Liu 3 Graduate Students,7 Undergraduate Students and 1 Pre-College Student were involved with this research 4 Publications,2 Presentations, and 1 MS thesis resulted from this work 1

1 Previous work:

" Effects ofHigh EnergyIrradiation ofMT Y123 on Jc, Trapped Field, Creep, and the Irreversibility Line " R. Weinstein, J. Liu, Y. Ren, I-G Chen, V. Obot, R.P. Sawh, C.

Foster, A. Crapo. Presented at International Workshop on Superconductivity, Kyoto, Japan, June 1994.

]

Reactor Sharing Support Provided:

$ 1,876.10 The Institute of Beam and Particle Dynamics (IBPD) continued to explore a unique type j

d of pinning center in the high temperature superconductor (HTS), YBa2Cu307-d(Y123).

Pinning centers are regions of poor or zero superconductivity. These regions permit the l.

presence of magnetic field, despite the Meissner Effect, and are essential to achieve high currents. The pinning centers explored are created by the fission fragments of normal thermal fission of U " The uranium (235 and some 238) was added to and dispersed 23 within the HTS. The fission fragments create a columnar damage region about 20mm long, and 50 Angstroms in diameter. These short columns are homogeneously distributed 1

in the HTS, and are randomly oriented. It is desirable to know the effects of these centers on current density (J.), critical temperature (T.), trapped field (B ) and other variables.

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Columnar defects are theoretically superior to pinning centers formed directly by proton or neutron interactions. These latter defects are very nearly point damage centers. The results of the research this past year was that the J. of Y123 was increased by a factor of 4, and exhibited an optimum value.

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90000 o

0% U Q I

80000 0

- 0.6% U Q J

70000 d

~

N E

80000 o

4 50000 o

7 40000 30000 20000 1016 1017 1018 1019 2

Fluence (neutrons /cm )

a i

Results for Jc, due to n irradiation at TAMU Reactor. The value of Jc achieved using 0.6% depleted U is the highest ever achieved in Mt Y123.

1 The activation of the samples with 0% U is consistent with the assumption that activation is due to the fast n component of the TAMU Reactor.

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An Assessment of the Viability of Energy Dispersive X-ray Fluorescence for the i

Analysis of Metals in Contaminated Soils i

A K-series Trachyte to Rhyolite Eruptive Center, Davis Mountain Volcanic Field, Texas Neutron Activation Analysis at the Sul Ross State University Analytical Laboratory Sul Ross State University Analytical Laboratory Dr. Kevin Urbanczyk Department ofGeology and Chemistry Sul Ross State University, Alpine, Texas 3 Graduate Students were involved in this work and 22 Undergraduates i -

Reactor Sharing Support Provided:

$ 5,894.00 Sul Ross State University actively used the NSC reactor to provide neutron activation of rock samples for graduate and undergraduate research projects. This past year, the radiation detection and counting equipment was out of commission at Sul Ross; therefore, e

j the NSC counted the radioactive samples at the facility and sent the results to Sul Ross for i

further analysis.

i Fission Track Thermochronology Fission Track Thermochronology Dr. Mark Cloos Department of Geological Sciences Dr. Sharon Mosher University ofTexas at Austin Dr. Earle McBride 4 Graduate Students from UT and I from University of Kansas

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Reactor Shat.;ng Support Provided

$ 766.16 Publications resulting from this work:

Boettcher, S..C, and Milliken, K.L.,1994, " Mesozoic-Cenozoic Unroofing of the Southern Appalachlan Basin: Evidencefrom Apatite Fission Track Thermochronology", Journal of Geology, v.102, in press.

Specific projectsin progress:

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" Investigation ofMesozoic Shortening ard Cretaceous-Tertiary Erumation in the Maria Foldand Thrust Belt, Southern UnitedStates Cordillera" (Ph.D. dissertation research for Stefan S. Boettcher)

" Tertiary Emplacement of the Irlan Ophioloite Belt and Unroofing of the Derwo-Rouffaer Metamorphic Belt, Irlan Jaya, Indonesia " (Ph.D. researchfor RichardJ.

