ML20214W702

Requests Exemption from Conversion from Highly Enriched U (HEU) Fuel.Special Design of Reactor Core Could Not Perform Intended Function W/O Using HEU Fuel

ML20214W702
Person / Time
Site:	University of Missouri-Columbia
Issue date:	09/26/1986
From:	Brugger R, Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8610030184
Download: ML20214W702 (10)

Text

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Research Reactor Facility UNIVERSITY OF MISSOURI September 26, 1986 Research Park Colurnbia. Missouri 65211 lelephone (314) 882-4211 Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

REFERENCE:

Docket 50-186 University of Missouri Research Reactor License R-103

SUBJECT:

Application for exemption from conversion from HEU fuel.

The University of Missouri requests a determination be made that the liniversity of Missouri Research Reactor (MURR) has a unique purpose as defined in 10CFR50.2 and is therefore exempt from conversion from HEU fuel. To support this request, a de-scription is given of some of the research programs that promote and enhance the health and safety of the general public. In reviewing these programs, it can be seen that the high neutron flux and fluence of MURR is essential to these programs and the benefit to the general public is very dependent on it. The program description is followed by a brief reactor physics explanation of the need to maintain or increase the current 235U loading in the fuel elements which is not possible with the current-ly available LEU fuels.

I. Program Description The University of Missouri Research Reactor has assumed a leadership role among university research reactors during its twenty years of operation. This is due in part to being the highest flux, highest steady state power university-owned reactor. It is due also to having aggressively promoted a healthy mix of research, education and service in order to fulfill the research reactor's char-ter to conduct the diverse and widespread research and development activities specified in Section 31 and Section 104c. of the Atomic Energy Act.

The University of Missouri Research Reactor supports a broad range of nationally and internationally significant research programs in the areas of neutron scat-tering, neutron activation analysis, radioisotope applications, radiation effects and radiography.

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I September 26, 1986 Page 2 MURR provides services to over 50 universities, over 20 Federal Agencies and over 70 industries (see Appendix A). In addition it provides a valuable resource for the international scientific community (see Appendix B). These services in-clude providing radioisotopes for both medical and industrial research and ap-plications; and participating in collaborative research projects in, but not limited to, the research areas listed above.

Some specific examples of significant research programs at MURR are: l A. Neutron Scattering Neutron scattering research permits investigation of the properties of condensed matter systems (liquids and solids). These systems comprise a broad range of materials - solids, liquids, polymers, alloys and organics.

Thermal neutrons as an investigative tool have the energy and wavelength needed to obtain maximum information about positions as well as motions of atoms. Neutrons are also best suited to investigate magnetic properties of materials since neutron and electron magnetic moments interact. This makes neutron scattering a valuable tool for many disciplines - physics, chemis-try, biology and materials science.

At MURR, there are four beam ports dedicated to neutron scattering in-vestigations. The investigation techniques available include small angle neutron scattering, diffractometry, inelastic scattering and interferometry.

Small angle neutron scattering (SANS) is a method used to investigate the inhomogeneities with dimensions of 10-1000 A in a wide variety of materials.

Because of the significantly different scattering power of hydrogen and its heavy isotope deuterium, SANS provides unique information about the structure of polymers and of biological systems where selective deuteration is pos-sible. The high penetration and large beam sizes leads to better sampling than is normally possible with microscopy, with far greater ease. The high penetration has also made it a method of choice in many metallurgical in-vestigations.

Neutron diffraction gives information about the regular arrangements of atoms in solids (crystalline and amorphous) and in liquids. New analysis methods have allowed refinement and even solution of unknown crystal struc-ture. MURR researchers recently determined the crystal structure of Nd2 Fel4B , a powerful new magnet material discovered by General Motors.

Diffraction also allows investigation of stress and texture in engineering materials and has recently been applied to such systems as a 2350 target for Argonne National Laboratory and reactor pressure head bolts for Westinghouse Bettis Laboratory.

Inelastic scattering allows the forces acting between atoms to be in-vestigated and to be related to the physical behavior of the systems (magnetic order, phase transitions, etc.). Recent studies involve such materials as V23 0 , Fe304 and others.

