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Confinement of airborne radioactivity. Final progress report, January-December 1978

Description: A new test method has been developed at the Savannah River Laboratory for evaluating the iodine retention capabilities of carbon used in the airborne-activity confinement system. Methyl iodide tagged with I-131 is injected into a test gas stream continuously for 5 hours with test conditions of 80/sup 0/C temperature, 95% relative humidity, and 55 feet per minute linear flow velocity. Results show that the CH/sub 3/I retention efficiency is independent of the inlet CH/sub 3/I concentration over … more
Date: February 1, 1980
Creator: A.G., Evans
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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K-Reactor Retubing Program graphite temperature study

Description: A project has been proposed and the funds allocated for the replacement of the central zone aluminum process tubes at both K Reactors with smooth bore zirconium process tubes of approximately the same outside diameter as the original tubes. Associated with this project is the problem of relieving the present graphite stack distortion in the vicinity of the process tube channels and counteracting or prereliving, at this time, the expected graphite stack distortion that, will take place over the … more
Date: December 26, 1962
Creator: Agar, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity effects of moderator voids

Description: Reactivity worths for large moderator voids similar to those produced by steaming in postulated reactor transients were measured in the Process Development Pile (PDP) reactor. The experimental results were compared to the computed void worths obtained from techniques currently used in routine safety analyses. Neutron energy spectrum measurements were used to verify a modified lattice pattern that correctly computed the measured spectrum, and consequently, improved macroscopic cross sections. In… more
Date: January 1, 1975
Creator: Ahlfeld, C.E. & Pryor, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The steam explosion potential for an unseated SRS reactor septifoil

Description: Control rods in the Savannah River Site`s K Reactor are contained within housings composed of seven channels (``septifoils``). Each septifoil is suspended from the top of the reactor and is normally seated on an upflow pin that channels coolant to the septifoil. Forced flow to the septifoil would be eliminated in the unlikely event of a septifoil unseated upon installation, i.e., if the septifoil is not aligned with its upflow pin. If this event were not detected, control rod melting and the in… more
Date: September 1, 1992
Creator: Allison, D. K.; Hyder, M. L.; Yau, W. W. F. & Smith, D. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The steam explosion potential for an unseated SRS reactor septifoil

Description: Control rods in the Savannah River Site's K Reactor are contained within housings composed of seven channels ( septifoils''). Each septifoil is suspended from the top of the reactor and is normally seated on an upflow pin that channels coolant to the septifoil. Forced flow to the septifoil would be eliminated in the unlikely event of a septifoil unseated upon installation, i.e., if the septifoil is not aligned with its upflow pin. If this event were not detected, control rod melting and the int… more
Date: January 1, 1992
Creator: Allison, D. K.; Hyder, M. L.; Yau, W. W. F. & Smith, D. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Impact of new K Area geotechnical parameters on K Reactor restart response spectra

Description: This report provides a description of a study performed to evaluate the impact of recently obtained soils parameters on the 105-K Reactor using Soil-Structure Interaction (SSI) analysis. This study includes: the frequency check of the reactor building based on the fixed base analysis; the modification of the computer model to reflect actual building properties and building frequencies; The live load impact on seismic analysis; The comparison of soil spectrum at elev. {minus}50 ft with 60% of RG… more
Date: August 1, 1991
Creator: Amin, J. A.; Chen, R. C. & Mulliken, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Impact of new K Area geotechnical parameters on K Reactor restart response spectra. Seismic Structural Engineering

Description: This report provides a description of a study performed to evaluate the impact of recently obtained soils parameters on the 105-K Reactor using Soil-Structure Interaction (SSI) analysis. This study includes: the frequency check of the reactor building based on the fixed base analysis; the modification of the computer model to reflect actual building properties and building frequencies; The live load impact on seismic analysis; The comparison of soil spectrum at elev. {minus}50 ft with 60% of RG… more
Date: August 1, 1991
Creator: Amin, J. A.; Chen, R. C. & Mulliken, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Review of Savannah River Site K Reactor inservice inspection and testing restart program

Description: Inservice inspection (ISI) and inservice testing (IST) programs are used at commercial nuclear power plants to monitor the pressure boundary integrity and operability of components in important safety-related systems. The Department of Energy (DOE) - Office of Defense Programs (DP) operates a Category A (> 20 MW thermal) production reactor at the Savannah River Site (SRS). This report represents an evaluation of the ISI and IST practices proposed for restart of SRS K Reactor as compared, where … more
Date: September 1992
Creator: Anderson, M. T.; Hartley, R. S. & Kido, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of Savannah River Site K Reactor inservice inspection and testing restart program

