Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components

B Barua, MC Messner, RI Jetter… - Pressure Vessels …, 2020 - asmedigitalcollection.asme.org
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 …

Non-axisymmetric buckling stress of axially compressed circular cylindrical shells: Closed-form and Simplified Formulae

AES Musa, OHA Dehwah… - Journal of …, 2023 - asmedigitalcollection.asme.org
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 …

Design rules for 316H nuclear components cladded with nickel or tungsten

B Barua, MC Messner, TL Sham, RI Jetter, Y Wang… - 2021 - osti.gov
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 …

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 …

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 …

[HTML][HTML] Designing Cladded Components for High Temperature Nuclear Service: Part II—Design Rules

B Barua, MC Messner, RI Jetter… - Journal of …, 2023 - asmedigitalcollection.asme.org
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 …

Designing Cladded Components for High Temperature Nuclear Service: Part I—Analysis Methods

MC Messner, B Barua, RI Jetter… - Journal of …, 2023 - asmedigitalcollection.asme.org
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 …

Identifying Limitations of ASME Section III Division 5 For Advanced SMR Designs

MC Messner, TL Sham, B Barua - 2021 - osti.gov
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 …