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Relevant bibliographies by topics / GSI-191

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Academic literature on the topic 'GSI-191'

Author: Grafiati

Published: 4 June 2021

Last updated: 8 February 2022

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Journal articles on the topic "GSI-191"

1

Kee, Ernie, John Hasenbein, Alex Zolan, et al. "RoverD: Use of Test Data in GSI-191 Risk Assessment." Nuclear Technology 196, no. 2 (2016): 270–91. http://dx.doi.org/10.13182/nt16-34.

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Larson, Wesley A., James E. Seeb, Carita E. Pascal, William D. Templin, and Lisa W. Seeb. "Single-nucleotide polymorphisms (SNPs) identified through genotyping-by-sequencing improve genetic stock identification of Chinook salmon (Oncorhynchus tshawytscha) from western Alaska." Canadian Journal of Fisheries and Aquatic Sciences 71, no. 5 (2014): 698–708. http://dx.doi.org/10.1139/cjfas-2013-0502.

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Genetic stock identification (GSI), an important tool for fisheries management that relies upon the ability to differentiate stocks of interest, can be difficult when populations are closely related. Here we genotyped 11 850 single-nucleotide polymorphisms (SNPs) from existing DNA sequence data available in five closely related populations of Chinook salmon (Oncorhynchus tshawytscha) from western Alaska. We then converted a subset of 96 of these SNPs displaying high differentiation into high-throughput genotyping assays. These 96 SNPs (RAD96) and 191 SNPs developed previously (CTC191) were scr

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3

Beeny, B., R. Vaghetto, K. Vierow, and Y. A. Hassan. "MELCOR and GOTHIC Analyses of a Large Dry PWR Containment to Support Resolution of GSI-191." Nuclear Technology 196, no. 2 (2016): 292–302. http://dx.doi.org/10.13182/nt16-36.

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Fleming, K. N., and B. O. Y. Lydell. "Insights into location dependent loss-of-coolant-accident (LOCA) frequency assessment for GSI-191 risk-informed applications." Nuclear Engineering and Design 305 (August 2016): 433–50. http://dx.doi.org/10.1016/j.nucengdes.2016.06.007.

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5

Singhal, Tripti, C. Tara Satyavathi, Aruna Kumar, et al. "Genotype × environment interaction and genetic association of grain iron and zinc content with other agronomic traits in RIL population of pearl millet." Crop and Pasture Science 69, no. 11 (2018): 1092. http://dx.doi.org/10.1071/cp18306.

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Biofortification of lines of pearl millet (Pennisetum glaucum (L.) R.Br.) with increased iron (Fe) and zinc (Zn) will have great impact because pearl millet is an indispensable component of food and nutritional security of inhabitants of arid and semi-arid regions. The aim of the present study was to assess the stability of Fe and Zn content in recombinant inbred lines (RILs) developed for grain Fe and Zn content, and to use these lines in developing micronutrient-rich pearl millet hybrids. A mapping population consisting of 210 RILs along, with parents and checks, was assessed in three consec

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6

Ali, Amir, and Edward D. Blandford. "An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss-of-Coolant Accident Conditions." Journal of Nuclear Engineering and Radiation Science 2, no. 3 (2016). http://dx.doi.org/10.1115/1.4032439.

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The United States Nuclear Regulatory Commission (NRC) initiated a generic safety issue (GSI-191) assessing debris accumulation and resultant chemical effects on pressurized water reactor (PWR) sump performance. GSI-191 has been investigated using reduced-scale separate-effects testing and integral-effects testing facilities. These experiments focused on developing a procedure to generate prototypical debris beds that provide stable and reproducible conventional head loss (CHL). These beds also have the ability to filter out chemical precipitates resulting in chemical head loss. The newly devel

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Dissertations / Theses on the topic "GSI-191"

1

Pan, Ying-An. "Uncertainty quantification for risk assessment of loss-of-coolant accident frequencies in nuclear power plants." 2013. http://hdl.handle.net/2152/22499.

