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Monthly report, March 1969

Description: This document is the March 1969 monthly report for Hanford Categories C-57 and C-65. It contains information on reactor plant operation, fuel and target fabrication, technical activities, and irradation services at the Hanford Production and Irradiation reactors. The document features a discussion of the 300 area environmental control program.
Date: April 18, 1969
Partner: UNT Libraries Government Documents Department

Monthly report, January 1969

Description: This document is the January 1969 monthly report for Hanford Categories C-57 and C-65. It covers reactor plant operation, fuel and target fabrication, irradiation services, and technical activities at the Hanford C, N, and K reactors. It features an evaluation of an incident at the KW reactor.
Date: February 18, 1969
Partner: UNT Libraries Government Documents Department

Monthly report, February 1969

Description: This document is the February 1969 monthly report for Hanford Categories C-57 and C-65. It contains information on reactor plant operation, fuel and target fabrication, technical activities, and irradiation services for the Hanford Production and Irradiation reactors. The document features a discussion of the backup coolant supply systems for the B and C reactors.
Date: March 18, 1969
Partner: UNT Libraries Government Documents Department

Designing CNR, a very high thermal neutron flux facility

Description: According to a recent study (Eastman-Seitz Committee, National Academy of Science) there is a need for a new generation of steady neutron sources with a thermal neutron flux peak between 5 to 10 times 10/sup 15//cm/sup 2/ sec. Ideally the neutron source would have to operate continuously for several days (two weeks at least) with minimum time (2 to 3 days) for refueling and/or maintenance and it would also be used to irradiate materials and produce isotopes. This paper describes the preliminary design of the nuclear reactor for the proposed Center for Neutron Research (CNR). A duplication of existing designs (HFIR, (ORNL), ILL (Grenoble, France)) would imply high total power and small core life; the necessity of higher efficiencies (in terms of peak-flux-per-unit source or power) then becomes apparent. We have found analytical expressions for the efficiency in terms of a few parameters such as the volume of the source and the Fermi age and diffusion length of thermal neutrons in both the source and reflector regions. A single analytical expression can then be used for scoping the design and to intercompare radically different designs. Higher efficiencies can be achieved by reducing the volume and the moderation of a core immersed in a very low absorbing reflector; on the contrary a very long core life has a negative effect on the efficiency at beginning of life. Consequently, and after detailed calculations, we have found a candidate design with the following characteristics: core, U/sub 3/Si/sub 2/, 93% enriched, 18.1-kg /sup 235/U, metal fraction 50%, Al cladding, and 35-L volume; reflector and moderator, D/sub 2/O; efficiency at end of life (EOL) with respect to the ILL reactor, 1.29; flux at EOL, 10 x 10/sup 15//cm/sup 2/ sec (power in core 270. MW); core life, 14 days; burnup 28.4%.
Date: January 1, 1986
Creator: Difilippo, F.C.
Partner: UNT Libraries Government Documents Department

Determination of Unknown Neutron Cross Sections for the Production of Medical Isotopes

Description: Calculational assessment and experimental verification of certain neutron cross sections that are related to widely needed new medical isotopes. Experiments were performed at the Oregon State University TRIGA Reactor and the High Flux Irradiation Reactor at Oak Ridge National Laboratory.
Date: April 9, 2004
Creator: Binney, Stephen E.
Partner: UNT Libraries Government Documents Department

Work plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S and M) and as quickly and economical as possible. Implementation and completion of the deactivation project will further reduce the risks to the environment and to public safety and health. Furthermore, completion of the project will result in significant S and M cost savings in future years. The IFDP work plan defines the project schedule, the cost estimate, and the technical approach for the project. A companion document, the EFDP management plan, has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has adopted the strategy of deactivating the simple facilities first, to reduce the scope of the project and to gain experience before addressing more difficult facilities. A decision support system is being developed to identify the activities that best promote the project mission and result in the largest cost savings. This work plan will be reviewed and revised annually. Deactivation of EFDP Facilities was initiated in FY 1994 and will be completed in FY 2000. The schedule for deactivation of facilities is shown. The total cost of the project is estimated to be $51M. The costs are summarized. Upon completion of deactivation, annual S and M costs of these facilities will be reduced from the current level of $5M per year to less than $1M per year.
Date: August 1, 1995
Partner: UNT Libraries Government Documents Department

Nonlinear analysis of hydraulic buckling instability of ANS involute fuel plates

Description: The hydraulic buckling instability of the involute fuel plates and hydraulic coolant channels in the Advanced Neutron Source (ANS) uranium fission reactor is analyzed nonlinearly using the commercial ABAQUS finite element computer program for the fuel plates in conjunction with a user-written element for the two-dimensional fluid flow in the coolant channels. This methodology has been used for several purposes, including determination of the effect of the aluminum-clad plate plastic behavior and the effect of three-dimensional plate temperature distributions on hydraulic buckling. The present report concentrates on a study of the effect of hydraulic channel imperfections on buckling. The specific form of imperfection considered is an error in fluid channel thickness that is uniform within any one channel but that varies from one channel to the next. The calculated bifurcation (linear buckling) coolant velocity is about 45 m/s, whereas the present design coolant velocity is 25 m/s. At the design velocity, the calculated fluid-induced plate deflection due to the imperfection is somewhat less in magnitude and opposite in direction from the imperfection itself.
Date: March 1, 1993
Creator: Sartory, W. K.
Partner: UNT Libraries Government Documents Department

