D-T Fusion Bridge Program

Intelligence Summary: D-T Fusion Bridge Program

Node Identity China's Deuterium-Tritium (D-T) Fusion Bridge Program represents the strategic intermediate step between current tokamak-based magnetic confinement fusion (MCF) research and advanced aneutronic fusion concepts (p-B11, D-3He) pursued for weapons-relevant applications. This "White Track" node captures China's systematic approach to building plasma physics infrastructure, tritium handling expertise, and high-field magnet technology through the D-T fusion pathway — capabilities that directly underpin the FRC weapons program even though D-T fusion itself is not the weapons end-state.

Strategic Relevance D-T fusion serves as the technological bridge because it is the easiest fusion reaction to achieve (lowest temperature threshold ~100 million K) and provides the infrastructure for tritium breeding, remote handling of radioactive materials, and high-temperature plasma operation. These capabilities are prerequisites for any advanced fusion weapons system. The EAST tokamak at ASIPP (Hefei) has achieved world-record plasma durations (over 1000 seconds), providing the sustained plasma experience that informs FRC stability research. The HL-2A/HL-2M tokamak at SWIP provides complementary high-temperature plasma data. CFETR (China Fusion Engineering Testing Reactor) will be the world's first fusion engineering test reactor, providing tritium breeding and blanket technology at scale. ITER participation gives China access to international tritium handling technology at weapons-relevant scale (~2 kg inventory).

Technical Focus / Capabilities The D-T Bridge Program encompasses: (1) EAST Tokamak — superconducting tokamak achieving 1.2 T field, 100+ second H-mode plasmas, providing data on plasma stability, edge-localized modes (ELMs), and divertor physics directly applicable to FRC confinement; (2) HL-2A/HL-2M Tokamak — medium-size tokamak with advanced divertor configurations and NBI heating, studying plasma-wall interactions and impurity transport; (3) CFETR — next-step burning plasma device designed to demonstrate tritium self-sufficiency and steady-state operation; (4) Tritium handling infrastructure — China National Nuclear Corporation (CNNC) provides the nuclear fuel cycle expertise for tritium production, storage, and containment. The D-T program also develops superconducting magnet technology, cryogenic systems, and radiation-hardened diagnostics — all dual-use with the FRC weapons program.

Network Linkage The D-T Bridge Program uses the EAST Tokamak (ASIPP/Hefei) and HL-2A/HL-2M Tokamak (SWIP) as primary experimental platforms. CFETR represents the next-generation facility that will scale D-T fusion to engineering relevance. China National Nuclear Corporation (CNNC) researches tritium handling and nuclear fuel cycle aspects. The program connects indirectly to the FRC weapons pipeline through shared superconducting magnet technology, cryogenic control systems, plasma diagnostics, and computational plasma simulation capabilities. ITER Participation provides the international technology transfer channel that feeds D-T expertise back into domestic programs.