Welfard)

"Three-dimensional distribution ofheat-producing elements in the southern Basin ard Range, USA " (Ph.D. researchfor Richard A. Ketcham)

" Annealing ofFission Tracks in Apatite over Geologic Timescales: Investigation of the influence ofComposition"

" Burial and Unroofing History ofMiddle Pennsylvanian Sandstonesfrom the Applachian basin in Kentucky and Virginia"

" Thermal Histories ofPiggy-Back andForeland Basins in the North Apennies, Italy, Derivedfrom Apatite Fission Track 7hermochronology"

" Investigation of Uranium Distribution in Apatitefission Track Age Standards"

" Timing and Thermal Characteristics ofSevier Belt Thrust Faulting and Synorogenic Sedimentation in the Pavant and Canyon Ranges, Central Utah " (Jonathan K. Linn, l

University ofKansas) l l

Methodology l

Fission track analysis is a geochronological method that utilizes the spontaneous fission of U-238 in uranium rich minerals such as apatite, zircon, and sphene. The spontaneous fissioning ofuranium in these minerals produces two highly ionized fission fragments whose passage through the crystal lattice leaves a linear trail of atomic defects referred to as fission tracks. The preferential etching of these tens of angstroms-wide trails of defects with respect to the bulk crystal enlarges the tracks allowing their lengths and density to be

- measured under a high powered (1000X-1500X) petrographic microscope.

Apatite is the most common mineral used in fission track thermochronology because more is known about the annealing characteristics of fission tracks in apatite than in sphene and zircon. In apatite, fission tracks are rapidly destroyed by annealing at temperatures above

~125 C. Because the spontaneous fission occurs at a statistically constant rate, the l-density of fission tracks in a mineral is a function of uranium concentration and fission track age. Fission track age is defined as the elapsed time during which tracks accumulated in the mineral. Determination of fission track ages in apatite, zircon, and sphene involves measuring: (1) the density of spontaneous (fossil) fission tracks; (2) the l

density ofinduced fission tracks in a mica external detector that is placed on top of the

- apatite grain mount and irradiated with thermal neutrons; (3) the density ofinduced fission 28-

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tracks in a standard glass (neutron fluence); and a zeta factor (z) determined from the density of fission tracks in a suitable standard. These variables, combined with the total decay constant (lo) for 2nU and the age of a standard, are used to calculate the age of the material. The irradiation of the grain mounts is performed with thermal neutrons in the NSC reactor Heavy-Water Irradiator.

Annealing of fission tracks refers to those processes that result in the repair oflattice i

defects such that the trail of defects is shortened or eliminated. Temperature is a dominant factor in fission track annealing in apatite. Fission track length distributions record

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information on the rate at which the rocks passed through the zone of partial annealing of fission tracks (50 C-125'C). As fission tracks form continuously through time with an-initial length of ~16mm, the final distribution of etchable fission track lengths in apatite contains a record of temperature variation with time below ~125 C.

In summary, fission track analysis involves both the measurement of fission track ages and track lengths. The age is a minimum estimate of the timing of the most recent cooling event in the mineral. The track length distribution provides additional information about the cooling history of a sample such as cooling rate, post-cooling thermal pulses, or post-cooling geothermal gradients.

Neutron Activation Analysis Program at the University of Texas at El Paso Reactor Sharing Support Provided

$ 2,028.15

" Geochemistry of Quaternary Lavasfrom the Chyulu Hills, Eastern Kenya "

Department of Geological Sciences Dr. Elizabeth Anthony University of Texas at El Paso Michelle Barnes 4

John Carney Peter Omenda l

Mines and Geological Dept.

John Omenge Nairobi, Kenya l

Submitted to the South-Central Geological Society of America Meeting, Lincoln, Nebraska, April 27-28,1995 Samples were collected from lavas representing seven different stratigraphic or eruptive units in the Chyulu Hills of eastern Kenya.

This volcanic field is very young, with the 1

most recent activity thought to be within the last thousand years, and is on the eastern flank of the African Rift Previous studies have shown that the lavas are olivine-physic, nepheline-normative and enriched in the light rare earth elements.

