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Research and Innovation in the Building Regulatory Process

Description: Report issued by the U.S. National Bureau of Standards discussing studies conducted on building codes, standards, and regulations. The report includes transcripts from the 12th annual National Conference of States on Building Codes and Standards. This report includes tables, and illustrations.
Date: June 1980
Creator: Berry, Sandra A.
Partner: UNT Libraries Government Documents Department

[Horse full side]

Description: Photograph of horse taken from full profile. The horse is standing in short grass and there is a wooden fence in the background.
Date: June 23, 1986
Creator: Shugart, Don
Partner: UNT Libraries Special Collections

Informacion Ambiental y Ecologica Sobre los Llanos del Rio Orinoco: Proyecto Orinoco-Apure: Secciones 1 y 2

Description: This report includes sections one and two of a study of the Llanos del Rio Orinoco. The aim of this study is to establish relationships between the characteristics of plant communities of the Central Plains of Venezuela and geomorfogenetica and pedogenic evolution during the Quaternary.
Date: June 1985
Creator: Acevedo, Miguel F.; Silva, Juan F. & Raventós, José
Partner: UNT College of Engineering

Informacion Ambiental y Ecologica Sobre los Llanos del Rio Orinoco: Proyecto Orinoco-Apure: Seccion 3

Description: This report is section three of a study of the Llanos del Rio Orinoco. The aim of the study is to establish relationships between the characteristics of plant communities of the Central Plains of Venezuela and geomorfogenetica and pedogenic evolution during the Quaternary.
Date: June 1985
Creator: Acevedo, Miguel F.; Silva, Juan F. & Raventós, José
Partner: UNT College of Engineering

Circulating water subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: The Circulating Water System is a subsystem within the Heat Rejection Group (HRG). The Circulating Water System consists of two independent loops to remove waste heat from the turbine building closed cooling water system and from the condensers associated with each turbine generator set. In normal plant operation circulating water is pumped from the cooling tower basin through the condensers and heat exchangers and back to the cooling tower where the waste heat is released to the atmosphere via mechanical draft cooling towers. The system consists of two flow paths with two half-size, vertical pumps associated with each path.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Chloride content of Rocky Flats scrub alloy eleventh campaign solution following head end treatment

Description: A single batch of dissolver solution from the eleventh Rocky Flats Scrub Alloy (RFSA) campaign has been analyzed for chloride content following head end treatment to reduce its concentration. Scrub alloy buttons were dissolved in Tank 6.4D during May. In subsequent head end processing, chloride was precipitated with mercurous ion added as the nitrate. The precipitate, Hg{sub 2}Cl{sub 2}, was concurrently removed with the gelatin floc via centrifugation. Duplicate samples from Tank 11.2, containing the head end product, produced excellent agreement between their density measurements, acid analyses, and gross alpha activities, indicating them to be truly representative of the tank`s contents. Duplicate aliquots from each of these solutions were analyzed using the turbidimetric chloride method developed in the Separations Technology Laboratory. These resulted in an average chloride value of 41 ppm ({micro}g/mL) chloride for the head end product. Relative standard deviation of the measurement was {+-}4 ppm (n = 4), a precision of {+-}10%. Such a variance is normal at this low chloride level. Since initial chloride values prior to head end averaged 1455 ppm (0.041M), as analyzed by Laboratories Department, a chloride DF of approximately 35 was obtained. Such a reduced chloride level (to less than 100 ppm) in the treated solution will permit further canyon processing with minimal corrosion.
Date: June 30, 1988
Creator: Holcomb, H. P.
Partner: UNT Libraries Government Documents Department

MCNP photon transport benchmarking calculations performed at SRP. Revision 1

Description: Monte Carlo methods have long been used at the Savannah River Laboratory (SRL) to perform criticality calculations for many different processes. To perform transport analyses (both neutron and photon) a two-dimensional infinite lattice integral transport code (GLASS) has been used. The neutron transport portion of the code has been benchmarked against other codes and experimental data. The photon transport portion of the code, which is used to calculate gamma redistribution in the event of a loss of moderator and/or coolant, had not been benchmarked against either. For this reason, the Monte Carlo code MCNP was used to benchmark the photon transport portion of the GLASS code. Preceding this, a brief description of the geometry of the Savannah River Plant`s (SRP) reactor cores and how they were modeled using MCNP will be given.
Date: 1989-06~
Creator: White, A. M.
Partner: UNT Libraries Government Documents Department