Description: Inservice inspection (ISI) and inservice testing (IST) programs are used at commercial nuclear power plants to monitor the pressure boundary integrity and operability of components in important safety-related systems. The Department of Energy (DOE) - Office of Defense Programs (DP) operates a Category A (> 20 MW thermal) production reactor at the Savannah River Site (SRS). This report represents an evaluation of the ISI and IST practices proposed for restart of SRS K Reactor as compared, where … more
Date: September 1, 1992
Creator: Anderson, M.T.; Hartley, R.S. & Kido, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Further code validation of Technical Specification Bases

Description: Personnel from the Applied Physics Group (APG) and from the Reactor Technology Section devised the K-14 reactor restart test program. The primary purpose of that program was to acquire data which could be used to further validate the computer codes which supported the Technical Specification Bases. The test program was highly successful and a large amount of useful data was obtained. DOE has now requested the schedule and plan for the additional code validation activities. A response to DOE was… more
Date: September 1, 1992
Creator: Apperson, C. E. & Webb, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validation of ANS-5. 1 as the decay heat standard at the Savannah River Plant

Description: The Savannah River Laboratory (SRL) is upgrading the methods used to predict the post shutdown decay heat of the Savannah River reactors by implementing procedures based on the ANS Decay Heat Power in Light Water Reactors standard. This approach takes advantage of the large volume of research used in developing the standard and establishes compatibility with the nuclear industry. To qualify the decay heat standard for use, a series of comparisons were made between detailed decay heat calculatio… more
Date: January 1, 1982
Creator: Apperson, Jr, C. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The effect of inoperative thermocouples on K reactor limits

Description: Previous operating procedures for the K reactor required management approval for continued operation if more than six monitor pin thermocouples were inoperable. Currently, there are eight inoperable thermocouples and this number is expected to increase after reactor restart. This report provides the basis and the power impact for allowing up to 20 inoperable thermocouples in the core. The SRS reactor operating limits are specified as limits on the assembly average effluent temperature, which is… more
Date: July 1, 1991
Creator: Askew, N. M. & Hardy, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The effect of inoperative thermocouples on K reactor limits

Description: Previous operating procedures for the K reactor required management approval for continued operation if more than six monitor pin thermocouples were inoperable. Currently, there are eight inoperable thermocouples and this number is expected to increase after reactor restart. This report provides the basis and the power impact for allowing up to 20 inoperable thermocouples in the core. The SRS reactor operating limits are specified as limits on the assembly average effluent temperature, which is… more
Date: July 1, 1991
Creator: Askew, N. M. & Hardy, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SRS K-Reactor PRA LOCA analyses using best-estimate methods

Description: The thermal-hydraulic system computer code RELAP5/MOD2.5 was used to investigate the response of the primary cooling system during loss-of-coolant accidents (LOCAs) at the Savannah River Site (SRS) K-Reactor. In contrast to the conservative safety analyses performed to support the restart of K-Reactor, the assumptions and boundary conditions used in the analyses described in this paper were carefully selected to reflect best-estimate values wherever possible. The results of the calculations ind… more
Date: December 1, 1992
Creator: Bailey, R. T.; Kalinich, D. A. & Chou, C. Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

SRS K-Reactor PRA LOCA analyses using best-estimate methods

Description: The thermal-hydraulic system computer code RELAP5/MOD2.5 was used to investigate the response of the primary cooling system during loss-of-coolant accidents (LOCAs) at the Savannah River Site (SRS) K-Reactor. In contrast to the conservative safety analyses performed to support the restart of K-Reactor, the assumptions and boundary conditions used in the analyses described in this paper were carefully selected to reflect best-estimate values wherever possible. The results of the calculations ind… more
Date: January 1, 1992
Creator: Bailey, R. T.; Kalinich, D. A. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Chou, C. Y. (Idaho National Engineering Lab., Idaho Falls, ID (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Evaluations of 105-K Reactor building floor slab frequencies and basemat stresses

