TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

Abstract

Abstract:The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high-temperature operating regimes. This paper outlines the unique qualification and validation processes developed in the U.S., offering the only access to the complete fusion environment, focusing on the most prominent U.S. blanket concept (the dual cooled PbLi (DCLL)) along with testing new generations of structural and functional materials in dedicated test modules. The venue for such activities is the proposed Fusion Nuclear Science Facility (FNSF), which is viewed as an essential element of the U.S. fusion roadmap. A staged blanket testing strategy has been developed to test and enhance the DCLL blanket performance during each phase of FNSF D-T operation. A materials testing module (MTM) is critically important to include in the FNSF as well to test a broad range of specimens of future, more advanced generations of materials in a relevant fusion environment. The most important attributes for MTM are the relevant He/dpa ratio (10-15) and the much larger specimen volumes compared to the 10-500 mL range available in the International Fusion Materials Irradiation Facility (IFMIF) and European DEMO-Oriented Neutron Source (DONES).

Compact steady-state tokamak performance dependence on magnet and core physics limits

“…For HTS TF magnets, sufficient shielding is required to protect against both nuclear heating and/or neutron damage. Detailed calculations including ferritic steel structure (which has lower neutron attenuation) to support and contain a WC shield and water coolant indicate shield-averaged attenuation decay lengths of 15–16 cm per decade, and this results in a requirement for approximately 60 cm of cooled WC shield (or equivalent shielding) to protect the HTS TF magnet in a device that can achieve a peak outboard neutron fluence of 7 MW yr m −2 [22,23]. These results motivate the inboard WC shielding thickness of 60 cm at A = 1.8 as shown in figure 1 a .…”

Feasibility Study of Low Mass and Low Energy Consumption Drilling Devices for Future Space (Mining Surveying) Missions

“…Since the publication of article [16], the world has made great progress in hightemperature superconductor technology (necessary for plasma stabilization) and in the work on controlled thermonuclear fusion. Some of these works have been described in publications [20][21][22][23][24][25][26][27][28][29][30][31]. In [22], the use of electric energy from fusion in transport in Europe is modeled.…”