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This research presents the methodologies used to resolve the Nuclear Regulatory Commission Generic Safety Issue 191. The presented results are specific to South Texas Project Nuclear Operating Company (STPNOC). However, the proposed methodologies may be applicable to other nuclear power plants given the appropriate plant-specific frequencies. This research provides important inputs to CASA Grande, a computer program used to model physical phenomena and quantify uncertainties to obtain estimates of failure probabilities for post-loss-of-coolant accident events at the STPNOC containment. We pr

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Books on the topic "GSI-191"

1

Rao, D. V. GSI-191: Thermal-hydraulic response of PWR reactor coolant system and containments to selected accident sequences. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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2

V, Rao D., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Los Alamos National Laboratory, eds. GSI-191 technical assessment. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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3

V, Rao D., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Los Alamos National Laboratory, eds. GSI-191 technical assessment. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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4

V, Rao D., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Los Alamos National Laboratory, eds. GSI-191: Separate-effects characterization of debris transport in water. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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5

GSI-191: Separate-effects characterization of debris transport in water. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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6

W, Ross K., Ashbaugh S. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Los Alamos National Laboratory, eds. GSI-191: Thermal-hydraulic response of PWR reactor coolant system and containments to selected accident sequences. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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7

GSI-191: The impact of debris induced loss of ECCS recirculation on PWR core damage frequency. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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8

GSI-191: The impact of debris induced loss of ECCS recirculation on PWR core damage frequency. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

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9

GSI-191: Thermal-Hydraulic Response of PWR Coolant System and Containments to Selected Accident Sequences (NUREG/CR-6770). USGOV, 1999.

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10

GSI-191: Impact of Debris Induced Loss of ECCS Recirculation on PWR Core Damage Frequency (NUREG/CR-6771). USGOV, 1999.

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Conference papers on the topic "GSI-191"

1

Sande, Timothy D., Gilbert L. Zigler, Ernie J. Kee, Bruce C. Letellier, C. Rick Grantom, and Zahra Mohaghegh. "The Benefits of Using a Risk-Informed Approach to Resolving GSI-191." In 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-54604.

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The emergency core cooling system (ECCS) and containment spray system (CSS) in a pressurized water reactor (PWR) are designed to safely shutdown the plant following a loss of coolant accident (LOCA). The assurance of long term core cooling in PWRs following a LOCA has a long history dating back to the NRC studies of the mid 1980s associated with Unresolved Safety Issue (USI) A-43. Results of the NRC research on boiling water reactor (BWR) ECCS suction strainer blockage of the early 1990s identified new phenomena and failure modes that were not considered in the resolution of USI A-43. As a res

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2

Morton, David, Bruce Letellier, Jeremy Tejada, et al. "Sensitivity Analyses of a Simulation Model for Estimating Fiber-Induced Sump Screen and Core Failure Rates." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30917.

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Output from a high-order simulation model with random inputs may be difficult to fully evaluate absent an understanding of sensitivity to the inputs. We describe, and apply, a sensitivity analysis procedure to a large-scale computer simulation model of the processes associated with Nuclear Regulatory Commission (NRC) Generic Safety Issue (GSI) 191. Our GSI-191 simulation model has a number of distinguishing features: (i) The model is large in scale in that it has a high-dimensional vector of inputs; (ii) some model inputs are governed by probability distributions; (iii) a key model output is t

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3

Adams, J. C., L. I. Ezekoye, S. M. Smith, and S. R. Swantner. "An Application of Computational Fluid Dynamics (CFD) Code to the Design of a Multi-Stage Breakdown Orifice in Support of GSI-191 Evaluations." In ASME 2007 Pressure Vessels and Piping Conference. ASMEDC, 2007. http://dx.doi.org/10.1115/pvp2007-26208.

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In September 2004, the Nuclear Regulatory Commission (NRC) issued Generic Letter GL2004-02 “Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors” to address Generic Safety Issue 191 (GSI-191) “Assessment of debris accumulation on PWR sump performance.” [1] GL2004-02 requested pressurized water reactor (PWR) licensees to perform a “downstream effects” evaluation of their emergency core cooling (ECCS) and containment spray systems (CSS). GL2004-02 also gave guidance on what analysis had to be completed in order to resolve GSI-

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4

Lee, Saya, Yassin A. Hassan, Rodolfo Vaghetto, Suhaeb Abdulsattar, and Matthew Kappes. "Water Chemistry Sensitivity on Fibrous Debris Bypass Through a Containment Sump Strainer." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-31176.