Description: This report describes the evaluation of natural frequencies of the concrete floor slabs in the K Reactor. The evaluation of the floor frequencies at elevation 34 ft and below is required to demonstrate that the floor frequencies of the Reactor Building are sufficiently high. This will provide confidence in the interim position that the structural amplification of the vertical motion are approximately in the same order or less than the structural amplification of the horizontal motion. Consequen… more
Date: December 1, 1990
Creator: Bandyopadhyay, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluations of 105-K Reactor building floor slab frequencies and basemat stresses

Description: This report describes the evaluation of natural frequencies of the concrete floor slabs in the K Reactor. The evaluation of the floor frequencies at elevation 34 ft and below is required to demonstrate that the floor frequencies of the Reactor Building are sufficiently high. This will provide confidence in the interim position that the structural amplification of the vertical motion are approximately in the same order or less than the structural amplification of the horizontal motion. Consequen… more
Date: December 1, 1990
Creator: Bandyopadhyay, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Actuator system history of safety rod lower latch problems review of latch inspection video tapes

Description: During pre-restart testing the safety rod at position X26-YlO bound after being driven approximately two (2) feet out of the reactor. Subsequently, the rod was manually returned to it`s seated position. Inspection of the lower latch showed that the latch locking plunger button (screwed on to the bottom of the plunger shaft and retained by a pin through a hole drilled through the button and the plunger shaft) was missing. The shaft failed through the hole drilled for the retaining pin. The butto… more
Date: June 24, 1992
Creator: Banks, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Actuator system history of safety rod lower latch problems review of latch inspection video tapes

Description: During pre-restart testing the safety rod at position X26-YlO bound after being driven approximately two (2) feet out of the reactor. Subsequently, the rod was manually returned to it's seated position. Inspection of the lower latch showed that the latch locking plunger button (screwed on to the bottom of the plunger shaft and retained by a pin through a hole drilled through the button and the plunger shaft) was missing. The shaft failed through the hole drilled for the retaining pin. The butto… more
Date: June 24, 1992
Creator: Banks, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor components P-11/K-15 re-inspection standards

Description: The Mark 22 assemblies previously charged to the P Reactor as the P-11 charge, but never irradiated, are stored in borated racks in Building 105-K Assembly Area. The assemblies are stored inside aluminum cans into which they are placed and subsequently dried upon removal from the P-Reactor. This report discusses non-destructive examinations supplemented by destructive examination of a small number of these assemblies made to establish the acceptability of these assemblies for use as the K-15 ch… more
Date: August 25, 1992
Creator: Banks, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor components P-11/K-15 re-inspection standards

Description: The Mark 22 assemblies previously charged to the P Reactor as the P-11 charge, but never irradiated, are stored in borated racks in Building 105-K Assembly Area. The assemblies are stored inside aluminum cans into which they are placed and subsequently dried upon removal from the P-Reactor. This report discusses non-destructive examinations supplemented by destructive examination of a small number of these assemblies made to establish the acceptability of these assemblies for use as the K-15 ch… more
Date: August 25, 1992
Creator: Banks, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor operation environmental information document

Description: This volume is a reactor operation environmental information document for the Savannah River Plant. Topics include meteorology, surface hydrology, transport, environmental impacts, and radiation effects. 48 figs., 56 tabs. (KD)
Date: December 1, 1989
Creator: Bauer, L.R.; Hayes, D.W.; Hunter, C.H.; Marter, W.L. & Moyer, R.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of debris vacuumed from K-Reactor tank

Description: During the ultrasonic (UT) inspection of K-Reactor tank by the Equipment Engineering Section in the spring of 1990, solid material (termed debris) was seen on the bottom of the tank. When the UT inspection was complete, a specially designed underwater vacuum cleaner was used to collect the accumulation at 17 monitor pin positions. This material was sent to SRL for characterization as an action item of the Reactor Corrosion Mitigation Committee. Acquisition of this debris provided an opportunity… more
Date: January 20, 1992
Creator: Baumann, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of debris vacuumed from K-Reactor tank

Description: During the ultrasonic (UT) inspection of K-Reactor tank by the Equipment Engineering Section in the spring of 1990, solid material (termed debris) was seen on the bottom of the tank. When the UT inspection was complete, a specially designed underwater vacuum cleaner was used to collect the accumulation at 17 monitor pin positions. This material was sent to SRL for characterization as an action item of the Reactor Corrosion Mitigation Committee. Acquisition of this debris provided an opportunity… more
Date: January 20, 1992
Creator: Baumann, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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