U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.
Resource Information
The organization U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
The Resource
U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.
Resource Information
The organization U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
- Label
- U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.
- Authority link
- (EG-IN)1310199
- Subordinate unit
- Office of Nuclear Regulatory Research.
107 Items by the Organization U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.
Context
Context of U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.Creator of
No resources found
No enriched resources found
- A report to Congress on nuclear regulatory research : project descriptions for FY ...
- Disposition of recommendations of the National Research Council in the report Revitalizing nuclear safety research
- Draft Regulatory Guide DG-1149 : qualification of safety-related motor control centers for nuclear power plants
- Draft Regulatory Guide DG-1198 : physical models for design and operation of hydraulic structures and systems for nuclear power plants
- Draft Regulatory Guide DG-1203 : containment performance for pressure loads
- Draft Regulatory Guide DG-1205 : bypassed and inoperable status indication for nuclear power plant safety systems
- Draft regulatory guide DG-1077 : guidelines for environmental qualification of microprocessor-based equipment important to safety in nuclear power plants
- Draft regulatory guide DG-1107 : water sources for long-term recirculation cooling following a loss-of-coolant accident : (proposed revision 3 to Regulatory Guide 1.82)
- Draft regulatory guide DG-1129 : criteria for independence of electrical safety systems
- Draft regulatory guide DG-1132 : qualification of safety-related cables and field splices for nuclear power plants
- Draft regulatory guide DG-1139 : risk-informed, performance-based fire protection for existing light-water nuclear power plants
- Draft regulatory guide DG-1142 : guidelines for environmental qualification of safety-related computer-based instrumentation and control systems in nuclear power plants
- Draft regulatory guide DG-1144 : guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors
- Draft regulatory guide DG-1146 : a performance-based approach to define the site-specific earthquake ground motion
- Draft regulatory guide DG-1175 : seismic qualification of electric and active mechanical equipment and functional qualification of active mechanical equipment for nuclear power plants
- Draft regulatory guide DG-1178 : instrument sensing lines
- Draft regulatory guide DG-1186 : measuring, evaluating, and reporting radioactive material in liquid and gaseous effluents and solid waste
- Draft regulatory guide DG-1187 : concrete radiation shields and generic shield testing for nuclear power plants
- Draft regulatory guide DG-1189 : an acceptable model and related statistical methods for the analysis of fuel densification
- Draft regulatory guide DG-1195 : availability of electric power sources
- Draft regulatory guide DG-1200 : an approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities
- Draft regulatory guide DG-7004 : establishing quality assurance programs for packaging used in the transport of radioactive material
- EPRI/NRC-RES fire PRA methodology for nuclear power facilities : final report
- General site suitability criteria for nuclear power stations
- Long-range research plan
- Regulatory Guide 1.200 : an approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities
- Regulatory Guide 1.201 : guidelines for categorizing structures, systems, and components in nuclear power plants according to their safety significance
- Regulatory Guide 1.202 : standard format and content of decommissioning cost estimates for nuclear power reactors
- Regulatory Guide 1.203 : transient and accident analysis methods
- Regulatory Guide 1.205 : risk-informed, performance-based fire protection for existing light-water nuclear power plants
- Regulatory Guide 1.207 : guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors
- Regulatory Guide 1.208 : a performance-based approach to define the site-specific earthquake ground motion
- Regulatory Guide 1.209 : guidelines for environmental qualification of safety-related computer-based instrumentation and control systems in nuclear power plants
- Regulatory analysis technical evaluation handbook : draft report
- Regulatory guide 1.100 (task EE 108-5) : seismic qualification of electric and mechanical equipment for nuclear power plants
- Regulatory guide 1.105 : (draft was DG-1045) : setpoints for safety-related instrumentation
