Zobrazeno 1 - 10
of 34
pro vyhledávání: '"P.L. Rittenhouse"'
Autor:
P.L. Rittenhouse, H.E. McCoy
Publikováno v:
Journal of Nuclear Materials. 171:103-107
A testing program is in progress to define the tensile and creep properties of SA533 Grade B Class 1 steel at temperatures from 371 to 538 °C. The overall objective is to provide the data necessary to obtain ASME Code approval for use of this materi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e28f8da675d2ecfc1b4972ed46c6e49b
https://doi.org/10.1016/0022-3115(90)90353-o
https://doi.org/10.1016/0022-3115(90)90353-o
Autor:
P.L. Rittenhouse, Dane F. Wilson, J.R. DiStefano, S.R. Greene, B.A. Worley, T.M. Besmann, J.H. DeVan, E.C. Beahm, U. Gat
This paper identifies and examines issues concerning the incorporation of gallium in weapons derived plutonium in light water reactor (LWR) MOX fuels. Particular attention is given to the more likely effects of the gallium on the behavior of the clad
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6dcf59fde8712c164250be16c2826ca
https://doi.org/10.2172/672086
https://doi.org/10.2172/672086
Irradiation capsule HRB-22 was a test capsule containing advanced Japanese fuel for the High Temperature Test Reactor (HTTR). Its function was to obtain fuel performance data at HTTR operating temperatures in an accelerated irradiation environment. T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ffa431df0e8c06a4f48d3c230e98a545
https://doi.org/10.2172/97179
https://doi.org/10.2172/97179
Autor:
P.L. Rittenhouse
Publikováno v:
Journal of Nuclear Materials. 23:183-191
The anisotropy of plastic properties of Zircaloy-2 is an important consideration in its use. A rapid and simple method of evaluating and characterizing these properties would be a valuable aid to the designer. Experimental yield and strain data on lo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8717e2331a38dd147cd31d9e5a02ff4e
https://doi.org/10.1016/0022-3115(67)90063-3
https://doi.org/10.1016/0022-3115(67)90063-3
Autor:
E. Tenckhoff, P.L. Rittenhouse
Publikováno v:
Journal of Nuclear Materials. 35:14-23
The annealing textures in Zircaloy tubing are more complex than those reported for rolled and annealed zirconium or titanium sheet. Different features of annealing textures can develop, depending on whether the tubing is hot extruded, rocked, or draw
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::516595a6e9ba149da802f8497f58fa12
https://doi.org/10.1016/0022-3115(70)90022-x
https://doi.org/10.1016/0022-3115(70)90022-x
Autor:
P.L. Rittenhouse
Publikováno v:
Journal of Nuclear Materials. 24:310-315
Tensile specimens of annealed Zircaloy tubing were tested to examine the influence of texture on anisotropy. It was found that the diameter and wallthickness strains could be treated to give both a measure of the anisotropy of plastic properties and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::372db587f01726de45cb3481ef425940
https://doi.org/10.1016/0022-3115(67)90203-6
https://doi.org/10.1016/0022-3115(67)90203-6
Results are presented for strain-controlled fatigue and tensile tests for two nickel-base, solution-hardened reference structural alloys for use in several High-Temperature Gas-Cooled Reactor (HTGR) concepts. These alloys, Hastelloy X and Inconel 617
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e4f9e11b6fa96d9ba77216cc17ce511d
https://doi.org/10.2172/5228668
https://doi.org/10.2172/5228668
During 1982 the High-Temperature Gas-Cooled Reactor (HTGR) Technology Program at Oak Ridge National Laboratory (ORNL) continued to develop experimental data required for the design and licensing of cogeneration HTGRs. The program involves fuels and m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::64ce6b15cdc711e8d7b3f0253ed0b748
https://doi.org/10.2172/6174841
https://doi.org/10.2172/6174841
Hastelloy X, an Ni--Cr--Fe--Mo alloy, may be an important structural alloy for components of gas-cooled reactor systems. Expected applications of this alloy in the High-Temperature Gas-Cooled Reactor (HTGR) are discussed, and the development of inter
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f987ba472a518539bded744dc9d1f473
https://doi.org/10.2172/7347624
https://doi.org/10.2172/7347624