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1 The purpose of the study was to use the field knowledge of the stratigraphic position of the various units in order to understand whether crystal fractionation is an important process in this volcanic field and if so, what minerals are responsible for the geochemical trends observed. Samples were analyzed using neutron activation analysis and inductively-coupled plasma spectroscopy for the major elements. Preliminary analyses indicate that although most of the lavas are not primitive in terms of their Mg number and thus have undergone some crystal fractionation, they are not related to each other by fractionation l

but rather represent separate magmatic pulses.

i The Quaternary Western Potrillo Volcanic Field, Southern Rio Grande Rift:

"Ar/'Ar Geochronology and Geochemistry Geological Sciences Wendi J. Williams University ofTexas at El Paso Joesph G. Miller Elizabeth Y. Anthony Los Alamos National Laboratory Jane Poths Geochronology Labo'ratory William C. McIntosh New Mexico Institute of Mining and Technology The petrogenetic history of the Quaternary Potrillo volcanic field, located in the southern Rio Grande rift, has been explored. 'He surface exposure dating provides refined temporal constraints for major and trace-element geochemical modeling. The eruption history in the central and eastern parts of this field is from 140 ka t 20 ka, with episodes at approximately 20 ka intervals. Except for maare-related products, the dominantly basanitic magmas resulted from low pressure, olivine crystal fractionation. With over two hundred cones and flows, the western part of the Patrillo volcanic field is an order of magnitude greater in volume than the central and eastern complexes combined.

Geochronologic and paleomagnetic surveys suggest the West Potrillo Mountains record a much longer eruption history that the remainder of the field. There is a series of reversed polarity flows present. Due to the older nature of this western alignment, current geochronology studies emphasize high precision " Arf'Ar dating methods.

l Apatite Fission-Track Thermochronology of Southern Rocky Mountain-Rio Grande Rift-Western High Plains Provinces l

New Mexico Institute of Mining and Technology Shari A. Kelley New Mexico Bureau of Mines and Mineral Resources Charles E. Chapin 30

Apatite fission-track (AFT) thermochronology has been a useful tool in evaluating the tectonic and topographic evolution of the Southern Rocky Mountains, Rio Grande Rift, and western High Plains provinces. AFT data from the Front Range and Wet Mountains document that little differential uplia has occurred in the late Cenozoic between the Souti.crn Rocky Mountains and the High Plains in Colorado, except the southern end of the Wi t Mountains. AFT results support a model whereby the central portion of the Front Range was upliRed vertically and the eastern and western flanks of the range were thrust laterally during early Laramide compression. Only about I km of denudation occurred in the central Front Range during early Laramide deformation, while approximately 2.5 km of material was removed during late Laramide deformation and the development of the Rocky Mountain erosion surface.

Fission-track Data Indicates the Wichita Mountains of Oklahoma Were Recently Uplifted (Presented at Fall 1995 Meeting of the Geological Society of America)

Department of Geoscience Jennifer E. Winkler University ofTexas at Dallas Robert J. Stern I

Department ofGeological Science Shari A. Kelley Southern Methodist University at Dallas The Wichita Mountains are associated with a series of basement-involved uplias and associated basins within the foreland of the Ouachita orogen. The exhumation timing of l

l the Wichita Mountains is a matter of debate. Originally, erosional surfaces found on the granitic rocks of the Wichita Mountains were thought to be Permian age wave cut benches. New interpretations suggest that the grante platforms are Pliocene pediment surfaces.

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l It was found by AFT analysis that the Wichatia Mountains were uplifted in the late l

Paleozoic, during the Ouachita Orogeny, then weathered and eroded. During Mesozoic l

time, these rocks were probably covered with sediments. As a result of burial to 1-2km depth, the temperature of the rocks was elevated to 60 -90 C into a partial annealing zone and the fission track lengths were shortened. Beginning in the Late Cretaceous to Early I

Eocene time, the Mesozoic rocks were uplined and eroded. Uplia continues through Present time with brief episodic periods of tectonic stability. Modeling of thermal histories reemphasizes uplift beginning in the Late Cretaceous to Early Eocene time and continuing to Present time.

Evidence for Post-Laramide Displacement on the Picuris-Pecos Fault Department of Geosciences Shari A.Kelley New Mexico Tech 31

The middle to late Cenozoic uplia history of the Santa Fe Range portion of the southem Sangre de Cristo Mountains is anomalous with respect to other mountain ranges bordering the northern Rio Grande riR. Recent modelt that describe rift flank development call upon significant isostatic uplift of mountain blocks adjacent to the side of asymmetric half-grabens bounded by master faults with large displacement. Mountain ranges on the hinged side of half-grabens tend to have lower relief. The development of the Sandia Mountains on the east side of the east-tilted northern Albuquerque Basin is a good example of the relationship between half-graben structure and the evolution of topographic relief. It has been determined that the Santa Fe Range does not follow the expected trend.

Apatite fission-track (AFT) dating gives ages of 50 to 70 Ma determined from an age-elevation traverse on Santa Fe Baldy are among the oldest AFT ages found in mountain ranges bordering the northern Rio Grande rift. It is suggested that the modern topographic reliefin this area developed in the late Cenozoic.

