Mechanical and Physical Properties of Irradiated Type 348 Stainless Steel

Abstract

A type 348 stainless steel in-pile tube 2 2 2 irradiated to a fluence of 3 x 10" n/cm, E > lMeV (57 dpa) , was destructively examined. The service had resulted in a maximum total creep of 1.8% at the high fluence. The metal temperature ranged between 623 and 652 K, hence the thermal creep portion of the total was negligible. Total creep was greater' than had been anticipated from creep data for austenitic stainless steels irradiated in other reactors. The objectives of the destructive examination were to determine the service-induced changes of mechanical and physical properties, and to assess the possibility of adverse effects of both these changes and the greater total creep on the prospective service life of other tubes, Measured bowing (0.51 mm) was correlated with a structural model. Post irradiation measurements included immersion density, fracture toughness, tensile strength and ductility, and creep-rupture strength. A reduction i:i fracture toughness due to irradiation creep was apparent.

Improvement of a model to predict static fracture toughness of austenitic materials under neutron irradiation

“…This was based on the data on fracture toughness for Russian austenitic materials (steels 09Kh18N9 and 08Kh18N10T, and weld metal of these steels) and foreign austenitic materials, series AISI 300 (steels 304, 306, 308, 316, 321, 347, 348 and weld metal of these steels) [8][9][10][11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26][27].…”

“…where is the temperature dependence of the yield stress of steel of grade 08Kh18N10T in the initial (unirradiated) condition expressed as (15) is the temperature dependence of the yield stress of steel of grade 08Kh18N10T at damage dose D* expressed as (16) is the increment of yield stress of steel of grade 08Kh18N10T as a function of damage dose and test temperature-for doses in the range from 0 to D*, this dependence has the form (17) is the increment of yield stress of steel of grade 08Kh18N10T as a function of damaging dosefor doses greater than or equal to D*, this dependence has the form (18) where D* is the neutron damage dose above which the increment in yield stress does not depend on test tem perature, D* = 7 dpa; = 621 MPa; and = 0.126 dpa -1 .…”

Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

“…test reactors show a reduction in failure strain, with a residual strain ductility of usually at least 0.01 (Olson et al 1976;Gilbert and Harding 1969;Standring et al 1969;Van der Schaaf 1982;Harries 1979;Beeston 1981).…”

Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico

“…Verifica-se que as ligas à base de zircônio não são apropriadas para altas temperaturas, fluência e o espectro de nêutrons rápidos [2]. As seguintes propriedades sofrem um decréscimo com a irradiação:…”

“…Analisando-se os códigos da época, somente alguns foram reportados na década de 1980, como capazes de modelar varetas combustíveis com revestimento de aço inoxidável austenítico [2,4]. Entre esses códigos estão o COMETHE, SLEUTH-SEER, BEHAVE IV, LIFE, THERMAL-1, URANUS, IAMBUS e FCODE-BETA/SS [1,7].…”