- Regulatory guide 1.105, (Task IC 010-5) : instrument setpoints for safety-related systems
- Regulatory guide 1.147 : inservice inspection code case acceptability, ASME Section XI Division 1
- Regulatory guide 1.147 : inservice inspection code case acceptability, ASME section XI division 1
- Regulatory guide 1.153, (Task IC 609-5) : criteria for power, instrumentation, and control portions of safety systems
- Regulatory guide 1.155 (task SI 501-4) : station blackout
- Regulatory guide 1.156 (task EE 404-4) : environmental qualification of connection assemblies for nuclear power plants
- Regulatory guide 1.161 : (draft was DG-1023) : evaluation of reactor pressure vessels with charpy upper-shelf energy less than 50 ft.-lb
- Regulatory guide 1.168 (draft was issued as DG-1123) : verification, validation, reviews, and audits for digital computer software used in safety systems of nuclear power plants
- Regulatory guide 1.170 : software test documentation for digital computer software used in safety systems of nuclear power plants
- Regulatory guide 1.171 : software unit testing for digital computer software used in safety systems of nuclear power plants
- Regulatory guide 1.172 : software requirements specifications for digital computer software used in safety systems of nuclear power plants
- Regulatory guide 1.173 : developing software life cycle processes for digital computer software used in safety systems of nuclear power plants
- Regulatory guide 1.174 : an approach for using probabilistic risk assessment in risk-informed decisions on plant-specific changes to the licensing basis
- Regulatory guide 1.175 (draft was issued as DG-1062) : an approach for plant-specific, risk-informed decisionmaking: inservice testing
- Regulatory guide 1.175 : an approach for plant-specific, risk-informed decisionmaking: inservice testing
- Regulatory guide 1.177 (draft was issued as DG-1065) : an approach for plant-specific, risk-informed decisionmaking : technical specifications
- Regulatory guide 1.177 : an approach for plant-specific, risk-informed decisionmaking : technical specifications
- Regulatory guide 1.178 : an approach for plant-specific risk-informed decisonmaking for inservice inspection of piping
- Regulatory guide 1.179 (draft was issued as DG-1079) : standard format and content of license termination plans for nuclear reactors
- Regulatory guide 1.179 : standard format and content of license termination plans for nuclear power reactors
- Regulatory guide 1.180 : guidelines for evaluating electromagnetic and radio-frequency interference in safety-related instrumentation and control systems
- 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)
- Regulatory guide 1.181 : content of the updated final safety analysis report in accordance with 10 CFR 50.71 (e)
- Regulatory guide 1.182 : assessing and managing risk before maintenance activities at nuclear power plants
- Regulatory guide 1.183 (draft was issued as DG-1081) : alternative radiological source terms for evaluating design basis accidents at nuclear power reactors
- Regulatory guide 1.183 : alternative radiological source terms for evaluating design basis accidents at nuclear power reactors
- Regulatory guide 1.184 (draft was issued as DG-1067) : decommissioning of nuclear power reactors
- Regulatory guide 1.184 : decommissioning of nuclear power reactors
- Regulatory guide 1.185 (draft was issued as DG-1071) : standard format and content for post-shutdown decommissioning activities report
- Regulatory guide 1.185 : standard format and content for post-shutdown decommissioning activities report
- Regulatory guide 1.186 (draft was issued as DG-109) : guidance and examples for identifying 10 CFR 50.2 design bases
- Regulatory guide 1.186 : guidance and examples for identifying 10 CFR 50.2 design bases
- Regulatory guide 1.187 (draft was issued as DG-1095) : guidance for implementation of 10 CFR 50.59, changes, tests, and experiments
- Regulatory guide 1.187 : guidance for implementation of 10 CFR 50.59, changes, tests, and experiments
- Regulatory guide 1.188 : standard format and content for applications to renew nuclear power plant operating licenses
- Regulatory guide 1.190 : calculational and dosimetry methods for determining pressure vessel neutron fluence
- Regulatory guide 1.191 : fire protection program for nuclear power plants during decommissioning and permanent shutdown
- Regulatory guide 1.192 : operation and maintenance code case acceptability, ASME OM code
- Regulatory guide 1.193 : ASME code cases not approved for use
- Regulatory guide 1.194 : atmospheric relative concentrations for control room radiological habitability assessments at nuclear power plants