In this investigation, AFT thermochronology is used to determine relative offset across the fault near the south end of the Santa Fe Range. AFT thermochronology has proven to be very useful in deciphering the cooling histories of mountain rances in the Southern Rocky Mountains. Based on this preliminary study, the Picuris-Pecos fault has accommodated some of the middle to late Cenozoic uplift and westward tilting of the Santa Fe Range.

The relative displacement across the fault is only about 400 m in the vicinity of Glorieta Baldy, but the amount of offset may vary along the strike of the fault. Other major faults within the Santa Fe Range, such as the Garcia Ranch-Borrego fault, may also be important in the evolution oflate Cenozoic reliefin this range.

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t 2.4 Commercial Activity and External Research The NSC provides services to a variety of users who have their own funding. A majority of the commercial activities are related to isotope production of radioactive tracers for support of the Texas petroleum and chemicalindustries. Another commercial activity uses the converted Thermal Column Area for the production of micropore filters that are now being used in ultra-pure water systems in the semiconductor industry. A significant amount of research at the reactor is funded by outside research grants.

The NSC has many years of experience in the production of radioisotopes and has developed several customer-specific methods for radioactive sample handling. The production of radioisotopes generally involves handling high-activity radioactive materials during unloading, therefore the staff take all possible precautions to minimize their exposures during the transfer of materials to the shipping shields.

Company or Institution User Advanced Isotope Technologies Dr. Floyd McDaniel Arco Exploration and Production Dr. Steven Bergman Technology J

Cardinal Survey Company Mr. George Newman Donelick Analytical Dr. Raymond Donelick Frac-Mate Ltd.

Mr. Cam Carlson ICI Tracerco Mr. Dave Ferguson IsoTag Specialist Incorp.

Mr. Fred Calaway Los Alamos National Lab Mr. Archie Velarde l

Lockheed Engineering Mr. David Stanley M.D. Anderson Cancer Center Mr. Tim Ochran Methodist Hospital, Houston Dr. William Cole New Mexico Tech Dr. Matthew Heizler Poretics Corporation Mr. Greg Stasny Protechnics/Spectratek Mr. Mike Brewer Texas Instruments Corp.

Dr. Joe Keenan TN Technologies Mr. Mark McCray Tracer Services Ltd.

Mr. Norman Seely Tru-Tec Mr. Chuck Winfield f

Sam Houston State University Dr. David Donnelly University of Houston Dr. Peter Copeland Zimmerman BCS Mr. Helmut Zimmerman 33

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3.0 Facility and Procedure Changes In accordance with the requirements of 10 CFR 50.59, changes to the facility and procedures were reviewed and documented. During this reporting period there were no changes that required additional safety analysis or changes to the Technical Specifications.

The following changes and experiments were implemented as not representing an unreviewed safety question and not increasing the probability of an accident previously _

analyzed in the Safety Analysis Report (SAR). No procedures contained in the SAR were changed.

3.1 Facility Modifications Replacement of Control Rod Drive System (MA-46)

A lack of replacement parts for the current rod drive system necessitated an upgraded system. The new system will use DC stepping motors for increased reliability and accuracy. The system will be controlled using modules with lower heat generation and electronic noise. The control rod run-out accident was analyzed and the new system worst-case reactivity insertion rates will always remain well below the limiting rates.

Transient Rod Drive Motor Upgrade (MA-47)

A bent motor shaft on the existing motor has caused excessive binding during Transient Rod withdrawals. A new design using a new motor and coupling system will be installed.

Rod position indication will be provided by a digital encoder signal to the control module.

Installation of Upgraded Logarithmic and Pulse Power Channels (MA-48)

- The channels were replaced with modular drawers built by Gamma-metrics. The channels contain no microprocessor circuits and were extensively tested by the vendor at other research reactor facilities. The installation included movement of the linear and logarithmic chart recorders for improved operator monitoring of reactor parameters.

Replacement of Safety Channel Drawer Multim icr (MA-49)

A lack of parts for a failed analog meter required a substitution with a more reliable and precise digital multimeter that was installed adjacent to the existing drawer.

3.2 Experiment Authorizations There were no new experiments approved by the Reactor Safety Board during this reporting period. All experiments performed were modifications of existing approved experiments and were reviewed in NSC staff meetings.

