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in subjects: "21 Specific Nuclear Reactors And Associated Plants"  
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Reactor Operations Management Plan

Description: The K-Reactor last operated in April 1988. At that time, K-Reactor was one of three operating reactors at the Savannah River Site (SRS). Following an incident in P-Reactor in August 1988, it was decided to discontinue SRS reactor operation and conduct an extensive program to upgrade operating practices and plant hardware prior to restart of any of the reactors. The K-reactor was the first of three reactors scheduled to resume production. At the present time, it is the only reactor with planned … more
Date: December 5, 1991
Creator: Rice, P.D.
Partner: UNT Libraries Government Documents Department
open access

HIGHLY ENRICHED URANIUM BLEND DOWN PROGRAM AT THE SAVANNAH RIVER SITE PRESENT AND FUTURE

Description: The Department of Energy (DOE) and Tennessee Valley Authority (TVA) entered into an Interagency Agreement to transfer approximately 40 metric tons of highly enriched uranium (HEU) to TVA for conversion to fuel for the Browns Ferry Nuclear Power Plant. Savannah River Site (SRS) inventories included a significant amount of this material, which resulted from processing spent fuel and surplus materials. The HEU is blended with natural uranium (NU) to low enriched uranium (LEU) with a 4.95% 235U iso… more
Date: June 5, 2008
Creator: Magoulas, V; Charles Goergen, C & Ronald Oprea, R
Partner: UNT Libraries Government Documents Department
open access

Further Dosimetry Studies at Rhode Island Nuclear Science Center.

Description: The RINSC is a 2 mega-watt, light water and graphite moderated and cooled reactor that has a graphite thermal column built as a user facility for sample irradiation. Over the past decade, after the reactor conversion from a highly-enriched uranium core to a low-enriched one, flux and dose measurements and calculations had been performed in the thermal column to update the ex-core parameters and to predict the effect from in-core fuel burn-up and rearrangement. The most recent data from measurem… more
Date: May 5, 2008
Creator: Reciniello, R. N.; Holden, N. E.; Hu, J. P.; Johnson, D. G.; Meddleton, M. & Tehan, T. N.
Partner: UNT Libraries Government Documents Department
open access

Applicability of flat plate methods in determining fluid/structure interaction effects in BWR pressure suppression systems

Description: Flat plate chord tests are one experimental method used to investigate how fluid/structure interaction (FSI) effects modify the impulsive loading in nuclear reactor pressure suppression pools. This analytical study examines the applicability of using a flexible flat plate in an otherwise rigid shell to model dynamic pool wall response in a flexible shell pressure suppression torus. Bubble pressures varying by a factor of seven are used as input to two-dimensional finite-element models. Boundary… more
Date: March 5, 1979
Creator: Holman, G.S.; McCauley, E.W. & Lu, S.C.H.
Partner: UNT Libraries Government Documents Department
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Heavy Water Components Test Reactor Decommissioning - Major Component Removal

Description: The Heavy Water Components Test Reactor (HWCTR) facility (Figure 1) was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR facility is on high, well-drained ground, about 30 meters above the water table. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. It was not a defense-related facility like th… more
Date: May 5, 2010
Creator: Austin, W. & Brinkley, D.
Partner: UNT Libraries Government Documents Department
open access

MSET modeling of Crystal River-3 venturi flow meters.

Description: The analysis of archived Crystal River-3 feedwater flow data reveals a slow and steady degradation of the flow meter measurements during the 1992/1993 operating cycle. MSET can reliably estimate the true flow rate and quantify the degree of departure between the indicated signal and the true flow rate with high accuracy. The MSET computed flow rate could, in principle, be used to provide an improved estimate of the reactor power and hence avoid the revenue loss associated with derating the reac… more
Date: January 5, 1998
Creator: Bockhorst, F. K.; Gross, K. C.; Herzog, J. P. & Wegerich, S. W.
Partner: UNT Libraries Government Documents Department
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Laser ablation of concrete.