Makeup water treatment and auxiliary boiler building structural design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: The Makeup Water Treatment and Auxiliary Boiler Building (MWABB) is a grade-founded, single-story, steel-framed structure with insulated sheet metal exterior walls and roof decking. It houses the electrically-heated auxiliary boiler and related equipment, and the Raw Water Treatment System. The Makeup Water Treatment and Auxiliary Boiler building is located adjacent to the Maintenance Building in the Energy Conversion Area of the plant.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Negative transverse impedance

Description: Recently, measurements in the SPS show that the coherent tune shift in the horizontal direction has positive values whereas that in the vertical direction has negative ones. Thus the existence of negative transverse impedance gets confirmed in a real machine. This stimulates us to start a new round of systematic studies on this interesting phenomenon. The results obtained from our computer simulations are presented in this note. Our simulations demonstrate that the negative transverse impedance may appear when the rotational symmetry embedded in a discontinuity is broken, and that the geometries that we have studies may be the source of the positive horizontal tune shift measured in the SPS.
Date: June 12, 1989
Creator: Chou, W.
Partner: UNT Libraries Government Documents Department

A study of eddy current measurement (1986-1987)

Description: A study was conducted in 1986 to evaluate a modified eddy current system for measuring copper thickness on Kapton. Results showed a measurement error of 0.42 {mu}in. for a thickness range of 165 to 170 {mu}in. and a measurement variability of 3.2 {mu}in.
Date: June 22, 1989
Creator: Ramachandran, R.S. & Armstrong, K.P.
Partner: UNT Libraries Government Documents Department

Liquid radioactive waste subsystem design description

Description: The Liquid Radioactive Waste Subsystem provides a reliable system to safely control liquid waste radiation and to collect, process, and dispose of all radioactive liquid waste without impairing plant operation. Liquid waste is stored in radwaste receiver tanks and is processed through demineralizers and temporarily stored in test tanks prior to sampling and discharge. Radwastes unsuitable for discharge are transferred to the Solid Radwaste System.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Class 1E dc power subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: The Class 1E DC Power System of the Electrical Group provides reliable and regulated 125 V dc electric power to the plant safety-related dc loads connected to the Four redundant and independent 125 V dc Class 1E buses to ensure plant safe shutdown or mitigate the effects of a design basis event. These four dc buses comprise the plant four Class 1E dc control and instrument channels (A, B, C and D).
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Performance criteria testing

Description: Savannah River Plant (SRP) has initiated an aggressive program aimed at improving their shipper/receiver (S/R) posture. The site is routinely involved in 800 nuclear material transfers/year. This many transactions between facilities provides many opportunities for resolving S/R differences. Resolution of S/R differences requires considerable effort from both DOE offices and contractors, presents legitimate safeguards concerns if the receiving quantity is less than the quantity shipped, and must be resolved for shipments to continue. This paper will discuss the programs in place at SRP to improve their position versus shipments and receipts of nuclear materials including: S/R agreements, which provide a method of communicating between the shipping and receiving facility and protects both facilities by eliminating misunderstandings; nondestructive assay (NDA) instrumentation, which allows the facility to obtain an accountability quality value for receipt before the material is processed; more accurate and precise analytical techniques in use wherever SRP does not have the capability to measure a shipment or receipt by NDA; S/R values are graphed to identify trends and/or biases that may not have exceeded any error limits; and the central Material Control and Accountability (MC and A) division has become more involved in analyzing the data from shipments and receipts including the calculation of limits of error (LOE`s), instrument biases, and analyzing trends.
Date: 1988-06~
Creator: Davis, F. B.
Partner: UNT Libraries Government Documents Department

Predicted discharge plutonium isotopics for LEU [low-enriched uranium] test pebble irradiated in the AVR [Arbeitsgemeinschaft Versuchsreaktor]