Neutron interferometry is one of the newest developments in thermal neu-tron scattering research. Its particular importance is in making the phase of the neutron wave function directly accessible to experiment, whereas

Director September 26, 1986 Page 3 conventional thermal neutron techniques are sensitive to only the amplitude of ,

scattered waves. A wide variety of experiments have been carried out at MURR dealing with fundamental quantum mechanical phenomena. These experiments in-clude measuring the effect of gravity on a neutron, precise measurement of the scattering amplitude of 2350 at various neutron energies and the direct measurement of the longitudinal coherence length of a thermal neutron beam.

Each of these scattering experiments depends on the highest possible flux and the longest feasible operating schedule. These attributes have  ;

allowed MURR to assemble the strongest neutron scattering program at any university reactor.

B. Neutron Activation Analysis Neutron Activation Analysis is a powerful analytical technique based on the interaction of neutrons with the isotopes of elements. Through neutron induced reactions, radioactive isotopes are produced when samples are irradi-  ;

ated in a neutron flux. The radioactivity from the subsequent decay of the l activated elements is a unique and highly sensitive fingerprint allowing the determination of many of a sample's constituent elements. Neutron Acti-vation Analysis depends on high flux to achieve the sensitivity required in  ;

measuring trace elements in, often, very small samples.

One internationally significant application of NAA at MURR involves testing the hypothesis designed by Harvard University, that an increased risk of certain types of cancer can be correlated with below normal intake of se-lenium. Efforts ara aimed at identifying geographic regions of populations at risk due to selenium deficiency.

The link between trace element concentration and other diseases are also being explored at MURR. These epidemiological studies are done in collabora-tion with several of the most respected medical facilities in the world, in-cluding Johns Hopkins University and Harvard Medical School.

C. Radioisotope Applications Radiotherapeutic application of reactor isotopes has existed for nearly forty years and appears today on the brink of a great expansion using beta-emitters coupled to tumor-selective chemical and biological agents such as monoclonal antibodies. In addition, radioisotope tracers produced by re-actors continue to find massive application in basic biological studies of physiology and disease.

The University of Missouri Research Reactor has participated for many years in this development by supplying the most widely used diagnostic radioisotope precursor, Mo-99, and by actively developing and supplying new radioisotope generator designs. These new gel generator designs for the Mo-99/Tc-99m and Sn-113/In-113m systems are uniquely suitable for efficient, inexpensive production of medical generators and for their widespread dis-tribution in large, developing countries such as China. In addition, MURR produces isotopes for the quantitation of osteoporosis (calcium loss in bone) and for basic studies of the cause and treatment of hypertension and cystic fibrosis.

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Director September 26, 1986 Page 4 Currently at least seven different reactor-produced isotopes are under l' investigation at MURR for such varied uses as the treatment of metastatic liver cancer using Y-90 microspheres, therapy to palliate the pain of bone cancer, radiotherapy of tumors using labeled antibodies, and radiation treat-ment of rheumatoid arthritis. Two of these radiotherapeutic drugs have been submitted to the FDA for Investigational New Drug exemptions to permit human trials, and a third is nearing that stage, with the rest at earlier stages of active development. The use of reactor-produced beta-emitters for radio-therapy is on the verge of a great expansion in which MURR will play an important role.

Radioisotope production requires the highest possible flux in order to provide the high specific activities required for medical research and therapeutics.

II. Arguments supporting MURR's request for a Unique Purpose Exemption.  ;

Although MURR would have a strong case in basing its unique purpose argument on its nationally significant research programs, the most relevant argument re-lates to purpose number 4 of the unique purpose definition. MURR has "a reactor core of special design that could not perform its intended function without using HEU fuel".

The MURR core is the most compact of any university reactor. Its design is characterized by high neutron leakage, to enhance beam currents, and low excess reactivity. The typical core in the fuel cycle starts with 580 MWD of burnup which corresponds to 5470 grams of 235 0 , and just barely provides enough reac-tivity to override equilibrium Xenon and operate at 10 MW for about six days.

