Tritium source terms for fusion power plants

Technical Report · Wed Sep 01 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/6439540· OSTI ID:6439540

Kabele, T J; Johnson, Jr, A B; Mudge, L K

The purpose of this study is to assess tritium control aspects of fusion reactors, to derive a preliminary estimate of the probable tritium releases and source terms under steady-state reactor operation, and to identify areas where advancement of fusion reactor tritium control technology will be required. Tritium release aspects of six fusion reactor conceptual designs were evaluated, including four Tokamaks, one mirror and one theta pinch reactor. The principal effort was directed to Tokamaks because they represent the current main-line Division of Magnetic Fusion Energy (DMFE) effort. Two tokamaks which had the most detailed conceptual designs at the time of the analysis (PPPL and UWMAK-I) were selected for detailed analysis to define tritium source terms.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• DOE Contract Number: EY-76-C-06-1830
• OSTI ID: 6439540
• Report Number(s): BNWL-2018
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CONTAINMENT
DIFFUSION
HAZARDS
HEALTH HAZARDS
HYDROGEN ISOTOPES
ISOTOPES
LEAKS
LIGHT NUCLEI
MAGNETIC MIRROR TYPE REACTORS
NUCLEI
ODD-EVEN NUCLEI
PERMEABILITY
PINCH EFFECT
RADIATION HAZARDS
RADIOISOTOPES
RECOVERY
THERMONUCLEAR REACTORS
THETA PINCH
TOKAMAK TYPE REACTORS
TOROIDAL PINCH TYPE REACTORS
TRITIUM
TRITIUM RECOVERY
YEARS LIVING RADIOISOTOPES