WorldCat Identities

U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research

Overview
Works: 2,300 works in 3,203 publications in 1 language and 106,617 library holdings
Genres: Periodicals 
Roles: Researcher, Funder, Sponsor
Classifications: TK9152, 363.179
Publication Timeline
.
Most widely held works about U.S. Nuclear Regulatory Commission
 
moreShow More Titles
fewerShow Fewer Titles
Most widely held works by U.S. Nuclear Regulatory Commission
Report to Congress on abnormal occurrences( )

in English and held by 654 WorldCat member libraries worldwide

Regulatory guide 1.183 alternative radiological source terms for evaluating design basis accidents at nuclear power reactors by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 2000 in English and held by 236 WorldCat member libraries worldwide

PRA procedures guide : a guide to the performance of probabilistic risk assessments for nuclear power plants( Book )

4 editions published in 1983 in English and held by 85 WorldCat member libraries worldwide

Regulatory guide 1.185 (draft was issued as DG-1071) standard format and content for post-shutdown decommissioning activities report by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 2000 in English and held by 77 WorldCat member libraries worldwide

Regulatory guide 1.187 (draft was issued as DG-1095) guidance for implementation of 10 CFR 50.59, changes, tests, and experiments by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 2000 in English and held by 77 WorldCat member libraries worldwide

Regulatory guide 1.184 (draft was issued as DG-1067) decommissioning of nuclear power reactors by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 2000 in English and held by 77 WorldCat member libraries worldwide

Regulatory guide 1.186 (draft was issued as DG-109) guidance and examples for identifying 10 CFR 50.2 design bases by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 2000 in English and held by 75 WorldCat member libraries worldwide

Regulatory guide 1.177 (draft was issued as DG-1065) an approach for plant-specific, risk-informed decisionmaking : technical specifications by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 1998 in English and held by 70 WorldCat member libraries worldwide

Regulatory guide 1.181 (draft was issued as DG-1083) content of the updated final safety analysis report in accordance with 10 CFR 50.71 (e) by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 1999 in English and held by 69 WorldCat member libraries worldwide

Regulatory guide 1.175 (draft was issued as DG-1062) an approach for plant-specific, risk-informed decisionmaking: inservice testing by U.S. Nuclear Regulatory Commission( Book )

2 editions published in 1998 in English and held by 68 WorldCat member libraries worldwide

Improvement of RELAP5/MOD3.3 reflood model based on the assessments against FLECHT-SEASET tests( Book )

2 editions published in 1983 in English and held by 40 WorldCat member libraries worldwide

Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments by O. K Chopra( Book )

2 editions published in 2008 in English and held by 35 WorldCat member libraries worldwide

In light water reactors, austenitic stainless steels (SSs) are used extensively as structural alloys in reactor core internal components because of their high strength, ductility, and fracture toughness. However, exposure to high levels of neutron irradiation for extended periods degrades the fracture properties of these steels by changing the material microstructure (e.g., radiation hardening) and microchemistry (e.g., radiation-induced segregation). Experimental data are presented on the fracture toughness and crack growth rates (CGRs) of wrought and cast austenitic SSs, including weld heat-affected-zone materials, that were irradiated to fluence levels as high as H"2x 10 n/cm (E> 1 MeV) (H"3 dpa) in a light water reactor at 288-300 C. The results are compared with the data available in the literature. The effects of material composition, irradiation dose, and water chemistry on CGRs under cyclic and stress corrosion cracking conditions were determined. A superposition model was used to represent the cyclic CGRs of austenitic SSs. The effects of neutron irradiation on the fracture toughness of these steels, as well as the effects of material and irradiation conditions and test temperature, have been evaluated. A fracture toughness trend curve that bounds the existing data has been defined. The synergistic effects of thermal and radiation embrittlement of cast austenitic SS internal components have also been evaluated
Crack growth rates and metallographic examinations of alloy 600 and alloy 82/182 from field components and laboratory materials tested in PWR environments by B Alexandreanu( Book )

2 editions published in 2008 in English and held by 35 WorldCat member libraries worldwide

In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the order of 220-230 kJ/mol, higher than the 130 kJ/mol commonly used for Alloy 600. The consequences of using a larger value of activation energy for SCC CGR data analysis are discussed
The Browns Ferry Nuclear Plant fire of 1975 knowledge management digest by Felix E Gonzalez( Book )

2 editions published in 2013 in English and held by 7 WorldCat member libraries worldwide

Fuel behavior under abnormal conditions by R. O Meyer( Book )

2 editions published in 2013 in English and held by 6 WorldCat member libraries worldwide

Three Mile Island accident of 1979 knowledge management digest by U.S. Nuclear Regulatory Commission( Book )

4 editions published between 2012 and 2013 in English and held by 6 WorldCat member libraries worldwide

Nuclear power plant fire modeling application guide : draft report for comment( Book )

3 editions published between 2010 and 2011 in English and held by 4 WorldCat member libraries worldwide

Processes, properties, and conditions controlling in situ bioremediation of uranium in shallow, alluvial aquifers( Book )

2 editions published in 2010 in English and held by 2 WorldCat member libraries worldwide

Essential elements of an electric cable condition monitoring program by M Villaran( Book )

2 editions published in 2010 in English and held by 2 WorldCat member libraries worldwide

 
moreShow More Titles
fewerShow Fewer Titles
Audience Level
0
Audience Level
1
  Kids General Special  
Audience level: 0.51 (from 0.46 for Report to ... to 0.80 for A report t ...)

Alternative Names
U.S. Nuclear Regulatory Commission. Office for Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Research

U.S. Nuclear Regulatory Commission. Office of Nuclear Research

U.S. Nuclear Regulatory Commission. Office of Research

United States. Office of Nuclear Regulatory Research

Languages
English (59)