Design and Laboratory Evaluation of Future Elongation and Diameter Measurements at the Advanced Test Reactor

Davis, K. L.; Knudson, D. L.; Rempe, J. L.; Crepeau, John; Solstad, S.

doi:10.13182/nt14-60

Cited by 6 publications

(4 citation statements)

References 5 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…They could prove useful to also study material properties of the loop structural material not included in Table 3, such as creep rate (this could be addressed in out-of-pile experiments however). While these types of measurements have been conducted in the past, the experiments were only under dry conditions [16]. The electric potential of the salt renders measurement more difficult than what was previous considered.…”

Section: In Situ Instrumentationmentioning

confidence: 99%

See 1 more Smart Citation

Evaluation of a Versatile Experimental Salt Irradiation Loop (VESIL) inside the Advanced Test Reactor

Abou-Jaoude

Sterbentz

Palmer

et al. 2019

View full text Add to dashboard Cite

A Versatile Experimental Salt Irradiation Loop (VESIL) is under investigation at Idaho National Laboratory. An initial feasibility study was conducted for potential deployment inside the Advanced Test Reactor (ATR). Historical salt-irradiation tests are reviewed and summarized in this report. The study also surveys available instrumentation for this type of application and identifies key design and testing requirements. Neutronic analysis was performed in different ATR position for various salt candidates using MCNP6 and ORIGEN-6.2. The results indicate that both the B and I-positions are suitable for VESIL. The B-position allows for accelerated testing in light of its higher flux, but its smaller volume may be detrimental for a flowing loop. The O-position flux level was found to be insufficient for the purposes of this experiment; it is not recommended. In all the different salt candidates investigated, both the B and I-positions are found to able to reach adequate burnup conditions that are representative of the operating conditions inside proposed molten-salt reactor concepts.

show abstract

Section: In Situ Instrumentationmentioning

confidence: 99%

“…Figure16. Impact of37 Cl enrichment in REBUS salt on sulfur production from35 Cl transmutation rate.…”

mentioning

confidence: 99%

Evaluation of a Versatile Experimental Salt Irradiation Loop (VESIL) inside the Advanced Test Reactor

Abou-Jaoude

Sterbentz

Palmer

et al. 2019

View full text Add to dashboard Cite

show abstract

“…Such a demonstration would provide an important capability to Department of Energy Office of Nuclear Energy programs and their stakeholders, partially replacing those testing capabilities lost due to the termination of HBWR operations. This is particularly relevant in light of the current plans to install water loops in the Advanced Test Reactor (ATR) I-positions in order to mimic the lost Halden capabilities [3,4,5].…”

Section: Introductionmentioning

confidence: 99%

Development of Real-Time, In-pile Creep Test Rigs for Characterizing the Structural Materials of Nuclear Components

Wilding

McMurtrey

Crawford

et al. 2021

View full text Add to dashboard Cite

New and improved materials are being considered for supporting both existing and next-generation nuclear reactors. Reactor materials can significantly degrade with time, thus limiting or altering their properties in harsh reactor environments. To accurately understand such material degradation, real-time data obtained under prototypic irradiation conditions are required. In particular, understanding the creep behavior of materials exposed to irradiation and elevated temperatures is essential for safety concern evaluations. To provide these capabilities, Idaho National Laboratory (INL)'s High Temperature Test Laboratory (HTTL) developed several instrumented test rigs for obtaining real-time data from specimens in well-controlled pressurized-water reactor (PWR) coolant conditions at the Materials Test Reactor. This technical report focuses on INL's efforts to evaluate and enhance the former creep test rig prototype that relied on linear variable differential transformers in laboratory settings. Specifically, the test rig can detect changes in the length of creep specimens, which is useful for measuring thermal expansion and creep deformation.vii

show abstract

“…Such a demonstration would afford an important capability to the Department of Energy (DOE) Office of Nuclear Energy (NE) programs and their stakeholders, partially replacing the testing capabilities lost along with the termination of HBWR operations. This is particularly relevant, given the plans to install water loops in the Advanced Test Reactor (ATR) I-positions in order to mimic the lost Halden capabilities [3,4,5].…”

Section: Introductionmentioning

confidence: 99%

Out-of-Pile Test of LVDT-Based Creep Test Rig at PWR Prototypical Conditions

Wilding

Davis

Skifton

et al. 2021

View full text Add to dashboard Cite

New and improved materials are being considered to support the existing nuclear reactors and future next-generation reactors. The materials can significantly degrade and limit their properties in harsh reactor environments. To accurately understand the material's degradation, real-time data is required under prototypic-irradiation conditions. Additionally, understanding the creep behavior of materials under harsh environments is essential for an evaluation of safety concerns. To provide these capabilities, the Idaho National Laboratory's (INL's) High Temperature Test Laboratory (HTTL) has developed several instrumented test rigs to obtain real-time data from specimens in well-controlled pressurized water reactor (PWR) coolant conditions in the Materials and Test Reactors (MTRs). This technical report focuses on INL's efforts to evaluate and enhance the former prototype creep test rig that relied on linear variable differential transformers in laboratory settings. Specifically, the test rig is capable of detecting changes in the length of tensile specimen, which is useful for measuring thermal expansion and creep loading.

show abstract

Design and Laboratory Evaluation of Future Elongation and Diameter Measurements at the Advanced Test Reactor

Cited by 6 publications

References 5 publications

Evaluation of a Versatile Experimental Salt Irradiation Loop (VESIL) inside the Advanced Test Reactor

Evaluation of a Versatile Experimental Salt Irradiation Loop (VESIL) inside the Advanced Test Reactor

Development of Real-Time, In-pile Creep Test Rigs for Characterizing the Structural Materials of Nuclear Components

Out-of-Pile Test of LVDT-Based Creep Test Rig at PWR Prototypical Conditions

Contact Info

Product

Resources

About