- Regulatory guide 1.195 : methods and assumptions for evaluating radiological consequences of design basis accidents at light-water nuclear power reactors
- Regulatory guide 1.196 : control room habitability at light-water nuclear power reactors
- Regulatory guide 1.197 : demonstrating control room envelope integrity at nuclear power reactors
- Regulatory guide 1.198 : procedures and criteria for assessing seismic soil liquefaction at nuclear power plant sites
- Regulatory guide 1.199 : anchoring components and structural supports in concrete
- Regulatory guide 1.204 : guidelines for lightning protection of nuclear power plants
- Regulatory guide 1.54 : service level I, II, and III protective coatings applied to nuclear power plants
- Regulatory guide 1.57 : design limits and loading combinations for metal primary reactor containment system components
- Regulatory guide 1.61 : damping values for seismic design of nuclear power plants
- Regulatory guide 1.68 : initial test programs for water-cooled nuclear power plants
- Regulatory guide 1.8, (Task OL 403-5) : qualification and training of personnel for nuclear power plants
- Regulatory guide 1.82 : water sources for long-term recirculation cooling following a loss-of-coolant accident
- Regulatory guide 1.82, (Task MS 203-4) : water sources for long-term recirculation cooling following a loss-of-coolant accident
- Regulatory guide 1.84 : design and fabrication code case acceptability, ASME Section III Division 1
- Regulatory guide 1.85 : materials code case acceptability, ASME Section III Division 1
- Regulatory guide 1.85 : materials code case acceptability, ASME Section III Division 1
- Regulatory guide 1.85 : materials code case acceptability, ASME Section III, Division 1
- Regulatory guide 10.11 (Task FC 603-4) : guide for the preparation of applications for radiation safety evaluation and registration of sealed sources containing byproduct material
- Regulatory guide 3.44, (Task CE 403-4) : standard format and content for the safety analysis report for an independent spent fuel storage installation (water-basin type)
- Regulatory guide 3.45, (Task CE 802-5) : nuclear criticality safety for steel-pipe intersections containing aqueous solutions of fissile materials
- Regulatory guide 3.52, (Task CE 308-4) : standard format and content for the health and safety sections of license renewal applications for uranium processing and fuel fabrication
- Regulatory guide 3.58, (Task CE 407-4) : criticality safety for handling, storing, and transporting LWR fuel at fuels and materials facilities
- Regulatory guide 3.59, (Task WM 407-4) : methods for estimating radioactiave and toxic airborne source terms for uranium milling operations
- Regulatory guide 3.60, (Task CE 410-4); : design of an independent spent fuel storage installation (dry storage)
- Regulatory guide 3.61, (Task CE 306-4) : standard format and content for a topical safety analysis report for a spent fuel dry storage cask
- Regulatory guide 3.64, (Task WM 503-4) : calculation of radon flux attenuation by earthen uranium mill tailings covers
- Regulatory guide 3.66, (Task DG-3002) : standard format and content of financial assurance mechanisms required for decommissioning under 10 CFR parts 30, 40, 70, and 72
- Regulatory guide 4.19, (Task WM 408-4) : guidance for selecting sites for near-surface disposal of low-level radioactive waste
- Regulatory guide 5.65 : vital area access controls, protection of physical security equipment, and key and lock controls (Task SG 302-4)
- Regulatory guide 7.10 : establishing quality assurance programs for packaging used in the transport of radioactive material
- The Browns Ferry Nuclear Plant fire of 1975 and the history of NRC fire regulations
Embed
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.library.in.gov/resource/XOPNDkw47E0/" typeof="Organization http://bibfra.me/vocab/lite/Organization"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/XOPNDkw47E0/">U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.library.in.gov/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.library.in.gov/">Indiana State 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, Office of Nuclear Regulatory Research.
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.library.in.gov/resource/XOPNDkw47E0/" typeof="Organization http://bibfra.me/vocab/lite/Organization"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/XOPNDkw47E0/">U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research.</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.library.in.gov/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.library.in.gov/">Indiana State Library</a></span></span></span></span></div>