Description: A Subprogram Plan related to the Arbeitsgemeinschaft Versuchsreaktor (AVR) Test Program is in place and describes cooperative work being carried out under the United States/Federal Republic of Germany (US/FRG) Implementing Agreement for Cooperation in Gas-Cooled Reactor Development. The AVR information to be provided as described in the plan will provide a basis for examining the accuracy of computational methods used for performance and safety analysis. The purpose of the cooperation is to obtain experimental information from the AVR relevant to the performance and safety of modular gas-cooled reactors, and to compare measured results with predictions of analytical tools. This report provides a progress report on the prediction of plutonium buildup in LEU fuel in a high-enriched uranium (HEU) core and also describes the method for calculating the U-238 resonance integral (cross section). 4 refs., 5 figs., 11 tabs.
Date: June 1, 1988
Creator: Lane, R.K. & Lefler, W.L.
Partner: UNT Libraries Government Documents Department

Core fluctuations test. Revision 1

Description: Fluctuations were first encountered in the Fort St. Vrain reactor early in cycle 1 operation, during the initial rise from 40% to 70% power. Subsequent in-core tests and operation throughout cycles 1 and 2 demonstrated that fluctuations were repeatable, occurring at core pressure drops of between 2.5 psi and 4.0 psi, and that in each instance their characteristics were very similar. Subsequently, tests and analysis were done to understand the core fluctuation phenomenon. These efforts also lead to a design fix which stopped these fluctuations in the FSV reactor core. This fix required that keys be used in addition to the keys in the core support floor which already existed. This report outlines a test plan to validate that core fluctuations will not occur in the MHTGR core. 2 refs., 12 figs., 3 tabs.
Date: June 1, 1987
Creator: Betts, W.S.
Partner: UNT Libraries Government Documents Department

Probabilistic risk assessment of the modular HTGR plant. Revision 1

Description: A preliminary probabilistic risk assessment (PRA) has been performed for the modular HTGR (MHTGR). This PRA is preliminary in the context that although it updates the PRA issued earlier to include a wider spectrum of events for Licensing Basis Events (LBE) selection, the final version will not be issued until later. The primary function of the assessment was to assure compliance with the NRC interim safety goals imposed by the top-level regulatory criteria, and utility/user requirements regarding public evacuation or sheltering. In addition, the assessment provides a basis for designer feedback regarding reliability allocations and barrier retention requirements as well as providing a basis for the selection of licensing basis events (LBEs) and the safety classification of structures, systems, and components. The assessment demonstrates that both the NRC interim safety goals and utility/user imposed sheltering/evacuation requirements are satisfied. Moreover, it is not anticipated that design changes introduced will jeopardize compliance with the interim safety goals or utility/user requirements. 61 refs., 48 figs., 24 tabs.
Date: June 1, 1986
Creator: Everline, C.J.; Bellis, E.A. & Vasquez, J.
Partner: UNT Libraries Government Documents Department

Dose estimates for the 1104 m APS storage ring

Description: The estimated dose equivalent rates outside the shielded storage ring, and the estimated annual dose equivalent to members of the public due to direct radiation and skyshine from the ring, have been recalculated. The previous estimates found in LS-84 (MOE 87) and cited in the 1987 Conceptual Design Report of the APS (ANL 87) required revision because of changes in the ring circumference and in the proposed location of the ring with respect to the nearest site boundary. The values assumed for the neutron quality factors were also overestimated (by a factor of 2) in the previous computation, and the correct values have been used for this estimate. The methodology used to compute dose and dose rate from the storage ring is the same as that used in LS-90 (MOE 87a). The calculations assumed 80 cm thick walls of ordinary concrete (or the shielding equivalent of this) and a roof thickness of 1 meter of ordinary concrete. The circumference of the ring was increased to 1,104 m, and the closest distance to the boundary was taken as 140 m. The recalculation of the skyshine component used the same methodology as that used in LS-84.
Date: June 1, 1989
Creator: Moe, H.J.
Partner: UNT Libraries Government Documents Department