The highest uranium density LEU fuel (20% enrichment) that is currently available, U3Si2-Al with 4.8 g U/cm 3, cannot provide the present 2350 core con-tent. Such fuel has a density of 0.96 g 235 0 /cm3, and in a typical core with 580 MWD of burnup would give only 3445 g of 2350. This is 2025 g less than needed, not even considering the reactivity loss due to increased 2380 in LEU.

MURR's operating schedule typically involves one weekly refueling and six '

days running at 10 MW. MURR is scheduled to operate 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per week, and has maintained this for eight years. It cannot use cores with fewer MWD's on them and still reach the allowed burnup per element which corresponds to an average burnup of 24%. MURR cannot lower the amount of 235U and maintain its current operating cycle. It is run in an absolutely optimum mode, regarding fuel utilization.

MURR's extensive research and service are a function of high neutron fluence (high power level and continuity of the operating schedule). All of .

MURR's most advanced experiments require the highest possible flux and oper- I ating time if the work is to be feasible. High flux reduces the time required i to complete experiments and in many cases, simply makes possible work that '

Director September 26, 1986 Page 5 could not be done at lower flux. High flux provides the high specific activi- l ties of isotopes required for Radioisotope Applications and for greater sensi-tivity in Neutron Activation Analysis.

The reactor at MURR was designed and is operated to take maximum advantage of the unique characteristics of HEU fuel. The design of the MURR will not ac-commodate the use of the currently available LEU fuel. It is designed to use as high a 2350 loading density as possible. In the twenty years that MURR has been operating, there has been a continuous effort to reduce the amount of 235U needed per MWD of energy produced. The initial core in 1966 was a uranium alu-minum alloy core loaded as high as technically achievable then - 1.3 gm-Uranium /

cm3 . This required 9.28 gm 2350 per MWD of energy produced. In 1970, MURR j

submitted a new fuel design utilizing as high a 23N loading as possible with aluminide UAlx fuel for Nuclear Regulatory Commission approval. With the Nuc-i lear Regulatory Commission's approval, this fuel was first used in 1971, de-creasing the required 2350 to 7.75 gm per MWD. MURR had a fuel element from the first aluminide core destructively analyzed to determine peak fission density.

Based on this analysis the burnup limit was extended in 1975 from 100 MWD /

element to 150 MWD / element resulting in the required 235U decreasing to 5.17 gm/ MWD. The University of Missouri, cooperating with the Department of Energy, provided financial support to a program started in 1980 to demonstrate that aluminide UAlx fuels were capable of higher uranium loadings and burnups (Extended Life Aluminide Fuel - the ELAF program). Citing the final report of the ELAF program, the University of Missouri submitted for Nuclear Regulatory Commission approval a new aluminide UA1x fuel design on September 12, 1986.

This will reduce the 2350 required in the fuel cycle to 4.23 gm/ MWD.

Additionally, the current HEU fuel with 1.55 gm-U/cm3 limits the research programs MURR can undertake. MURR has, for the past 15 months, researched upgrading the power of the research reactor, along with the addition of a cold neutron source, to further establish MURR's continuing efforts to enhance its research programs.

To this end, MURR submitted the license request for a new upgraded fuel element design. This fuel also takes advantage of the maximum 23N loading possible, with high fissions /cm3 burnup, to allow for higher power and to re-duce the fuel cycle cost. The new fuel design will allow MURR to participate in research programs not feasible previously.

MURR's fuel analysis showed that one advantage of higher 235U loadings per fuel element is a reduction in HEU fuel in cycle. The usable 2350 in the i

fuel cycle is the excess grams in the fuel element greater than the amount required to be critical with equilibrium xenon and control rods out of the

, core. For a given annual operating cycle, the number of grams of 2350 burned up is nearly independent of the enrichment, however, the ratio of total 235U needed in the core per usable 2350 increases as the enrichment decreases for a given uranium density. Therefore with higher 2350 loading 5(e.g. highly enriched and high density uranium) the total kilograms of 2 0 in the fuel

Director September 26, 1986 Page 6 cycle goes down. The decrease shows up in a lower amount of HEU needed at the reactor at any one time and a decrease in the total number of kilograms of HEU shipped to and from the reactor. With this approach the goal of reducing the risk of diversion of HEU can be achieved with a net fuel cycle savings instead of increased cost.

