U.S. Nuclear Regulatory Commission
Label
U.S. Nuclear Regulatory Commission
Name
U.S. Nuclear Regulatory Commission
Actions
Incoming Resources
- Reactor oversight process
- Coupled RELAP/PARCS full plant model, assessment of a cooling transient in Trillo Nuclear Power Plant, prepared by J.C. Martinez-Murillo [and others]
- Assessment of channel coolant voiding in RD-14M test facility using TRACE, prepared by Andrew Oussoren, Aleksandar Delja
- Audit of NRC's process for addressing bankruptcy of materials licensees, Stephen D. Dingbaum
- Modelling of ROCOM mixing test 2.2 with TRACE v5.0 Patch 3, prepared by Joona Kurki
- Improvements and validation of the system code TRACE for lead and lead-alloy cooled fast reactors safety-related investigations, prepared by: Wadim Jaeger, Victor Hugo Sanchez Espinoza
- Development of a computer tool for in-depth analysis and post processing of the RELAP5 thermal hydraulic code, R.H. Santos, J. M. Izquierdo Rocha
- Analysis of the control rod drop accident (CRDA) for lungmen ABWR, prepared by Chunkuan Shih [and five others]
- The FSAR transients analysis of Lungmen ABWR using TRACE/PARCS, prepared by: Jong-Rong Wang [and three others]
- Transient analysis of the research reactor MARIA MC fuel elements using RELAP5 Mod 3.3, prepared by M. Dabrowski, P. Domitr, E. Staron
- Assessment of the TRACE code using transient data from Maanshan PWR Nuclear Power Plant, prepared by: Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih
- RELAP5/MOD3.3 assessment against PMK test T3.1 -- LBLOCA with nitrogen in PRZ, prepared by Pavel Kral
- Potential for degradation of the emergency core cooling system and the containment spray system after a loss-of-coolant accident because of construction and protective coating deficiencies and foreign material in containment
- Simulation of LSTF upper head break (OECD/NEA ROSA test 6.1) with TRACE code, application to a PWR NPP model, prepared by César Queral [and four others]
- Assessment of LONF ATWS for Maanshan PWR using TRACE code, prepared by: Jong-Rong Wang [and three others]
- Nuclear regulation, NRC needs more effective analysis to ensure accumulation of funds to decommission nuclear power plants
- Coupling the RELAP code with external calculation programs (shared memory version), prepared by Felix Maciel
- Hacienda nuestro negocio su negocio
- TRACE analysis on heat removal decrease accidents for AP1000, prepared by: Jong-Rong Wang [and three others]
- Three Mile Island, a nuclear crisis in historical perspective, J. Samuel Walker
- Environmental impact statement on the construction and operation of a mixed oxide fuel fabrication facility at the Savannah River site, South Carolina, draft report for comment ; prepared by Argonne National Laboratory for U.S. Nuclear Regulatory Commission
- Hydrogen:air:steam flammability limits and combustion characteristics in the FITS vessel, by Billy W. Marshall, Jr
- Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility, prepared by M. Kynčl, R. Pernica
- Assessment of TRACE 5.0 against ROSA Test 6-1, vessel upper head SBLOCA, prepared by S. Gallardo, V. Abella, G. Verdú
- TRACE5 assessment of 100% direct vessel injection line break in ATLAS facility, prepared by Byung-Gil Huh [and four others]
- RELAP5 extended station blackout analyses, prepared by A. Prosek, B. Mavko
- Analysis of JNES seismic tests on degraded piping, T. Zhang [and others]
- License renewal generic environmental impact statement, (NUREG-1437)
- An assessment of ultrasonic techniques for far-side examinations of austenitic stainless steel piping welds, prepared by M.T. Anderson [and others]
- Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3, prepared by M. Dabrowski, E. Staron
- Post-test analysis of Hot Leg 2x25% break at PSB-VVER facility using TRACE V5.0 code, prepared by P. Heralecky, M. Blaha
- TRACE (V 5.0 Patch 2) validation based on the RELAP5-Calculation of FIX-III LOCA experiments no. 5052, 4011, 3051, prepared by S. ChunHong Sheng
- Full scale loop seal experiments with TRACE V5 Patch 1, prepared by Seppo Hillberg
- An assessment of TRACE V5 RC1 code separator model with the Westinghouse Model Boiler 2 experiments, prepared by S. Hillberg, A. Calvo
- RELAP5/MOD3.3 assessment against new PMK experiments, prepared by P. Kral
- Public involvement in the nuclear regulatory process
- NRC collection of abbreviations, U.S. Nuclear Regulatory Commission
- RELAP5/MOD3 horizontal off-take model for application to reactor headers of CANDU type reactors, prepared by: Bub Dong Chung [and others]
- Nuclear Regulatory Commission, revision of fee schedules : fee recovery for FY 2003
- Hydrogen-steam jet-flame facility and experiments, Joseph E. Shepherd
- Reporting safety concerns to the NRC
- Modeling potential reactor accident consequences
- Simulation of LSTF hot leg break (OECD/NEA ROSA-2 test 1) with TRACE code, application to a PWR NPP model, prepared by Juan Gonzalez-Cadelo [and four others]
