United States Nuclear Regulatory Commission - Protecting People and the Environment

Site Additions in 2019

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See also New on Our Site for current additions.


April 30, 2019

NUREG/CR-7103, Volume 4
Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys: Behavior of Alloy 152 And 52 Welds

April 18, 2019

Validation of RELAP5/MOD3.3 Friction Loss and Heat Transfer Model for Narrow Rectangular Channels

April 16, 2019

NUREG-0713, Volume 39
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and other Facilities 2017, Fiftieth Annual Report

Simulation of ROSA-2 Test 3 Counterpart with TRACE5 – Application to Nuclear Power Plant

April 15, 2019

Assessment of TRACE 5.0 Against ROSA-2 Test 5, Main Steam Line Break with Steam Generator Tube Rupture

April 4, 2019

NUREG-1437, Supplement 5, Second Renewal
Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Subsequent License Renewal for Turkey Point Nuclear Generating Unit Nos. 3 and 4

April 3, 2019

NUREG-2226, Volumes 1 & 2
Environmental Impact Statement for an Early Site Permit (ESP) at the Clinch River Nuclear Site: Final Report

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March 26, 2019

Credibility Assessment Framework for Critical Boiling Transition Models: A generic safety case to determine the credibility of critical heat flux and critical power models, Draft for Comment

NUREG-1556, Volume 13, Revision 2
Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Commercial Radiopharmacy Licenses, Final Report

March 18, 2019

NUREG-1100, Volume 35
Congressional Budget Justification: Fiscal Year 2020

March 15, 2019

NUREG/BR-0117, No. 17-04
NMSS Quarterly Newsletters – Spring 2017

Post-Test Analysis of Cold Leg Small Break 4.1% at PSB-VVER Facility using TRACE V5.0

Natural Circulation (Interruption) Analysis with MELCOR 2.2 during Asymmetric Cooldown Transients

Assessment of TRACE 5.0 Against ROSA-2 Test 3 Counterpart Test to PKL

March 14, 2019

Post-Test Calculation of the ROSA-2 Test 3 Using RELAP5/MOD3.3

March 14, 2019

Investigation of the Loop Seal Clearing Phenomena for the ATLAS DVI Line and Cold Leg SBLOCA Tests Using MARS-KS and RELAP5/MOD3.3

March 14, 2019

Simulation of ROSA-2 Test-2 Experiment: Application to Nuclear Power Plant

March 14, 2019

Seismic Isolation of Nuclear Power Plants using Elastomeric Bearings

March 14, 2019

Post-Test Analysis of ROSA-2 Test 2 (IBLOCA) with TRACE

March 11, 2019

NUREG-1100, Volume 35
Congressional Budget Justification: Fiscal Year 2020 Summary

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February 28, 2019

The Analysis and Study of ELAP Event and Mitigation Strategies Using TRACE Code for Maanshan PWR

IBLOCA Analysis for Vandellòs-NPP Using RELAP5/MOD3.3. Sensitivity Calculations to EOP Actions

Post-Test Calculation of the PKL-2 Test G7.1 Using RELAP5/MOD3.3

February 22, 2019

Technical Considerations for Seismic Isolation of Nuclear Facilities

February 15, 2019

Assessment of the Wall Film Condensation Model with Non-condensable Gas in RELAP5 and TRACE for Vertical Tube and Plate Geometries

February 14, 2019

NUREG-1830, Volume 15
Office of Investigations – Annual Report FY 2018

February 7, 2019

NUREG-1307, Revision 17
Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities, Final Report

Assessment of NEPTUN Reflooding Experiments 5050 and 5052 with TRACE V5.0 Patch 5

February 6, 2019

The Ultimate Response Guideline Simulation and Study for Lungmen (ABWR) Nuclear Power Plant Using RELAP5/SNAP

Critical Heat Flux Data Used to Generate the 2006 Groeneveld Lookup Tables

NUREG-1885, Revision 11
Report to Congress on the Security Inspection Program for Commercial Power Reactors and Category I Fuel Cycle Facilities: Results and Status Update – Annual Report for Calendar Year 2017

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January 29, 2019

NUREG-1650, Revision 6, Supplement 1
Answers to Questions from the Peer Review by Contracting Parties on the United States of America Seventh National Report for the Convention on Nuclear Safety

January 28, 2019

Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions

RELAP5 Model of a CANDU-6 (Embalse) Nuclear Power Plant: Application to a Turbine Trip Event

January 22, 2019

Simulation of the LSTF-PKL Counterpart G7.1 Test at PKL Facility Using TRACE 5

January 18, 2019

Simulation of the PKL-G7.1 Experiment in a Westinghouse Nuclear Power Plant Using RELAP5/Mod3.3

Using SNAP/RADTRAD and HABIT to Establish the Analysis Methodology for Maanshan PWR

January 17, 2019

Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis

January 10, 2019

Validation of keff Calculations for Extended BWR Burnup Credit

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Page Last Reviewed/Updated Friday, June 07, 2019