The MURR reactor and the research programs it supports are so special that it must be exempt from converting from its present HEU fuel if MURR is to con-tinue its efforts and assist the Nuclear Regulatory Commission in its purpose of " conducting, assisting and fostering research and development in order to encourage maximum scientific and industrial progress;" (Sec. 3, Atomic Energy Act).

Sincerely.

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Walt A. Meyer, J Acting Reactor Manager Attachments: Appendix A Appendix B l ],

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Endorsement: /

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Y APPENDIX A i OTHER EDUCATIONAL INSTITUTIONS SUPPORTED BY MURR July 1985/ June 1986 ARIZONA STATE UNIVERSITY NEW MEXICO INSTITUTE OF MINING & TECHNOLOY BOSTON UNIVERSITY NORTHWESTERN UNIVERSITY BRIGHAM YOUNG UNIVERSITY OLD DOMINION UNIVERSITY l CALIFORNIA INSTITUTE OF TECHNOLOGY OREGON STATE UNIVERSITY ,

! COLUMBIA COLLEGE PRINCETON UNIVERSITY l ECN, PETTEN, THE NETHERLANDS PURDUE UNIVERSITY HAMES CLINIC - HDFP SOUTHERN METHODIST UNIVERSITY HARVARD UNIVERSITY STEPHENS COLLEGE l

GEORGE WASHINGTON UNIVERSITY TEXAS A&M UNIVERSITY GEORGIA INSTITUTE OF TECHNOLOGY TULANE UNIVERSITY j

INDIANA STATE UNIVERSITY UNIVERSITY OF ARIZONA j INDIANA UNIVERSITY UNIVERSITY OF ARKANSAS IOWA STATE UNIVERSITY UNIVERSITY OF CALIFORNIA-LOS ANGELES

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JAPAN-HAWAII CANCER CENTER UNIVERSITY OF CALIFORNIA-SANTA BARBARA

JOHNS HOPKINS UNIVERSITY UNIVERSITY OF CALIFORNIA-SAN DIEGO I LINCOLN UNIVERSITY UNIVERSITY OF CHICAG0 i MASSACHUSETTS INSTITUTE OF TECHNOLOGY UNIVERSITY OF CINCINNATI MISSISSIPPI STATE UNIVERSITY UNIVERSITY OF ILLIN0IS l WATIONAL UNIVERSITY OF MEXIC0 UNIVERSITY OF IOWA NEELY RESEARCH CENTER UNIVERSITY OF KENTUCKY WEW MEXICO INSTITUTE OF MINING & TECHNOLOGY UNIVERSITY OF MARYLAND NORTHWESTERN UNIVERSITY UNIVERSITY OF MICHIGAN

! OLD DOMINION UNIVERSITY UNIVERSITY OF NORTH CAROLINA-CHAPEL HILL i

0REGON STATE UNIVERSITY UNIVERSITY OF PENNSYLVANIA PRINCETON UNIVERSITY UNIVERSITY OF TENNESSEE MISSISSIPPI STATE UNIVERSITY UNIVERSITY OF TEXAS-M.D. ANDERSON HOSPITAL NATIONAL UNIVERSITY OF MEXICO UNIVERSITY OF WASHINGTON l NEELY RESEARCH CENTER WASHINGTON UNIVERSITY i

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l STATE AND FEDERAL AGENCIES SUPPORTED BY MURR July 1985/ June 1986 ARGONNE NATIONAL LABORATORY NATIONAL INSTITilTES OF HEALTH COLUMBIA NATIONAL FISHERY RESEARCH LABORATORY SANDIA NATIONAL LABORATORIES FRED HUTCHINSON CANCER RESEARCH CENTER US ARMY HARRY S. TRUMAN VETERANS ADMINISTRATION HOSPITAL US DEPARTMENT OF AGRICULTURE IDAHO NATIONAL ENGINEERING LABORATORY US DEPARTMENT OF COMMERCE LAWRENCE BERKELEY LABORATORY US DEPARTMENT OF ENERGY LOS ALAMOS NATIONAL LABORATORY US DEPARTMENT OF INTERIOR MISSOURI DEPARTMENT OF NATURAL RESOURCES US ENVIRONMENTAL PROTECTION AGENCY NATIONAL CANCER INSTITUTE US NAVY NATIONAL BUREAU OF STANDARDS WRIGHT PATTERSON AIR FORCE LABORATORY NATIONAL HEART, LUNG AND BLOOD INSTITUTE l

