Tritium is the main fuel ingredient in the plasma of MFE and IFE systems based on the D-T fuel cycle. Since tritium is not a naturally existing isotope, attaining tritium selfsufficiency is necessary for self-sustaining fusion plants operating on the D-T fuel cycle. Tritium is bred in a lithium-containing blanket surrounding the plasma. Once tritium is generated, it needs to be collected, proce...

Direct measurement of tritium atoms by accelerator mass spectrometry (AMS) enables rapid low-activity tritium measurements from milligram-sized samples and permits greater ease of sample collection, faster throughput, and increased spatial and/or temporal resolution. Because existing methodologies for quantifying tritium have some significant limitations, the development of tritium AMS has allo...

Tritium released into the environment may be incorporated into organic matter. Organically bound tritium in that case will show retention times in organisms that are considerably longer than those of tritiated water which has significant consequences on dose estimates. This article reviews the most important processes of organically bound tritium production and transport through food networks. ...

Detailed three-dimensional (3-D) neutronics calculations have been performed for the dual coolant molten salt blanket designs. The model includes the detailed heterogeneous geometrical arrangement of the inboard (IB) and outboard (OB) blanket sectors. The total tritium breeding ratio (TBR) is ~1.07. The 1-D calculations tend to overestimate nuclear heating in the blanket by ~8% resulting in ove...

Tritium behavior in the breeder/coolant plays a crucial role in keeping the tritium loss under an allowable limit and realizing high tritium recovery efficiency. In this paper, progress toward the development of a comprehensive 3D predictive capability is discussed and presented. The sequence of transport processes leading to tritium release includes diffusion and convection through the PbLi, t...

We develop a general equation for converting laboratory-reported tritium levels, expressed either as concentrations (tritium isotope number fractions) or mass-based specific activities, to mass fractions in aqueous systems. Assuming that all tritium is in the form of monotritiated water simplifies the derivation and is shown to be reasonable for most environmental settings encountered in practi...

The JAERI /USDOE collaborative program is going on using the FNS facility at JAERI. The phase-III is a new series on tritium breeding measurements with a totally different experimental arrangement from the previous ones that used a point neutron source geometry. The new series basically consists of an annular test blanket and a pseudo-line source to investigate the effect of source spread on th...

Abstract The nuclear fusion waste generated by the activation of constitutent components Korean DEMOnstration reactor (K-DEMO) is assessed after end life (EOL). Based on results, an attempt made to classify radioactive (RW) according regulations RW classification and self-disposal standards. One hundred years EOL, most (∼90%) reduced ferritic/martensitic steel structures in tritium-breeding bla...

An engineering scaling process is applied to the solid breeder ITER TBM designs in accordance with the testing objectives of validating the design tools and the database, and evaluating blanket performance under prototypical operating conditions. The goal of scaling is to ensure that changes in structural response and performance caused by changes in size and operating conditions do not reduce ...