- How to handle radioactive materials packages, a guide for cargo handlers
- NRC public meetings, U.S. Nuclear Regulatory Commission
- Assessment of TRACE 5.0 against ROSA test 3-1, cold leg SBLOCA, prepared by S. Gallardo [and others]
- Assessment of TRACE 5.0 against ROSA test 3-2, high power natural circulation, prepared by S. Gallardo [and others]
- Acceptance and verification for early warning fire detection systems, interim guide, J.L. Boccio and R.E. Hall and I. Asp
- Loss of external load analysis with RELAP5/MOD3.3 patch 03 code, prepared by Andrej Prošek, Borut Mavko
- ISCORS assesement [sic] of radioactivity in sewage sludge radiological survey results and anaysis, developed by the Sewage Sludge Subcommittee on Radiation Standards ; prepared by Andrea R. Jones
- Creator of9
- Hacienda nuestro negocio su negocio
- NRC regulatory guides
- The United States of America fourth national report for the Convention on Nuclear Safety
- The United States of America, national report for the Convention on Nuclear Safety
- A journey to your future, make discovering your career an adventure, U.S. Nuclear Regulatory Commission
- NRC inspector, field observation best practices, United States Nuclear Regulatory Commission
- Strategic plan, fiscal year 2000 - fiscal year 2005
- Making our business your business
- Open government plan, U.S. Nuclear Regulatory Commission
- Focus of49
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Recruiting
- U.S. Nuclear Regulatory Commission -- Automation -- Management
- U.S. Nuclear Regulatory Commission -- Finance
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Training of
- U.S. Nuclear Regulatory Commission -- Communication -- Security measures
- U.S. Nuclear Regulatory Commission -- Handbooks, manuals, etc
- U.S. Nuclear Regulatory Commission -- Appropriations and expenditures, 1986-1987
- U.S. Nuclear Regulatory Commission -- Planning
- U.S. Nuclear Regulatory Commission -- Information resources management -- Security measures
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Selection and appointment
- U.S. Nuclear Regulatory Commission -- Rules and practice
- U.S. Nuclear Regulatory Commission -- Security measures
- U.S. Nuclear Regulatory Commission -- Licenses -- Management
- U.S. Nuclear Regulatory Commission -- Information technology -- Security measures
- U.S. Nuclear Regulatory Commission -- Information technology -- Management
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Recruiting -- Handbooks, manuals, etc
- U.S. Nuclear Regulatory Commission -- Management
- U.S. Nuclear Regulatory Commission -- Auditing
- U.S. Nuclear Regulatory Commission -- Finance -- Auditing
- U.S. Nuclear Regulatory Commission -- Personnel management
- U.S. Nuclear Regulatory Commission -- Officials and employees
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Training
- U.S. Nuclear Regulatory Commission -- Information technology
- U.S. Nuclear Regulatory Commission -- Reorganization
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Management
- U.S. Nuclear Regulatory Commission -- Licenses -- Rules and practice
- U.S. Nuclear Regulatory Commission -- Employees -- Identification
- U.S. Nuclear Regulatory Commission -- Data processing
- U.S. Nuclear Regulatory Commission -- Information technology -- Procurement -- Auditing
- U.S. Nuclear Regulatory Commission -- Procurement
- U.S. Nuclear Regulatory Commission -- Appropriations and expenditures
- U.S. Nuclear Regulatory Commission -- Research -- Moral and ethical aspects -- Auditing
- U.S. Nuclear Regulatory Commission -- Finance -- Management
- U.S. Nuclear Regulatory Commission -- Security measures -- Evaluation
- U.S. Nuclear Regulatory Commission -- Management -- Evaluation
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Security measures
- U.S. Nuclear Regulatory Commission -- Data processing -- Management
- U.S. Nuclear Regulatory Commission -- Rules and practice -- Evaluation
- U.S. Nuclear Regulatory Commission -- Records and correspondence
- U.S. Nuclear Regulatory Commission -- Evaluation
- U.S. Nuclear Regulatory Commission -- History
- U.S. Nuclear Regulatory Commission -- Employees -- Research
- U.S. Nuclear Regulatory Commission -- Data processing -- Security measures
- U.S. Nuclear Regulatory Commission -- Quality control
- U.S. Nuclear Regulatory Commission -- Information resources management
- U.S. Nuclear Regulatory Commission -- Officials and employees -- Rating of
- U.S. Nuclear Regulatory Commission -- Rules and practice -- Evaluation
- U.S. Nuclear Regulatory Commission
- U.S. Nuclear Regulatory Commission -- Employees
- Author of3
- inverse.issuingbody48
- Transient analysis of the research reactor MARIA MC fuel elements using RELAP5 Mod 3.3, prepared by M. Dabrowski, P. Domitr, E. Staron
- Audit of NRC's process for addressing bankruptcy of materials licensees, Stephen D. Dingbaum
