Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components
The clad selection criteria proposed in this work supports a design approach provided in
[PVP2020-21469] for cladded component for high temperature nuclear service. The …
[PVP2020-21469] for cladded component for high temperature nuclear service. The …
Non-axisymmetric buckling stress of axially compressed circular cylindrical shells: Closed-form and Simplified Formulae
Due to their thin-walled characteristics, axially loaded circular cylindrical shells (CCSs)
commonly undergo buckling failure. The limiting buckling stress of such shells has not yet …
commonly undergo buckling failure. The limiting buckling stress of such shells has not yet …
Design rules for 316H nuclear components cladded with nickel or tungsten
The existing Class A metallic materials qualified in the ASME Boiler & Pressure Vessel Code
Section III, Division 5 rules for high temperature nuclear reactors are not ideally suited for …
Section III, Division 5 rules for high temperature nuclear reactors are not ideally suited for …
Preliminary Procedures and Acceptance Criteria for in-situ Structural Materials Surveillance for MSR
MC Messner, TL Sham - 2021 - osti.gov
This report describes the initial development of the technical basis for a materials
surveillance technology that, when fully developed and validated, can be used by …
surveillance technology that, when fully developed and validated, can be used by …
Fracture Toughness Evaluation of the Heat-Affected Zone Under the Weld Overlay Cladding in Reactor Pressure Vessel Steel
Y Ha, T Tobita, H Takamizawa… - Journal of …, 2023 - asmedigitalcollection.asme.org
The fracture toughness in the heat-affected zone (HAZ), which is located under the weld
overlay cladding on the inner surface of the reactor pressure vessel (RPV), was evaluated …
overlay cladding on the inner surface of the reactor pressure vessel (RPV), was evaluated …
[HTML][HTML] Designing Cladded Components for High Temperature Nuclear Service: Part II—Design Rules
The challenge of using existing ASME Section III, Division 5, class A metallic materials for
the construction of structural components of advanced reactors with corrosive coolants could …
the construction of structural components of advanced reactors with corrosive coolants could …
Designing Cladded Components for High Temperature Nuclear Service: Part I—Analysis Methods
Use of corrosion-resistant cladding can greatly extend the design life of structural
components in many advanced reactor systems. However, there are currently no ASME …
components in many advanced reactor systems. However, there are currently no ASME …
Identifying Limitations of ASME Section III Division 5 For Advanced SMR Designs
This report provides an overview of the ASME Boiler & Pressure Vessel Section III, Division
5 rules for the design and construction of high temperature nuclear reactor components. The …
5 rules for the design and construction of high temperature nuclear reactor components. The …