34 l

se 4.0 Reactor Maintenance and Surveillance 4.1 Scheduled Maintenance Reactor scheduled maintenance was performed twice during the reporting period. The primary shutdown maintence period was changed from the first week in January to the first week in September. This coincides with the University fiscal year and, in general, has been a period oflow reactor activity. The result was an overlap of semi-annual and annual required maintenance.

Calibrations were performed on the Fuel Element Temperature Channel, Area Radiation Monitors and the Linear, Log, and Safety Power Channels as required by the Technical Specifications.

Control rod worth, and scram time measurements were performed in January 1995 and September 1995. The worths were found to be $16.45 and $ 16.63 respectively. The difference in the worths were attributed to an increased Transient Rod worth. This is likely resulting from a change in total rod travel after an adjustment of the TR drive motor.

Rod Scram times are well within the limit of 1.2 seconds.

Control rod visual inspections were performed and all rods appeared normal. A calorimetric calibration was performed following each maintenance period. Fuel inspections were performed as required by the Technical Specification with no l

abnormalities noted.

j The cold critical reactivity worth for each reactor experiment was measured prior to full experiment approval. The most reactive fixed experiment has been found to be the Fast Flux Irradiation Device (-$1.28) due to the high boron loading.

4.2 Emergency Planning and Review The Facility Security Plan and Emergency Plan were review by the NSC staff on 2/24/95 and by fne RSB on 3/2/95. A site emergency drill involving the College Station Fire Department and the local hospitals was conducted was 8/31/95. All required external audits were completed in the reporting period.

4.3 Unscheduled Shutdowns A total of eight unscheduled shutdowns occured during 1994. Seven shutdowns were a result of a loss of facility power and another was caused by a malfunction in the new Log Power Monitor during testing.

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1 4.4 Reportable Occurences There were no reportable occurrences.

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5.0 HEALTH PHYSICS SURVEILLANCES A dedicated Health Physics group is maintained at the NSC reactor facility as an integral part of the line organization. Additional support is provided, upon request, by the TAMU Office of Radiological Safety, i

5.1 Radioactive Shipments The Health Physics's monitoring and technical support that was provided in 1995, assured minimal, hazard exposure as well as state and federal regulation compliance during sample handling, shipment of radioactive material, and normal reactor operation. During 1995, 1

there were 400 radioactive material shipments of which 72 were sent to various departments on the campus ofTexas A&M.

5.2 Personnel Monitoring l

Personnel monitoring was provided to 37 NSC employees. All radiation exposure to personnel was below the limit set forth in 10CFR20. One individual did receive greater i

than 10% of the annual maximum exposure, his exposure was 650 mrem. A total of 3.43 man-rem was recorded for 1995.

1 During 1995,2,808 visitors toured the Nuclear Science Center. Minimal exposures were measured with pocket ion chambers worn by these visitors and their tour guides.

NSC employees wore TLDs and film badges that were provided by Landauer, an accredited supplier. Landauer also provided the analysis reports of the exposure received.

5.3 Facility Monitoring Surveys of the Nuclear Science Center facilities were performed to assess radiological hazards to NSC workers. Radiation levels and sources of radioactive contamination were frequently monitored. Approximately 350 smear samples were collected and evaluated each month.

5.4 Particulate Emuent Monitoring Radioactive particulates were monitored in the central exhaust stack and summarized on a

- monthly basis. The isotopes identified by gamma analysis were Sc-46 and Ir-192. The NSC monitoring system currently does not differentiate natural radioactive materials from man-made materials. Although very small amounts of Sc and Ir were released, all activities were conservatively considered to be caused by those identified isotopes produced in the NSCR. The annual average release rate was 4.02 x 10'" mci /cc. Total activity released for 1995 was 4.74 x 10 Ci.

37

i i

The following table summarizes annual particulate effluent releases during 1995.