- Improvements and validation of the system code TRACE for lead and lead-alloy cooled fast reactors safety-related investigations, prepared by: Wadim Jaeger, Victor Hugo Sanchez Espinoza
- Modelling of ROCOM mixing test 2.2 with TRACE v5.0 Patch 3, prepared by Joona Kurki
- Analysis of the control rod drop accident (CRDA) for lungmen ABWR, prepared by Chunkuan Shih [and five others]
- Modeling potential reactor accident consequences
- Assessment of LONF ATWS for Maanshan PWR using TRACE code, prepared by: Jong-Rong Wang [and three others]
- Simulation of LSTF upper head break (OECD/NEA ROSA test 6.1) with TRACE code, application to a PWR NPP model, prepared by César Queral [and four others]
- Hacienda nuestro negocio su negocio
- TRACE analysis on heat removal decrease accidents for AP1000, prepared by: Jong-Rong Wang [and three others]
- Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility, prepared by M. Kynčl, R. Pernica
- TRACE5 assessment of 100% direct vessel injection line break in ATLAS facility, prepared by Byung-Gil Huh [and four others]
- RELAP5 extended station blackout analyses, prepared by A. Prosek, B. Mavko
- TRACE (V 5.0 Patch 2) validation based on the RELAP5-Calculation of FIX-III LOCA experiments no. 5052, 4011, 3051, prepared by S. ChunHong Sheng
- Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3, prepared by M. Dabrowski, E. Staron
- Assessment of channel coolant voiding in RD-14M test facility using TRACE, prepared by Andrew Oussoren, Aleksandar Delja
- The FSAR transients analysis of Lungmen ABWR using TRACE/PARCS, prepared by: Jong-Rong Wang [and three others]
- Simulation of LSTF hot leg break (OECD/NEA ROSA-2 test 1) with TRACE code, application to a PWR NPP model, prepared by Juan Gonzalez-Cadelo [and four others]
- The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model, prepared by Chunkuan Shih [and five others]
- RELAP5/MOD3.3 assessment by comparison with PKL III G3.1 experiment (small break in the main steam line), prepared by A. Zaruba, K. Krezeminski, A. Benkert
- Performing uncertainty analysis of IIST facility SBLOCA by TRACE and DAKOTA, prepared by Jong-Rong Wang [and three others]
- Reflections on Fukushima, NRC senior leadership visit to Japan, 2014, C. Rosales-Cooper [and thirteen others]
- The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE, prepared by: Jong-Rong Wang [and three others]
- Regulating nuclear fuel
- The establishment and assessment of Kuosheng (BWR/6) NPP dry-storage system TRACE/SNAP model, prepared by Chunkuan Shih [and three others]
- Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2, prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- The development and application of TRACE/PARCS model for Lungmen ABWR, prepared by: Jong-Rong Wang [and three others]
- No undue risk, regulating the safety of operating nuclear power plants
- Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants, guidance for protective action strategies
- Sensitivity study of the DEG LBLOCA transient on the counter-current flow limitation by using TRACE, prepared by: Jong-Rong Wang [and three others]
- BEPU analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA, prepared by Chunkuan Shih [and five others]
- The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model, prepared by Jong-Rong Wang [and three others]
- The regulation and use of radioisotopes in today's world
- Implementation of the control rod movement option by means of control variables in RELAP5/PARCS v2.7 coupled code, prepared by R. Miro [and six others]
- Post-test analysis of Upper Plenum 11% break at PSB-VVER facility using TRACE v5.0 and RELAP5/MOD3.3 code, prepared by Petr Heralecky
- Analysis of loss of feedwater heater transients for Lungmen ABWR by TRACE/PARCS, prepared by: Jong-Rong Wang [and three others]
- Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE, prepared by: S. Belaïd, J. Freixa, O. Zerkak
- Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA, prepared by Jong-Rong Wang [and three others]
- Applying statistics, Dan Lurie, Lee Abramson, James Vail
- TRACE simulation of SBO accident and mitigation strategy in Maanshan PWR, prepared by: Jong-Rong Wang [and three others]
- RELAP5/MOD3.3 analysis of steam generator tube rupture (SGTR) accident for NPP Krško, prepared by V. Benčik, D. Grgić
- ATWS analysis of Lungmen ABWR for MSIV closure transient, prepared by: Jong-Rong Wang [and three others]
- Analysis with TRACE code of PKL-III test F 1.2, prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivà
- The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA, prepared by: Jong-Rong Wang [and three others]
- Making our business your business
- Assessment against ACHILLES reflood experiment with TRACE V5.0 Patch3, prepared by O.A. Berar, A. Prosek
- Tribal protocol manual, Patricia McGrady-Finneran
- RELAP5/MOD3.3 release pre & postprocessor, prepared by W. Teitsch