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XMGR5 users manual

Description: ACE/gr is XY plotting tool for workstations or X-terminals using X. A few of its features are: User defined scaling, tick marks, labels, symbols, line styles, colors. Batch mode for unattended plotting. Read and write parameters used during a session. Polynomial regression, splines, running averages, DFT/FFT, cross/auto-correlation. Hardcopy support for PostScript, HP-GL, and FrameMaker.mif format. While ACE/gr has a convenient point-and-click interface, most parameter settings and operations a… more
Date: March 1, 1997
Creator: Jones, K.R. & Fisher, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Plant Analyzer: Installation manual. Volume 1

Description: This report contains the installation instructions for the Nuclear Plant Analyzer (NPA) System. The NPA System consists of the Computer Visual System (CVS) program, the NPA libraries, the associated utility programs. The NPA was developed at the Idaho National Engineering Laboratory under the sponsorship of the US Nuclear Regulatory Commission to provide a highly flexible graphical user interface for displaying the results of these analysis codes. The NPA also provides the user with a convenien… more
Date: January 1, 1995
Creator: Snider, D. M.; Wagner, K. L.; Grush, W. H. & Jones, K. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An assessment of BWR (boiling water reactor) Mark-II containment challenges, failure modes, and potential improvements in performance

Description: This report assesses challenges to BWR Mark II containment integrity that could potentially arise from severe accidents. Also assessed are some potential improvements that could prevent core damage or containment failure, or could mitigate the consequences of such failure by reducing the release of fission products to the environment. These challenges and improvements are analyzed via a limited quantitative risk/benefit analysis of a generic BWR/4 reactor with Mark II containment. Point estimat… more
Date: July 1, 1990
Creator: Kelly, D. L.; Jones, K. R.; Dallman, R. J. & Wagner, K. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of SCDAP/RELAP5/MOD3 to TRAC-PF1/MOD1 for timing analysis of PWR fuel pin failures

Description: A comparison has been made of SCDAP/RELAP5/MOD3- and TRAC-PF1/MOD1- based calculations of the fuel pin failure timing (time from containment isolation signal to first fuel pin failure) in a loss-of-coolant accident (LOCA). The two codes were used to calculate the thermal-hydraulic boundary conditions for a complete, double-ended, offset-shear break of a cold leg in a Westinghouse 4-loop pressurized water reactor. Both calculations used the FRAPCON-2 code to calculate the steady-state fuel rod b… more
Date: December 1, 1991
Creator: Jones, K. R.; Katsma, K. R.; Wade, N. L.; Siefken, L. J. & Straka, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Calculation of fuel pin failure timing under LOCA conditions

Description: The objective of this research was to develop and demonstrate a methodology for calculation of the time interval between receipt of the containment isolation signals and the first fuel pin failure for loss-of-coolant accidents (LOCAs). Demonstration calculations were performed for a Babcock and Wilcox (B W) design (Oconee) and a Westinghouse (W) 4-loop design (Seabrook). Sensitivity studies were performed to assess the impacts of fuel pin burnup, axial peaking factor, break size, emergency core… more
Date: October 1991
Creator: Jones, K. R.; Wade, N. L.; Siefken, L. J.; Straka, M. & Katsma, K. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

An assessment of BWR (boiling water reactor) Mark III containment challenges, failure modes, and potential improvements in performance

Description: This report describes risk-significant challenges posed to Mark III containment systems by severe accidents as identified for Grand Gulf. Design similarities and differences between the Mark III plants that are important to containment performance are summarized. The accident sequences responsible for the challenges and the postulated containment failure modes associated with each challenge are identified and described. Improvements are discussed that have the potential either to prevent or del… more
Date: January 1, 1991
Creator: Schroeder, J. A.; Pafford, D. J.; Kelly, D. L.; Jones, K. R. & Dallman, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Severe accident natural circulation studies at the INEL

Description: Severe accident natural circulation flows have been investigated at the Idaho National Engineering Laboratory to better understand these flows and their potential impacts on the progression of a pressurized water reactor severe accident. Parameters affecting natural circulation in the reactor vessel and hot legs were identified and ranked based on their perceived importance. Reviews of the scaling of the 1/7-scale experiments performed by Westinghouse were undertaken. RELAP5/MOD3 calculations o… more
Date: February 1, 1995
Creator: Bayless, P. D.; Brownson, D. A.; Dobbe, C. A.; Jones, K. R.; O`Brien, J. E.; Pafford, D. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of SCDAP/RELAP5/MOD3 to TRAC-PF1/MOD1 for timing analysis of PWR fuel pin failures

Description: A comparison has been made of SCDAP/RELAP5/MOD3- and TRAC-PF1/MOD1- based calculations of the fuel pin failure timing (time from containment isolation signal to first fuel pin failure) in a loss-of-coolant accident (LOCA). The two codes were used to calculate the thermal-hydraulic boundary conditions for a complete, double-ended, offset-shear break of a cold leg in a Westinghouse 4-loop pressurized water reactor. Both calculations used the FRAPCON-2 code to calculate the steady-state fuel rod b… more
Date: January 1, 1991
Creator: Jones, K.R.; Katsma, K.R.; Wade, N.L.; Siefken, L.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States)) & Straka, M. (Halliburton NUS, Idaho Falls, ID (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Timing analysis of PWR fuel pin failures

Description: This report discusses research conducted to develop and demonstrate a methodology for calculation of the time interval between receipt of the containment isolation signals and the first fuel pin failure for loss-of-coolant accidents (LOCAs). Demonstration calculations were performed for a Babcock and Wilcox (B W) design (Oconee) and a Westinghouse (W) four-loop design (Seabrook). Sensitivity studies were performed to assess the impacts of fuel pin burnup, axial peaking factor, break size, emerg… more
Date: September 1, 1992
Creator: Jones, K.R.; Wade, N.L.; Katsma, K.R.; Siefken, L.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States)) & Straka, M. (Halliburton NUS, Idaho Falls, ID (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Timing analysis of PWR fuel pin failures

Description: Research has been conducted to develop and demonstrate a methodology for calculation of the time interval between receipt of the containment isolation signals and the first fuel pin failure for loss-of-coolant accidents (LOCAs). Demonstration calculations were performed for a Babcock and Wilcox (B W) design (Oconee) and a Westinghouse (W) four-loop design (Seabrook). Sensitivity studies were performed to assess the impacts of fuel pin bumup, axial peaking factor, break size, emergency core cool… more
Date: September 1, 1992
Creator: Jones, K. R.; Wade, N. L.; Katsma, K. R.; Siefken, L. J. (EG and G Idaho, Inc., Idaho Falls, ID (United States)) & Straka, M. (Halliburton NUS, Idaho Falls, ID (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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