Výsledky vyhledávání - "T.T. Claudson"

Cladding and structural materials semi-annual progress report, January 1975--July 1975

Autor: T.T. Claudson

Theoretical and experimental programs are in progress to determine the effects of fast neutron radiation on the mechanical properties and swelling of 3C4 and 316SS cladding and duct materials. Detailed specimen characterization and detailed test cond

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::fd5a47f0f960540b1a52428a7153b2c6
https://doi.org/10.2172/7193569

Zobrazit plný text záznamu

Irradiation effects on reactor structural materials. Semiannual progress report, March 1975--July 1975

Autor: T.T. Claudson

Mechanical properties and irradiation effects are reported by Aerojet, ANL, AI, GE, HEDL, NRL, ORNL, PNL, and Univ. of Cincinnati for: Type 304, 304L, and 316 stainless steels; Inconel 718; nickel; Ni alloys; V alloys; Mo; Nb; and Nb--1 Zr. (DLC)

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::68241fb191e6045e7b893f59bb38fa63
https://doi.org/10.2172/4058914

Zobrazit plný text záznamu

Irradiation performance of enriched uranium clad in stainless steel: PT-IP-123-A. Final report

Autor: T.T. Claudson

Early in the development of an extended surface fuel element for use in the NPR, several 7-rod cluster fuel elements were irradiated to determine the dimensional stability of such geometries at high burnups. These elements were fabricated from small

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d34486912541d751460f60a9d48609e3
https://doi.org/10.2172/10175226

Zobrazit plný text záznamu

Vyhledávací nástroje:

Upřesnit hledání