1995 Radioactive Particulate Release Summary Average Diluted Exhaust Total conc.*

conc.*

Volume' Release' otr Month (uci/cc)

(uci/cc)

(cc)-

(ci)

I January 8.40E-11 4.20E-13 1.01E+13 0.000849804 February 4.79E-11 2.39E-13 9.14E+12 0.000437421 March 1.74E-11 8.72E-14 1.01E+13 0.000176435 l'

Average:

4.98E-11 2.49E-13 9.79E+12 0.000487887 total:

2.90E+13 0.001101743 II April 2.80E-11 1.40E-13 9.79E+12 0.00027413 May 3.58E-11 1.79E-13 1.01E+13 0.000362178 June 1.01E-10 5.05E-13 9.79E+12 0.000988827 4

1 Average:

5.49E-11 2.75E-13 9.90E+12 0.000541712 total:

2.98E+13 0.001892718 III July 1.85E-12 9.25E-15 1.01E+13 1.87159E-05 August

< MDA

< MDA 1.01E+13

< MDA l

September 7.42E-11 3.71E-13 9.79E+12 0.000726445 Average 2.535E-11 1.27E-13 1.00E+13 0.000248387 total:

2.99E+13 0.000974832 1

IV october 4.59E-11 2.30E-13 1.01E+13 0.000464357 November 1.97E-11 9.85E-14 9.79E+12 0.00019287 December 2.65E-11 1.325E-13 1.01E+13 0.000268093 I-Average:

3.07E-11 1.54E-13 1.00E+13 0.00030844 total:

2.99E+13 0.000769403 Annual Average:

4.02E-11 2.01E-13 9.93E+12 0.000396606 total released:

1.19E+14 0.004738696 Notes:

1.

Average Release Concentration data from NSC form 805, channel 1-

" Activity Released" 2.

Diluted concentration equal to Average Release Concentration multilled by 0.005 (Technical specification 3.5.2, dilution value for release concentration at exclusion boundary) 3.

Exhaust. Volume equal to ( # days / month)*( 24 hrs / day)*(

60 min /hr)*( 8000cfm)/ 3.53E-5cfm/cc) 4.

. Total Release equal to (Average Release Concentration)*( Exhaust volume)*(1ci/ 1E6 uCi) 38

.i

=

1 5.5 Gaseous Effluents Monitoring Argon-41 is the major gaseous effluent produced and' released at the Nuclear Science Center. This effluent is monitored in the central exhaust stack. Total Argon-41 released 4

during 1995 was 26.848 Ci with an annual release rate of1.68 x 10 mci /cc (no dilution l

factors applied). Release rates are also determined using the dilution factors for the release rate at the restricted area boundary. The total amount released is determined from the undiluted release rate. These data are summarized below:

i 1995 Radioactive Gaseous Release Summary Diluted Exhaust Total Average Conc.

Conc.#

Volume' Release" Qtr Month uC1/cc)

(uci/cc)

(cc)

(C1)

I January 8.70E-08 4.35E-10 1.01E+13 0.880 February 4.17E-08 2.09E-10 9.14E+12 0.381 March 2.53E-07 1.27E-09 1.01E+13 2.560 Average:

1.27E-07 6.36E-10 9.79E+12 1.274 total:

2.93E+13 5.095 II April 1.69E-07 8.45E-10 9.79E+12 1.655 May 6.50E-08 3.25E-10 1.01E+13 0.658 June 1.55E-07 7.75E-10 9.79E+12 1.518 Average 1.30E-07 6.48E-10 9.90E+12 1.277 total:

2.97E+13 5.108 2

III July 1.08E-07 5.40E-10 1.01E+13 1.093 August 4.31E-07 2.15E-09 1.01E+13 4.360 i

september 1.24E-07 6.20E-10 9.79E+12 1.214 Averages 2.21E-07 1.11E-09 1.00E+13 2.222 3

total:

2.99E+13 8.889 IV october 1.76E-07 8.8E-10 1.01E+13 1.781 November 2.20E-07 1.1E-09 9.79E+12 2.154 December 1.86E-07 9.3E-10 1.01E+13 1.882 Averages 1.94E-07 9.7E-10 1.00E+13 1.939 total:

2.99E+13 7.756 Annual

Averages, 1.68E-07 8.40E-10 9.93E+12 1.678 total released:

1.19E+14 26.848 Notes:

1.

Average Release.Concenration data from NSC form 805, " Channel 3 Activity Released" 2.

Diluted Concentration equal to Average Release Concentration multiliedby 0.005 (Technical specification 3.5.2, dilution value for release concentration at exclusion boundary) d 39

l 0

4, 3.

Exhaust volume equal to ( # days / month)*( 24 hrs / day)*

l (60 min /hr)*( 8000cfm)/ 3.53E-5cfm/ce) 4.

