U.S. Nuclear Regulatory Commission, Division of Systems Analysis
Resource Information
The organization U.S. Nuclear Regulatory Commission, Division of Systems Analysis represents an institution, an association, or corporate body that is associated with resources found in Biddle Law Library.
The Resource
U.S. Nuclear Regulatory Commission, Division of Systems Analysis
Resource Information
The organization U.S. Nuclear Regulatory Commission, Division of Systems Analysis represents an institution, an association, or corporate body that is associated with resources found in Biddle Law Library.
- Label
- U.S. Nuclear Regulatory Commission, Division of Systems Analysis
- Subordinate unit
- Division of Systems Analysis
32 Items by the Organization U.S. Nuclear Regulatory Commission, Division of Systems Analysis
Context
Context of U.S. Nuclear Regulatory Commission, Division of Systems AnalysisContributor of
- Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code
- Analysis with TRACE code of ROSA test 1.1 : ECCS water injection under natural circulation condition
- Analysis with TRACE code of Rosa test 1.2 : small LOCA in the hot-leg with HPI and accumulator actuation
- Assessment against ACHILLES reflood experiment with TRACE V5.0 Patch3
- Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5
- BEPU analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA
- Benchmarking of a generic CANDU reactor with PARCS, MCNP and RFSP
- Comparison of the U.S. NRC PARCS core neutronics simulator against in-core detector measurements for LWR applications
- Development of a coupled TRACE/PARCS model for KKL and benchmark against the turbine trip test
- Evaluation of TRACE spacer grid model with FLECHT-SEASET reflood test
- Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
- Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA
- Implementation of advanced multigroup nodal and pin power reconstruction methods into PARCS 3.1
- Main stream line break analysis for lungmen ABWR
- Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2
- Proposal for the development and implementation of an uncertainty and sensitivity analysis module in SNAP
- RELAP5 analysis of mitigation strategy for extended blackout power condition in PWR
- RELAP5 and TRACE calculations of LOCA in PWR
- RELAP5/MOD3.3 analysis of event with actuation of safety injection system at the loss of external power
- Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3
- Sensitivity analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP/MOD3.2
- Simulation of LSTF hot leg break (OECD/NEA ROSA-2 test 1) with TRACE code : application to a PWR NPP model
- Simulation of LSTF upper head break (OECD/NEA ROSA test 6.1) with TRACE code : application to a PWR NPP model
- Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
- TRACE analysis on heat removal decrease accidents for AP1000
- TRACE assessment for effect of spacer grid in RBHT reflood heat transfer experiments
- TRACE/RELAP5 comparative calculations for double-ended LBLOCA and SBO
- TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline
- The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE
- Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface
- Uncertainty and sensitivity investigations with TRACE-SUSA and TRACE-DAKOTA by means of post-test calculations of NUPUC BFBT experiments
- Validation of RELAP5 model of ringhals 4 against a load step test at uprated power
Issuing body of
- Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code
- Analysis with TRACE code of ROSA test 1.1 : ECCS water injection under natural circulation condition
- Analysis with TRACE code of Rosa test 1.2 : small LOCA in the hot-leg with HPI and accumulator actuation
- Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5
- Development of a coupled TRACE/PARCS model for KKL and benchmark against the turbine trip test
- Evaluation of TRACE spacer grid model with FLECHT-SEASET reflood test
- Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
- Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA
- Implementation of advanced multigroup nodal and pin power reconstruction methods into PARCS 3.1
- Main stream line break analysis for lungmen ABWR
- RELAP5 analysis of mitigation strategy for extended blackout power condition in PWR
- RELAP5 and TRACE calculations of LOCA in PWR
- RELAP5/MOD3.3 analysis of event with actuation of safety injection system at the loss of external power
- Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
- TRACE assessment for effect of spacer grid in RBHT reflood heat transfer experiments
- TRACE/RELAP5 comparative calculations for double-ended LBLOCA and SBO
- TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline
- Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface
- Uncertainty and sensitivity investigations with TRACE-SUSA and TRACE-DAKOTA by means of post-test calculations of NUPUC BFBT experiments
- Validation of RELAP5 model of ringhals 4 against a load step test at uprated power
Sponsoring body of
- Assessment against ACHILLES reflood experiment with TRACE V5.0 Patch3
- BEPU analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA
- Benchmarking of a generic CANDU reactor with PARCS, MCNP and RFSP
- Comparison of the U.S. NRC PARCS core neutronics simulator against in-core detector measurements for LWR applications
- Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2
- Proposal for the development and implementation of an uncertainty and sensitivity analysis module in SNAP
- Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3
- Simulation of LSTF hot leg break (OECD/NEA ROSA-2 test 1) with TRACE code : application to a PWR NPP model
- Simulation of LSTF upper head break (OECD/NEA ROSA test 6.1) with TRACE code : application to a PWR NPP model
- TRACE analysis on heat removal decrease accidents for AP1000
- The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE
Embed (Experimental)
Settings
Select options that apply then copy and paste the RDF/HTML data fragment to include in your application
Embed this data in a secure (HTTPS) page:
Layout options:
Include data citation:
<div class="citation" vocab="http://schema.org/"><i class="fa fa-external-link-square fa-fw"></i> Data from <span resource="http://link.law.upenn.edu/resource/E5jfVu2xgt0/" typeof="Organization http://bibfra.me/vocab/lite/Organization"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.law.upenn.edu/resource/E5jfVu2xgt0/">U.S. Nuclear Regulatory Commission, Division of Systems Analysis</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.law.upenn.edu/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.law.upenn.edu/">Biddle Law Library</a></span></span></span></span></div>
Note: Adjust the width and height settings defined in the RDF/HTML code fragment to best match your requirements
Preview
Cite Data - Experimental
Data Citation of the Organization U.S. Nuclear Regulatory Commission, Division of Systems Analysis
Copy and paste the following RDF/HTML data fragment to cite this resource
<div class="citation" vocab="http://schema.org/"><i class="fa fa-external-link-square fa-fw"></i> Data from <span resource="http://link.law.upenn.edu/resource/E5jfVu2xgt0/" typeof="Organization http://bibfra.me/vocab/lite/Organization"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.law.upenn.edu/resource/E5jfVu2xgt0/">U.S. Nuclear Regulatory Commission, Division of Systems Analysis</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.law.upenn.edu/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.law.upenn.edu/">Biddle Law Library</a></span></span></span></span></div>