Linear plasma-based tritium production facility

Description: The concept presented here is an adaptation of a recently completed conceptual design of a compact high-fluence D-T neutron source for accelerated end-of-life testing of fusion reactor materials. Although this preliminary assessment serves to illustrate the main features of a linear plasma-based tritium breeder, it is not necessarily an optimized design. We believe that proper design choices for the breeder application will certainly reduce costs, perhaps as much as a factor of two. We also point out that Q (the ratio of fusion power produced to power input to the plasma) increases with system length and that the cost per kg of tritium decreases for longer systems with higher output. In earlier studies of linear two-component plasma systems, Q values as high as three were predicted. At this level of performance and with energy recovery, operating power requirements of the breeder could approach zero. 5 refs., 1 fig., 1 tab.
Date: February 15, 1989
Creator: Coensgen, F.H.; Futch, A.H. & Molvik, A.W.
Partner: UNT Libraries Government Documents Department

Nonlinear analysis of hydraulic buckling instability of ANS involute fuel plates

Description: The hydraulic buckling instability of the involute fuel plates and hydraulic coolant channels in the Advanced Neutron Source (ANS) uranium fission reactor is analyzed nonlinearly using the commercial ABAQUS finite element computer program for the fuel plates in conjunction with a user-written element for the two-dimensional fluid flow in the coolant channels. This methodology has been used for several purposes, including determination of the effect of the aluminum-clad plate plastic behavior and the effect of three-dimensional plate temperature distributions on hydraulic buckling. The present report concentrates on a study of the effect of hydraulic channel imperfections on buckling. The specific form of imperfection considered is an error in fluid channel thickness that is uniform within any one channel but that varies from one channel to the next. The calculated bifurcation (linear buckling) coolant velocity is about 45 m/s, whereas the present design coolant velocity is 25 m/s. At the design velocity, the calculated fluid-induced plate deflection due to the imperfection is somewhat less in magnitude and opposite in direction from the imperfection itself.
Date: March 1, 1993
Creator: Sartory, W.K.
Partner: UNT Libraries Government Documents Department

Criticality safety of the ten-well insert for the pot dissolver

Description: Nuclear safety for most fuels dissolved at SRP is ensured by some form of insert with a favorable geometry in a pot dissolver. A ten-well insert was designed which would permit an adequate charge of highly enriched U-Al alloy fuels of the MTR type. It can handle cylindrical fuel bundles up to 5 in. dia. Dependence on administrative control is reduced. 10 figures. (DLC)
Date: May 1, 1982
Creator: Forstner, J.L.
Partner: UNT Libraries Government Documents Department

Advanced Neutron Source (ANS) Project progress report, FY 1994

Description: The President`s budget request for FY 1994 included a construction project for the Advanced Neutron Source (ANS). However, the budget that emerged from the Congress did not, and so activities during this reporting period were limited to continued research and development and to advanced conceptual design. A significant effort was devoted to a study, requested by the US Department of Energy (DOE) and led by Brookhaven National Laboratory, of the performance and cost impacts of reducing the uranium fuel enrichment below the baseline design value of 93%. The study also considered alternative core designs that might mitigate those impacts. The ANS Project proposed a modified core design, with three fuel elements instead of two, that would allow operation with only 50% enriched uranium and use existing fuel technology. The performance penalty would be 15--20% loss of thermal neutron flux; the flux would still just meet the minimum design requirement set by the user community. At the time of this writing, DOE has not established an enrichment level for ANS, but two advisory committees have recommended adopting the new core design, provided the minimum flux requirements are still met.
Date: January 1, 1995
Creator: Campbell, J. H.; King-Jones, K. H.; Selby, D. L.; Harrington, R. M. & Thompson, P. B.
Partner: UNT Libraries Government Documents Department

Analysis of the KUCA MEU experiments using the ANL code system

Description: This paper provides some preliminary results on the analysis of the KUCA critical experiments using the ANL code system. Since this system was employed in the earlier neutronics calculations for the KUHFR, it is important to assess its capabilities for the KUHFR. The KUHFR has a unique core configuration which is difficult to model precisely with current diffusion theory codes. This paper also provides some results from a finite-element diffusion code (2D-FEM-KUR), which was developed in a cooperative research program between KURRI and JAERI. This code provides the capability for mockup of a complex core configuration as the KUHFR. Using the same group constants generated by the EPRI-CELL code, the results of the 2D-FEM-KUR code are compared with the finite difference diffusion code (DIF3D(2D) which is mainly employed in this analysis.
Date: January 1, 1982
Creator: Shiroya, S.; Hayashi, M.; Kanda, K.; Shibata, T.; Woodruff, W.L. & Matos, J.E.
Partner: UNT Libraries Government Documents Department

