An Assessment of Problems Associated with Tritium Containment

Sze, D.K.; Hassanein, A.; Piet, Steven J.; Wong, C.P.C.; Bjorndahl, W.D.

doi:10.13182/fst85-a24574

Cited by 7 publications

(2 citation statements)

References 6 publications

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“…Pressure driven permeation will cause problems with tritium containment. The key region in which this will be a problem is the main heat exchanger, where the requirement of good heat transfer also results in high mass transfer [61].…”

Section: Tritium Permeationmentioning

confidence: 99%

“…A recent measurement reported that pressure square root dependence was still obeyed at tritium partial pressures as low as 10~7 Pa [63] -far lower than predicted. The surface condition and the isotopic concentration [61,64] will all affect this relationship. The effect of surface condition is also important to plasma driven permeation, since it changes the recombination constant [59].…”

Section: Tritium Permeationmentioning

confidence: 99%

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Technical issues and requirements of experiments and facilities for fusion nuclear technology

et al. 1987

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The technical issues, development problems and required experiments and facilities for fusion nuclear technology have been investigated. The results have been used to develop a technical framework for a test plan that identifies the role, timing, characteristics and costs of major experiments and facilities. A major feature of this framework is the utilization of non-fusion facilities over the next 15 years, followed by testing in fusion devices beyond about the year 2000. Basic, separate effect and multiple interaction experiments in non-fusion facilities will provide property data, explore phenomena and provide input to theory and analytic modelling. Experiments in fusion facilities can proceed in two phases: (1) concept verification and (2) component reliability growth. Integrated testing imposes certain requirements on fusion testing device parameters; these requirements have been quantified. The nuclear subsystems addressed in the study are: (a) blanket and first wall; (b) tritium processing system; (c) plasma interactive components; and (d) radiation shield. The two generic classes of liquid and solid breeder blankets have significant engineering feasibility issues, and new experimental data must be obtained before selection of an attractive design concept. Liquid metal blanket issues are dominated by problems related to momentum, heat and mass transfer, which can be addressed in non-neutron test facilities. Solid breeder blanket issues are, however, dominated by the effects of radiation, including heating, transmutation and damage, which can be reasonably addressed in fission reactors. The tritium processing uncertainties are primarily related to the control and recovery systems, and most can be addressed in existing and planned non-neutron facilities. A dominant feature of plasma interactive components is the strong interrelation to both plasma physics and nuclear technology. Required facilities include thermomechanical test stands and confinement devices with sufficiently long plasma burn. The radiation shield poses no feasibility issues, but improved accuracy of predictions will reduce design conservatism and lower costs.

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Section: Tritium Permeationmentioning

confidence: 99%

Section: Tritium Permeationmentioning

confidence: 99%