Description: Laser ablation is effective both as an analytical tool and as a means of removing surface coatings. The elemental composition of surfaces can be determined by either mass spectrometry or atomic emission spectroscopy of the atomized effluent. Paint can be removed from aircraft without damage to the underlying aluminum substrate, and environmentally damaged buildings and sculptures can be restored by ablating away deposited grime. A recent application of laser ablation is the removal of radioacti… more
Date: October 5, 1998
Creator: Savina, M.
Partner: UNT Libraries Government Documents Department
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Mechanical properties of highly irradiated 20 percent cold-worked Type 316 stainless steel

Description: Recent experiments have extended the mechanical properties data base of 20 percent cold worked 316 stainless steel to a fluence of 1.3 x 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV), the goal exposure of the Fast Flux Test Facility. Both uniaxial and biaxial tests were conducted on speciments of developmental cladding which were irradiated in the Experimental Breeder Reactor-II at temperatures ranging from 370/sup 0/C to 650/sup 0/C. Uniaxial tensile tests were conducted at strain rates ranging from 10… more
Date: April 5, 1982
Creator: Hamilton, M. L.; Cannon, N. S. & Johnson, G. D.
Partner: UNT Libraries Government Documents Department
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Gas Centrifuge Enrichment Plant Safeguards System Modeling

Description: The U.S. Department of Energy (DOE) is interested in developing tools and methods for potential U.S. use in designing and evaluating safeguards systems used in enrichment facilities. This research focuses on analyzing the effectiveness of the safeguards in protecting against the range of safeguards concerns for enrichment plants, including diversion of attractive material and unauthorized modes of use. We developed an Extend simulation model for a generic medium-sized centrifuge enrichment plan… more
Date: June 5, 2006
Creator: Elayat, H A; O'Connell, W J & Boyer, B D
Partner: UNT Libraries Government Documents Department
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Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

Description: The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous… more
Date: May 5, 2000
Creator: Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P. & Kraev, A. G.
Partner: UNT Libraries Government Documents Department
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RAMI modeling of plant systems for proposed tritium production and extraction facilities

Description: The control of life-cycle cost is a primary concern during the development, construction, operation, and decommissioning of DOE systems and facilities. An effective tool that can be used to control these costs, beginning with the design stage, is called a reliability, availability, maintainability, and inspectability analysis or, simply, RAMI for short. In 1997, RAMI technology was introduced to the Savannah River Site with applications at the conceptual design stage beginning with the Accelera… more
Date: April 5, 2000
Creator: Blanchard, A.
Partner: UNT Libraries Government Documents Department
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Developing ''SMART'' equipment and systems through collaborative NERI research and development

Description: The United States Department of Energy initiated the Nuclear Energy Research Initiative (NERI) to conduct research and development with the objectives of: (1) overcoming the principal technical obstacles to expanded nuclear energy use, (2) advancing the state of nuclear technology to maintain its competitive position in domestic and world markets, and (3) improving the performance, efficiency, reliability, and economics of nuclear energy. Fiscal Year 1999 program funding is $19 Million, with in… more
Date: June 5, 2000
Creator: Harmon, Daryl L.; Chapman, Leon D.; Golay, Michael W.; Maynard, Kenneth P. & Spencer, Joseph W.
Partner: UNT Libraries Government Documents Department
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Thermal hydraulic calculations to support increase in operating power in McClellen Nuclear Radiation Center(MNRC) TRIGA reactor.

Description: The RELAP5/Mod3.1 computer program has been used to successfully perform thermal-hydraulic analyses to support the Safety Analysis for increasing the MNRC reactor from 1.0 MW to 2.0 MW. The calculation results show the reactor to have operating margin for both the fuel temperature and critical heat flux limits. The calculated maximum fuel temperature of 705 C is well below the 750 C operating limit. The critical heat flux ratio was calculated to be 2.51.
Date: May 5, 1998
Creator: Jensen, R. T.
Partner: UNT Libraries Government Documents Department
open access

Analysis of Enriched Uranium and Weapons Plutonium Reloads for PWRs Using BRACC

Description: Comparisons of the multicycle results demonstrate that the correlation coefficients based on the CASMO3 data were implemented correctly and that the Linear Reactivity Model is acceptably accurate for missed reloads containing both uranium and weapons plutonium fuel. The expanded set of correlation coefficients make BRACC a useful tool for performing multi-cycle in-core fuel management studies of PWR cores containing weapons plutonium.
Date: June 5, 1997
Creator: Alonso, G. & Parish, T. A.
Partner: UNT Libraries Government Documents Department
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