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ASME - Page 42/50
Norma Técnica ASME STP-NU-018
Title:
Creep-Fatigue Data and Existing Evaluation Procedures for Grade 91 and Hastelloy XR
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-019-1
Title:
Verification of Allowable Stresses in ASME Section III Subsection NH for Grade 91 Steel
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-020
Title:
Verification of Allowable Stresses in ASME Section III, Subsection NH for Alloy 800H
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-035
Title:
Extend Allowable Stress Values for Alloy 800H
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-037
Title:
Operating Condition Allowable Stress Values in ASME Section III Subsection NH
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-038
Title:
ASME Code Considerations for the Intermediate Heat Exchanger (IHX)
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-039
Title:
Creep and Creep-Fatigue Crack Growth at Structural Discontinuities and Welds
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-040
Title:
Update and Improve Subsection NH - Simplified Elastic and Inelastic Design Analysis Methods
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-041
Title:
Update and Improve Subsection NH - Alternative Simplified Creep-Fatigue Design Methods
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-042
Title:
New Materials for ASME Subsection NH
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-044
Title:
Non Destructive Examination (NDE) and In-Service Inspection (ISI) Technology for High Temperature Reactors
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-045
Title:
Roadmap to develop ASME CODE Rules for the construction of high temperature gas cooled reactors (HTGRS)
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-045-1
Title:
Roadmap to Develop ASME Code Rules for the Construction of high Temperature Gas cooled Reactors (HTGRS)
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-051
Title:
Code Comparison Report for Class 1 Nuclear Power Plant Components
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-051-1
Title:
Code Comparison Report for Class 1 Nuclear Power Plant Components
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-057
Title:
ASME Code Development Roadmap for HDPE Pipe in Nuclear Service
Entity:
ASME
Subject:
Piping and couplings
Norma Técnica ASME STP-NU-059
Title:
Corrections to Stainless Steel Allowable Stresses
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-061
Title:
Comprehensive Evaluation of the NSQ-100 Nuclear Safety and Quality Management System Requirements
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-061-1
Title:
Comprehensive Evaluation of the NSQ-100 Nuclear Safety and Quality Management System Requirements
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-062
Title:
Comprehensive Comparison of International Quality Standards
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-062-1
Title:
Comprehensive Comparison of International Quality Standards
Entity:
ASME
Subject:
Nuclear power plants. Safety
Norma Técnica ASME STP-NU-063
Title:
Correct and Extend Allowable Stress Values for 304 and 316 Stainless Steel
Entity:
ASME
Subject:
Reactor engineering
Norma Técnica ASME STP-NU-067
Title:
Roadmap for the Development of ASME Code Rules for Fusion Energy Devices
Entity:
ASME
Subject:
Research and development
Norma Técnica ASME STP-NU-068
Title:
Corrosion of A193 Grade B7 Bolt Material in BWR Sodium Pentaborate Solutions
Entity:
ASME
Subject:
Bolts, screws, studs
Norma Técnica ASME STP-NU-069
Title:
Analysis of Selected Nondestructive Examination (NDE) Methodologies for the Assessment of Cracking in Concrete Containments
Entity:
ASME
Subject:
Reactor engineering
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