High flux isotope reactor quarterly report, July, August, and September of 1981

Description: Routine reactor operation with four end-of-cycle shutdowns and two unscheduled shutdowns resulted in an on-stream time of 91.3% for the quarter. The outer control plates and the inner control cylinder were changed and a semi-annual core component inspection was made.
Date: April 1, 1982
Creator: Corbett, B.L. & Poteet, K.H.
Partner: UNT Libraries Government Documents Department

High Flux Isotope Reactor. Quarterly report, July--September 1977

Description: Routine reactor operation with three end-of-cycle shutdowns and the completion of a fourth carried over from the previous quarter resulted in an on-stream time of 95.5 percent. The control plates were changed, and a new inner control cylinder was installed. Basic operating data for the quarter are listed.
Date: December 1, 1977
Creator: Corbett, B.L.; McCord, R.V. & Poteet, K.H.
Partner: UNT Libraries Government Documents Department

High Flux Isotope Reactor. Quarterly report, October--December 1977

Description: Routine reactor operation with four end-of-cycle shutdowns and one scheduled cycle interruption shutdown resulted in an on-stream time of 90.3 percent. A new inner control cylinder and a set of outer control plates with remotely replaced bearing brackets were installed. The semiannual core component inspection was made.
Date: March 1, 1978
Creator: Corbett, B. L.; McCord, R. V. & Poteet, K. H.
Partner: UNT Libraries Government Documents Department

Oregon State University TRIGA Reactor annual report

Description: The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included.
Date: August 31, 1979
Creator: Anderson, T.V.; Johnson, A.G.; Bennett, S.L. & Ringle, J.C.
Partner: UNT Libraries Government Documents Department

Intense steady state neutron source. The CNR reactor

Description: The Center for Neutron Research (CNR) has been proposed in response to the needs - neutron flux, spectrum, and experimental facilities - that have been identified through workshops, studies, and discussions by the neutron-scattering, isotope, and materials irradiation research communities. The CNR is a major new experimental facility consisting of a reactor-based steady state neutron source of unprecedented flux, together with extensive facilities and instruments for neutron scattering, isotope production, materials irradiation, and other areas of research.
Date: January 1, 1986
Creator: Difilippo, F.C.; Moon, R.M.; Gambill, W.R.; Moon, R.M.; Primm, R.T. III & West, C.D.
Partner: UNT Libraries Government Documents Department

Getting the most D and D ''know how'' before starting to plan your decommissioning project.

Description: Over the last 20 years, the Decommissioning Program of the ANL-East Site has successfully decommissioned numerous facilities including: three research reactors (a 100 MW BWR, a smaller 250 kW biological irradiation reactor and a 10 kW research reactor), a critical assembly, a suite of 61 plutonium gloveboxes in 9 laboratories, a fuels fabrication facility and several non-reactor (waste management and operations) facilities. In addition, extensive decontamination work was performed on 5 hot cells formerly used in a joint ANL/US Navy R&D program. Currently the D&D of the CP-5 research reactor is underway as is planning for several other future D&D projects. The CP-5 facility was also used as a test bed for the evaluation of select evolving D&D technologies to ascertain their value for use in future D&D projects.
Date: June 23, 1999
Creator: Boing, L. E.
Partner: UNT Libraries Government Documents Department

Production of transplutonium elements in the high flux isotope reactor (HFIR)

Description: The techniques described have been demonstrated to be adequate to predict the contents of transplutonium element production targets which have been irradiated in the HFIR. The deviations, at least for isotopes of mass 253 or less, are generally within the usual analytical uncertainties, or else are for isiotopes which are of little overall import to the program. Work is especially needed to get a better picture of the production of /sup 250/Cm, /sup 254/Es, /sup 255/Es, and ultimately /sup 257/Fm, since researchers are frequently stating their interest in obtaining larger quantities of these rare and difficult-to-produce nuclides.
Date: January 1, 1980
Creator: Bigelow, J.E.; Corbett, B.L.; King, L.J.; McGuire, S.C. & Sims, T.M.
Partner: UNT Libraries Government Documents Department

High Flux Isotope Reactor. Quarterly report, October, November, and December 1979

Description: Routine reactor operation with four end-of-cycle shutdowns and one scheduled midcycle shutdown resulted in an on-stream time of 93.6% for the quarter. This gave the HFIR an on-stream time for the year of 91.3%. The outer control plates were replaced, and the annual core components inspection was made.
Date: August 1, 1980
Creator: Corbett, B.L. & Poteet, K.H.
Partner: UNT Libraries Government Documents Department