Total Release equal tot (Average Release concentration)*( Ehaust volume)* (1ci/ 1E6 uC1) 5.6 Liquid Emuents Monitoring Radioactive liquid effluents are maintained in collection tanks prior to release from the confines of the Nuclear Science Center. Sample activity concentrations and isotope identifications were determined prior to each release. There were 39 releases in 1995, totaling 1.01E +09 liters, excluding dilution from the Nuclear Science Center. The total radioactivity released was 1.19E -02 Ci with an average concentration of 9.27E -11 Ci/cc.

Summaries of the release data are presented in the table below. Radioactivity concentrations for each isotope found were below the limits specified in 10CFR20, Appendix B.

Month Number of Amount Activity concentration.

Releases Released Released Released (cc)

(ci)

(ci/cc)

January 0

0.0 0.0 0.0 4

February 0

0.0 0.0 0.0

(

March 7

2.39E+08 6.25E-04 2.61E-12 Quat. Total :

7 2.39E+08 6.25E-04 2.61E-12 April 3

6.62E+07 1.03E-04 1.55E-12 I

May 0

0.0 0.0 0.0 June 8

2.22E+08 7.24E-04 3.26E-12 I

Quat. Totals :

11 2.88E+08 8.26E-04 4.81E-12 July 4

1.63E+07 5.36E-05 3.29E-12 August 5

1.48E+08 4.48E-04 3.03E-12 september 3

8.49E+07 3.15E-04 3.71E-12 j

Quat. Totals :

12 2.49E+08 8.16E-04 1.00E-11 october 5

1.06E+08 4.71E-04 4.44E-12 November 0

0.0 0.0 0.0

(.

December 4

1.29E+08 9.14E-03 7.09E-11 Quat. Totals :

9 2.35E+08 9.61E-03 7.53E-11 Annual Totals:

39 1.01E+09 1.19E-02 9.27E-11 1

40

~. _..

January February March April May June Total

1. of releases 0

0 7

3 0

8 18 i

Sc-46 0

0 5.95E-04 4.0$E-04 0

2.07E-03 0.000307 Cr-51 0

0 4.71E-04 0

0 7.93E-04 0.000126 Mn-54 0

0 2.85E 03 2.44E-04 0

2.83E 03

. 0.000592 Co 58 0

0 1.82E-04 8.00E-05 0

1.66E-04 0.000042 Co-60 0

0 1.73E 03 1.32E-04 0

1.68E-04 0.000203 I

Zn 65 0

0 1.56E-04 1.68E-05 0

2.19E-04 0.000039 Sb-124 0

0 2.18E-04 1.48E-04 0

6.24E-04 0.000099 Ir192 0

0 4.31E-05 0

0 3.69E-04 0.000041 i

Volume (cc) 0 0

2.39E+09 6.62E+08 0

2.22E+09 52720000 ActMty(Ci) 0 0

6.25E-03 1.03E 03 0

7.24E-03 0.001452 Conc.(Ci/cc) '

0 0

2.61506E-1.55589E-0 3.26126E-7.43222E-July August September October November December Total

1. of releases 1

5 3

5 0

4 18 Sc-46 4.65E 04 8.27E-04 2.60E-03 2.77E-03 0

4.14E-04 0.000707 Cr-51 0

5.51E-04 0

4.44E-04 0

7.93E-02 0.008029 Mn-54 2.47E 05 1.57E-03 3.83E-04 8.22E-04 0

3.06E-03 0.000585 4

Co-58 0

1.36E 04 0

7.05E-05 0

2.67E-04 0.000047 Co-60 2.49E-05 1.06E 03 1.53E-04 5.01E-04 0

1.62E-03 0.000335 Zn-65 0

1.89E 04 0

3.69E-05 0

1.82E-03 0.000204 Sb-124 2.10E4)5 1.45E-04 1.39E-05 6.71E-05 0

1.18E-03 0.000142 l

Ir-192 0

0 0

0 0

0 0

Volume (cc) 1.63E+08 1.48E+09 8.49E+08 1.06E+09 0

1.29E+09 48420000 Activity (Ci) 5.36E 04 4.48E 03 3.J5E-03 4.71E-03 0

9.14E-02 0.010427 Conc.(Ci/cc) 3.28834E-3.02703E-3.71025E-4.44340E-0 7.08527E-8.53217E-6.0 ENVIRONMENTAL MONITORING s

In conjunction with representatives from the State ofTexas Department of Health, a quarterly environmental survey program is conducted to insure compliance with federal regulations. This program consists of TLD monitors located at various locations on the NSC site and a background monitor located at the Brazos River,5.25 miles west of the site. The collection, analysis, and evaluation of soil, water, and milk samples are also included in the program.

