Development of design equations for ferritic alloys in fusion reactors

Amodeo, R. J.; Ghoniem, Nasr M.

doi:10.1016/s0920-3796(85)80039-9

Cited by 3 publications

(4 citation statements)

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“…Other data on the ferritic steels include steady state thermal creep correlations [5] . The expression used for swelling of the ferricic steel 2 1/4 Cr -1 Mo is from work by Gelles and Puigh (6] on irradiation induced swelling.…”

Section: Materials Propertiesmentioning

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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Section: Materials Propertiesmentioning

confidence: 99%

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

Sharafat¹,

Amodeo²,

Ghoniem³

1986

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“…The most widely accepted are the correlations developed by Amodeo and Ghoniem [5,6] and by Lewis and Chuang [7].…”

Section: Existing Correlations For Creep Strainmentioning

confidence: 99%

“…Although the thermal creep of HT9 has been studied for decades for both nuclear and non-nuclear applications [5][6][7][8][9], inconsistencies still exist in the correlations and the experimental data. In the present study, the test data available for the thermal creep tests of HT9 were assessed.…”

Section: Introductionmentioning

confidence: 99%

Thermal creep modeling of HT9 steel for fast reactor applications

Ryu

Kim

Yacout

2011

Journal of Nuclear Materials

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“…Blink y Lasche [10] estudiaron analíticamente en 1985 los criterios de selección del tipo de acero útiles en el proceso de concepción del reactor. Como consecuencia la importancia ambiental de este problema, en los últimos años se ha producido una gran investigación sobre aceros de baja activación, de tipo ferrítico (Amodeo y Ghoniem [6]), martensítico (Sanz y Perlado [133]) y austenítico (Zucchetti y Zublena [179]).…”

Section: Revisión Bibliográfica Sobre Seguridad En Reactores De Fusiónunclassified

Contribución al análisis de transitorios térmicos accidentales en los componentes de un reactor de fusión nuclear

Ramírez¹

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Development of design equations for ferritic alloys in fusion reactors

Cited by 3 publications

References 0 publications

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

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

Thermal creep modeling of HT9 steel for fast reactor applications

Contribución al análisis de transitorios térmicos accidentales en los componentes de un reactor de fusión nuclear

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