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Fibrous debris generated from insulation materials during a Loss of Coolant Accident (LOCA) might be transported to the containment sump strainer. Once the fibrous debris reaches the sump strainer, it might accumulate on the strainer causing loss of Net Positive Suction Head (NPSH), called the upstream effect, or it might penetrate through the strainer becoming a source of clogging of flow channel in the core (in-vessel effect). This is the main idea of the Generic Safety Issue (GSI) 191 initiated by the U.S. Nuclear Regulatory Commission (U.S.NRC). In this study, the authors focused on the qu

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5

Ezekoye, L. Ike, Rolv Hundal, and Paul V. Pyle. "An Evaluation of Post-LOCA Debris on Multi-Stage Safety-Related Pumps in PWR ECCS in Support of Generic Safety Issue 191 Closure." In ASME 2008 Pressure Vessels and Piping Conference. ASMEDC, 2008. http://dx.doi.org/10.1115/pvp2008-61766.

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The U.S. Nuclear Regulatory Commission (NRC) issued Generic Safety Issue (GSI) 191 covering the ability of nuclear reactor containment building (RCB) sumps to support long-term core cooling post-accident for Pressurized Water Reactors (PWRs). The issue is that a postulated Loss-of-Coolant Accident (LOCA) for a PWR would result in the initial escape of high-pressure, high-temperature subcooled coolant from the pipe break location in the form of a two-phase jet. The impingement of the jet may damage materials used inside the RCB, resulting in the generation of debris. The debris transported to a

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6

Lee, Saya, Suhaeb Abdulsattar, and Yassin A. Hassan. "Head Loss Through Fibrous Beds Generated on Different Types of Containment Sump Strainers." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-31233.

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During a Loss of Coolant Accident (LOCA), the high energy jet from the break may impinge on surrounding surfaces and materials, producing a relatively large amount of fibrous debris (mostly insulation materials). The debris may be transported through the reactor containment and reach the sump strainers. Accumulation of such debris on the strainers’ surface can cause a loss of Net Positive Suction Head (NPSH) and negatively affect the Emergency Core Cooling System (ECCS) capabilities. The U.S. Nuclear Regulatory Commission (U.S.NRC) initiated the Generic Safety Issue (GSI) 191 to understand the

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7

Detar, Heather L., Daniel T. McLaughlin, and Robert J. Lutz. "Probabilistic Model for Debris-Induced Loss of Long Term Core Cooling." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48780.

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Generic Safety Issue (GSI) 191 deals with the potential for generation and transport of debris following a design basis accident that is in excess of quantities assumed in the original design basis and licensing of Pressurized Water Reactor (PWR) plants. In addition to physical modifications to the sump screens to comply with the Generic Letter requirements, some plants have also changed Emergency Operating Procedures (EOPs) to include contingency actions to prevent debris-induced loss of long term core cooling. ASME Probabilistic Risk Assessment (PRA) standard RA-Sb-2005 requires that the pla

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8

Mehta, A. R., A. J. Bilanin, J. Hamel, and A. Kaufman. "Containment Sump Active Strainers." In ASME 2005 Pressure Vessels and Piping Conference. ASMEDC, 2005. http://dx.doi.org/10.1115/pvp2005-71695.

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The containment sump, also known as emergency or recirculation sump, is part of the Emergency Core Cooling System (ECCS). Every nuclear power plant is required by regulations to have an ECCS to mitigate a design basis accident. The containment sump of a Pressurized Water Reactor (PWR) collects reactor coolant and chemically reactive spray solutions following a Loss of Coolant Accident (LOCA). The containment sump serves as the water source to support long-term recirculation. This water source, the related pump inlets and the piping between the source and inlets are all important safety compone

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