6.1 Environmental Survey Samples t

41

The environmental survey samples were collected in accordance with the schedules of the cooperative surveillance program between the Texas State Department of Health and the Texas A&M University. These samples were analyzed using an intrinsic germanium detection system for isotopic identification at the NSC. A second set of samples are also analyzed by a Texas Department of Health lab for comparison to NSC results. Data collected from this analysis reflect the continued positive use of retention facilities and sample analysis for laboratory effluents prior to their release.

Summaries of the environmental survey program for 1995 are presented in the three tables below Isotopic activity is listed as reported to, or determined by, the NSC (when data from the state was unavailable.)

Envioronmental Water Samples 1995 Quarter Sample Location Concentration (mci /ml) 1st Brazos River none found 1st NSC Creek none found 2nd Brazos River none found 2nd NSC Creek none found 3rd Brazos River none found 3rd NSC Creek none found 4th Brazos River none found 4th NSC Creek none found Milk Samples 1992 Quarter Sample Location Concentration (mci /ml) ist TAMU Dairy none found 2nd TAMU Dairy none found 3rd TAMU Dairy none found 4th TAMU Dairy none found Soil Samples 1992 Quarter Sample Location Concentration (mci /ml) 1st NSC Soil 1.07 E-07 42 l

2nd NSC Soil 1.005 E-06 3rd NSC Soil none found 4th NSC Soil none found 6.2 Site Boundary Monitoring The environmental survey program measures the integrated radiation exposures at the restricted area boundaries. These measurements are made for periods of approximately 90 days, using TLDs. The dosimeters are provided and processed by Texas Department of Health, Bureau of Radiation Control, Division of Environmental Programs. The state background monitor (survey point 14)is located at a point 52.25 miles west-southwest of the facility and is generally at right angles to the prevailing southeasterly winds.

Site #

Location Average exposure Annual Rate (mR/91 day)

Exposure 1995 (mR) 2 300 fl. W of reactor building, near fence 21.8 70.0 corner 3

250 n W-SW of reactor building, on SW 28.2 123.0 chain link fence 4

200 fl NW of reactor building, on chain 24.4 83.0 link fence, near butane tank.

5 225 fl NE of reactor building, on fence 11.5 39.0 N ofdriveway 6

300 fl N-NE reactor building, near fence 25.6 80.0 corner 10 190 fl SE of reactor building, near fence 7.7 32.0 corner 11 300 fl NE of reactor building, near fence 3.8 22.0 corner 18 375 flNE ofreactor building 12.8 49.0 19 320 fl NE of reactor building 10.3 45.0 14 5.25 miles W-SW of reactor building, at 0.0 0.0 FM 60 bridge over Brazos River 43

The highest exposure point was determined to be at site #3 (123.0 mR/yr) which is at the W SW comer of the reactor building near a storage building. The material stored in this building should be moved in 1996 and the exposure should be reduced at that time. The closest off-site point ofextended occupancy is located just beyond the site boundary fence directly behind the site #10 monitoring location; the occupants of this area continue to receive only background exposure.

6.3 RADIOACTIVE WASTE Solid Waste During the 1995 year, there was no solid waste released from the NSC for disposal oSite.

7.0 Reactor Safety Board The Reactor Safety Board is responsible to the licensee for providing an independent review and audit of the the safety aspects of the NSCR. The RSB meets at least once a year to review audit reports, security and emergency plans, new experiments and modifications to the facility.

Membership (1994-1995)

Chairman:

Dr. Gary Hogg, Associate Director, TEES Members:

Dr. Marvin Adams, Professor, Nuclear Engineering Department Dr. Ted Parish, Professor Nuclear Engineering Department Dr. Robert Kenefick, Professor Physics Department Dr. Roger Koppa, Associate Professor, Industrial Engineering Department Dr. Earl Morris, Professor Veterinary Medicine-Large Animal Clinic 44 1

O-l Dr. William Dennis James, Research Chemist Chemistry Department l

Ex-Officio Members:

j Dr. Warren Reece, Director, Nuclear Science Center Mr. Sean O' Kelly, Assistant Director, Nuclear Science Center Mr. Chris Meyer, Interim Director, Radiological Safety Office Dr. John Poston, Professor and Head, Nuclear Engineering Department TEES:

Dr. Raymond Flumerfelt, Licensee l

a 4

J 4

A l

45 i

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