Irradiation study of lithium compound samples for tritium breeding application

Yang, Lǜ; Medico, R.; Baugh, W.; Schultz, Kenneth R.

doi:10.1016/0022-3115(82)90662-6

Cited by 25 publications

(6 citation statements)

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“…The last six runs (28)(29)(30)(31)(32)(33) appear to be diffusion controlled. The agreement between the calculated diffusivities for Runs 1-8, 28-33, and the derived diffusivity relationship [Eq.…”

Section: Ix-4mentioning

confidence: 99%

TRIO experiment

Clemmer¹,

Finn²,

Malecha³

et al. 1984

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A~l REFERENCES R-l ACKNOWLEDGMENTS a SECTION I INTRODUCTION I. INTRODUCTION Lithium aluminate, LiA10 2 > is representative of a group of ceramics, called the "Solid Breeders/ , that are candidate materials for use as the tritium breeding medium in fusion reactors. In the past several years, a number of conceptual blanket designs for fusion reactors have used solid breeders, and the data base has been reviewed. Although the data base is limited, experimental programs are in progress and more results are becoming available.25-39 Tne so i±& breeders include Li 2 O, LiA10 2 , LL 2 Zr0 3 , Li^SiOjj, and Li 2 Si0 3 . The ternary oxides, in general, have much better chemical and thermophysical stability than Li 2 O, but owing to its high lithium atom density, Li 2 O has better tritium breeding potential. The TRIO experiment involved the irradiation of IAAIO2 in the Oak Ridge Research Reactor (ORR) under well-defined conditions of temperature, neutron flux, sweep gas flow, and sample configuration. Lithium aluminate was selected for the experiment because of its attractive properties (discussed later). Tritium, in its various chemical forms (and other gases evolved from the LiA10 2 during irradiation), was moved by a sweep gas to an analytical train in which measurements on the composition of the effluent were performed. 1-1 SECTION II PURPOSE II-l determine values of heat transfer coefficients and thermal conductivity of the LiA10 2 and to access the effects of radiation damage upon these values* (4) Measure tritium permeation through primary cladding. A measurable quantity of tritium may permeate through the primary cladding into the gas gap of the breeder capsule. This tritium which permeates will be collected and assayed. (5) Investigate the form of the tritium species (e.g., 'lyJrT, ratio) in the sweep gas stream. The amount of tritium released in each chemical form is to be quantitatively determined. (6) Establish the methodology for in-pile testing. This experiment is the first truly comprehensive test of in-situ tritium recovery from solid breeders. Thus, a methodology for this kind of test will be developed. (7) Measure radioactive species in the sweep gas stream. Certain impurities in the LiA10 2 (e .g., uranium, potassium, sodium, chlorine, etc.) produce volatile radionuclides during irradiation. These will be quantified to ensure that tritium monitoring is not affected. In addition, transport data on other species (mostly nobel gases), which may provide some insight into transport of helium, will be obtained.

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Section: Ix-4mentioning

confidence: 99%

TRIO experiment

Clemmer¹,

Finn²,

Malecha³

et al. 1984

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“…Two configurations for solid breeders have been considered: pressed and sintered pellets and sphere-pac. Gold pressing and sintering techniques were developed for LijO, Li^SiO^, and 7-L1A102 samples irradiated in ORE [16] and EBR-II irradiation experiments [17].…”

Section: Introductionmentioning

confidence: 99%

Materials data base and design equations for the UCLA solid breeder blanket

Sharafat¹,

Amodeo²,

Ghoniem³

1986

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and HA10-after 20 3 achieving a burnup of 3x10 captures/cm (after Hollenberg [2]). . 35 2 Volumetric swelling of LiAlO. exposed to = 5 MW/m of neutron wall loading as a function of irradiation time 39 2 Volumetric swelling of Li,0 exposed to 5 MN/m of neutron wall wall loading as a function of irradiation time 42 Blanket pin average steady state temperature as a function of distance from the first wall for a neutron wall loading of = 5 MW/m 2 45 Helium production in LiAlO, breeder pins as a function of distance from the. first wall 47 Average helium production in Be-rods as a function of distance from the first wall 48 Average volumetric swelling of LiAlO, breeder rods exposed to 2 5 MW/m neutron wall loading after 3 years of irradiation 49 2 Volumetric swelling of Be-rods exposed to 5 MW/m neutron wall loading after 1, 2, and 3 years of irradiation 50 TABLES Summary for blanket material properties current status (12/85) ... Estimates for bubble number densities and radii using above model and experimental swelling data for LiAlO. Experimental and analytical swelling results for LiAlO, for 500 i T 1 900°C 3S Experimental sw511ing and helium retention data for Li 0 iv 5. Estimate for bubble number densities and radii using the above model and experimental data for Li-O 6. Experimental and analytical swelling results for Li.O for 500 < T < 900°C 7. Experimental and analytical swelling results for Be irradiated to

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“…Cold pressing and sintering techniques were developed for Li20, Li4SiC>4, and Y-L1A1O2 samples irradiated in ORR. 23 For the EBR-II/FUBR irradiation experiment, techniques were developed to control impurities, structures, and grain size for candidate material powders and to fabricate these powders into pellets by hot pressing techniques. 2 * Li20 pellets of 70 to 93% theoretical density were prepared using cold pressing and sintering techniques.…”

Section: Blanket Fabricationmentioning

confidence: 99%

Recent advances in the development of solid breeder blanket materials

Johnson

Hollenberg

1984

Journal of Nuclear Materials

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Increasing attention in breeder blanket development has been given to the lithium-containing ceramic materials. The most promising of these materials include Li£O, LigZrOg, Li4SiO4, and y-LiA102. Recent studies have focused on Li20 because of its high tritium breeding potential and good thermal characteristics. Tritium solubility in Li20 is within acceptable ranges and this oxide displays excellent behavior under neutron ii'radiation. A broad scope of laboratory and in-reactor irradiation experiments are underway to further investigate these materials.

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Irradiation study of lithium compound samples for tritium breeding application

Cited by 25 publications

References 0 publications

TRIO experiment

TRIO experiment

Materials data base and design equations for the UCLA solid breeder blanket

Recent advances in the development of solid breeder blanket materials

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