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USE OF CEMENTITIOUS MATERIALS FOR SRS REACTOR FACILITY IN-SITU DECOMMISSIONING - 11620

Description: The United States Department of Energy (US DOE) concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., producing (reactor facilities), processing (isotope separation facilities) or storing radioactive materials. The Savannah River Site 105-P and 105-R Reactor Facility ISD requires about 250,000 cubic yards of grout to fill the below grade structure. The fills … more
Date: December 7, 2010
Creator: Langton, C.; Stefanko, D.; Serrato, M.; Blankenship, J.; Griffin, W.; Waymer, J. et al.
Partner: UNT Libraries Government Documents Department
open access

CHARACTERIZATION OF RADIOACTIVITY IN THE REACTOR VESSEL OF THE HEAVY WATER COMPONENT TEST REACTOR

Description: The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that was used to test candidate fuel designs for heavy water power reactors. The reactor operated at nominal power of 50 MW{sub th}. The reactor coolant loop operated at 1200 psig and 250 C. Two isolated test loop were designed into the reactor to provide special test conditions. Fig. 1 shows a cut-away view of the reactor. The two loops are contained in four inch diameter stainless steel piping. The HW… more
Date: June 1, 2010
Creator: Vinson, Dennis
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

Assessment of the Potential for Hydrogen Generation During Grouting Operations in the R and P Reactor Vessels

Description: The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D and D). D and D activities consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it comes in contact with the alkaline grout materials and as a result produces hydrogen gas. To address this potential deflagration/explosion hazard, the Materials Science and Technology Directorate (MS and T) … more
Date: May 24, 2010
Creator: Wiersma, B.
Partner: UNT Libraries Government Documents Department
open access

R- AND P- REACTOR VESSEL IN-SITU DECOMISSIONING VISUALIZATION

Description: The R- & P- Reactor facilities were constructed in the early 1950's in response to Cold War efforts. The mission of the facilities was to produce materials for use in the nation's nuclear weapons stockpile. R-Reactor was removed from service in 1964 when President Johnson announced a slowdown of he nuclear arms race. PReactor continued operation until 1988 until the facility was taken off-line to modernize the facility with new safeguards. Efforts to restart the reactor ended in 1990 at the end… more
Date: June 7, 2010
Creator: Vrettos, N.; Bobbitt, J. & Howard, M.
Partner: UNT Libraries Government Documents Department
open access

Assessment of the Potential for Hydrogen Generation During Deactivation and Decommissioning of Reactor Vessels at the Savannah River Site

Description: The R- and P-reactor vessels at the Savannah River Site (SRS) are being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of physically isolating and stabilizing the reactor vessel by filling it with a grout material. The reactor vessels contain aluminum alloy materials, which pose a concern in that aluminum corrodes rapidly when it comes in contact with the alkaline grout. A product of the corrosion reaction is hydrogen gas and therefore potenti… more
Date: November 10, 2010
Creator: Wiersma, B.; Serrato, M. & Langton, C.
Partner: UNT Libraries Government Documents Department
open access

UNDESIRABLE FLOW BEHAVIOR IN A PROPOSED VALIDATION DATA SET

Description: The next generation nuclear plant (NGNP), whose development is supported by the U. S. Department of Energy, will be a very high temperature reactor (VHTR). The VHTR is a single-phase helium-cooled reactor that will provide helium at up to 1000 °C. The prospect of a coolant at these temperatures circulating in the reactor vessel demands that careful analysis be performed to ensure that excessively hot spots are not created and that sufficient mixing of the coolant is obtained. Computational flui… more
Date: May 1, 2010
Creator: Johnson, Richard W.; McIlroy, Hugh M.; Johnson, Ryan C. & Christensen, Daniel P.
Partner: UNT Libraries Government Documents Department
open access

SATURATED-SUBCOOLED STRATIFIED FLOW IN HORIZONTAL PIPES

Description: Advanced light water reactor systems are designed to use passive emergency core cooling systems with horizontal pipes that provide highly subcooled water from water storage tanks or passive heat exchangers to the reactor vessel core under accident conditions. Because passive systems are driven by density gradients, the horizontal pipes often do not flow full and thus have a free surface that is exposed to saturated steam and stratified flow is present.
Date: August 1, 2010
Creator: Schultz, Richard
Partner: UNT Libraries Government Documents Department
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