ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Jan 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
November 2025
Latest News
ORNL to partner with Type One, UTK on fusion facility
Yesterday, Oak Ridge National Laboratory announced that it is in the process of partnering with Type One Energy and the University of Tennessee–Knoxville. That partnership will have one primary goal: to establish a high-heat flux facility (HHF) at the Tennessee Valley Authority’s Bull Run Energy Complex in Clinton, Tenn.
K. L. Davis, D. L. Knudson, J. L. Rempe, J. C. Crepeau, S. Solstad
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 92-105
Technical Note | Materials for Nuclear Systems | doi.org/10.13182/NT14-60
Articles are hosted by Taylor and Francis Online.
New materials are being considered for fuel, cladding, and structures in next-generation and existing nuclear reactors. Such materials can undergo significant dimensional and physical changes during high-temperature irradiation. To accurately predict these changes, real-time data must be obtained under prototypic irradiation conditions for model development and validation. To provide these data, programs such as the Advanced Test Reactor (ATR) National Scientific Users Facility (NSUF) have funded researchers at the Idaho National Laboratory (INL) High Temperature Test Laboratory (HTTL) to develop several instrumented test rigs to obtain data in real time from specimens irradiated in well-controlled pressurized water reactor (PWR) coolant conditions in ATR. This technical note reports the status of INL efforts to develop and evaluate prototype test rigs that rely on linear variable differential transformers (LVDTs) in laboratory settings. Although similar LVDT-based test rigs have been deployed in lower-flux materials testing reactors (MTRs), this effort is unique because it relies on robust LVDTs that can withstand higher temperatures and higher fluxes than often found in other MTR irradiations. Specifically, the test rigs are designed for detecting changes in the length and diameter of specimens irradiated in ATR PWR loops. Once implemented, these test rigs will provide ATR users with unique capabilities that are sorely needed to obtain measurements, such as elongation caused by thermal expansion and/or creep loading, and diameter changes associated with fuel and cladding swelling, pellet-cladding interaction, and crud buildup.