Challenges and Solutions for Fast Neutron Irradiation of Bulk Material Specimens
Reactor developers continue to recognize opportunities for further enhancing fast spectrum reactor designs with advanced core materials, but all the material test reactors currently available to the United States are thermal spectrum designs. Fortunately, the Advanced Test Reactor and High Flux Isotope Reactor are versatile high flux facilities where spectral modification strategies can be used […]
Neutron Irradiation & Thermomechanical Experiment (NITE) – design
For the reliable long-term operation of fusion power plants, it is crucial to understand and predict the lifetime of materials in use. These materials include all structural and functional materials utilized at the first wall, blanket, magnets, and shielding. The key challenge is, that the harsh environment including high heat fluxes, high thermal stress and […]
CCTE Irradiation Plan – PBNC 2024
This paper outlines the irradiation plan for the CCTE-ANEEL-1A experiment in the ATR including irradiation locations, test train geometry, and a summary of the experiment design analysis. ATR irradiation is expected to begin in Spring 2024, with burnup targets of 20, 40, and 60 GWd/MTU.
Irradiation Plan for a Mixed Thorium Uranium Oxide Drop In Experiment in the Advanced Test Reactor
This paper outlines the irradiation plan for the CCTE-ANEEL-1A experiment in the ATR including irradiation locations, test train geometry, and a summary of the experiment design analysis. ATR irradiation is expected to begin in Spring 2024, with burnup targets of 20, 40, and 60 GWd/MTU.
Innovative Nuclear Materials Outboard-A Project Specimen Preparation Guide
The Innovative Nuclear Materials (INM) Program was recently established by the U.S. Department of Energy (DOE) to develop advanced material technologies for use in nuclear reactors. The INM program is presently focused on researching in-core non-fueled materials for application in fast spectrum nuclear reactors. The widespread deployment of fast reactors continues to be a prominent […]
CCTE Pre-irradiation Characterization Report
The purpose of this report is to transmit pre-irradiation characterization data for fuel pellets being irradiated in the ATR to the irradiation customer.
Thermal Gradient and Neutron Irradiation Experiment Design for Fusion Reactor Materials in the Advanced Test Reactor
This work outlines a hypothetical coupled thermal gradient and neutron irradiation experiment in the Advanced Test Reactor (ATR) at the Idaho National Laboratory. Although the ATR is a thermal spectrum test reactor and doesn’t inherently produce a flux spectrum dominated by the high-energy neutrons typical in a fusion reactor, it’s multitude of experiment positions and […]
Fast Neutron Irradiation Capability in Existing Thermal Test Reactors
In today’s nuclear industry, momentum towards the design, licensing, and construction of advanced nuclear demonstration plants, including fast reactors, is at a remarkably high level. However, there are currently no dedicated fast spectrum irradiation test facilities in the United States to support the development of fast spectrum technologies. As a result, a unique situation is […]
CCTE-ANEEL-1A Irradiation Experiment Test Plan
Clean Core Thorium Energy (CCTE), LLC is committed to the development of alternative nuclear fuels using thorium, primarily for Pressurized Heavy-Water Reactors (PHWR) / Canada Deuterium Uranium (CANDU) reactors. CCTE requested Idaho National Laboratory (INL) support to conduct irradiation testing on various mixed thorium-uranium oxide ((Th,U)O2) fuel samples to help assess fuel performance. Experiment pellets […]
The Accident Tolerant Fuels’ Neutronics Scoping Study (ATF-2Pert)
This summary discusses an ongoing scoping study to better understand the neutronic characteristics surrounding the center flux trap of the advanced test reactor. This summary details the need for the study, the means by which it was carried out, the study’s results, and how the results benefit the accident tolerant fuels program.