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INDUSTRIES SUPPORTED BY MURR July 1985/ June 1986 ALLIED AER0 SPACE CORPORATION-KANSAS CITY ICN RADI0 CHEMICALS ALPHA OMEGA SERVICES INTEL CORPORATION AMERICAN DENTAL ASSOCIATION IS0 TOPE PRODUCTS AMERSHAM CORPORATION J0EL DJAHJAH ATOMIC ENERGY OF CANADA, LIMITED J. T. BAKER COMPANY AT&T BELL LABORATORIES KOMATSU ELECTRONIC METALS AUSTRALIAN DEPARTMENT OF AGRICULTURE LIXI, INC.

BLOCK DRUG CORPORATION LEVER BROTHERS COMPANY CAROLINA POWER & LIGHT LOCKHEED COMPANY, INC.

CINCINNATI MILICRON McDONNELL DOUGLAS CORPORATION C0X MIDWEST RESEARCH INSTITUTE DELC0 MINERALS SCIENCE TECHNOLOGY DOMTAR, INC. MISSOURI ANALYTICAL LABORATORIES DOW CHEMICAL COMPANY MONSANTO COMPANY E. I. DUPONT-NEN PRODUCTS NEW ENGLAND NUCLEAR E. I. DUPONT NUCLEAR DATA, INC.

! EXXON NUCLEAR MEDICINE, INC.

GAMMA INDUSTRIES NUCLEAR SOURCES & SERVICES, INC.

GEARHART INDUSTRIES 0. J. CRYSTALS GENERAL MOTORS COMPANY NUCLEPORE CORPORATION GROW COMPANY, INC. OLIN BRASS GULF RESEARCH AND DEVELOPMENT ORTEC HARRIS CORPORATION PACIFIC G/.S & ELECTRIC COMPANY HEWLETT PACKARD PETR0 LITE CORPORATION HONEYWELL RADS INCORPORATED HUGHES AIRCRAFT RADIATION SAFETY AND NUCLEAR PRODUCTS, INC.

IBF ROCKWELL-COLLINS INTERNATIONAL CORPORATION SCIENCE APPLICATIONS, INC. TOPSIL SEMTECH CORPORATION UNION CARBIDE SEQUOYAH NUCLEAR PLANT UNITRODE CORPORATION SOURCE PRODUCTION AND EQUIPMENT COMPANY UNIVERSAL TECHNOLOGY CORPORATION ST. PATRICK HOSPITAL VIRGINIA ELECTRIC POWER COMPANY STANDARD OIL OF OHIO (S0HIO) WESTINGH0USE ELECTRIC TECHNICAL OPERATIONS WIL LABORATORY TEXAS INSTRUMENTS, INC. ZION NUCLEAR PLANT A-3

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APPENDIX B INTERNATIONAL INSTITUTIONS SUPPORTED BY MURR July 1985/ June 1986 JOINT RESEARCH CENTER - PETTEN, THE NETHERLANDS CNRS, GREN0BLE - FRANCE TECHNION, ISRAEL INSTITUTE OF TECHNOLOGY ATOMIC ENERGY RESEARCH ESTABLISHMENT - HARWELL, ENGLAND UNIVERSITY OF MELBOURNE REACTOR OPERATIONS INSTITUTE - PEOPLES REPUBLIC 0F CHINA TECHNICAL UNIVERSITY OF DENMARK INSTITUTE OF OCCUPATIONAL HEALTH - NORWAY UNIVERSITY OF OTAGO - NEW ZEALAND UNIVERSITE D' AIX-MARSIELLE, PHYSICS DEPARTMENT INSTITUTE OF ATOMIC ENERGY - PEOPLES REPUBLIC 0F CHINA STUDSVIK - SWEDEN TECHNICAL UNIVERSITY - BERLIN HAHN MEITNER INSTITUTE - BERLIN ECOLE POLYTECHNIQUE - MONTREAL, CANADA l

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