Zobrazeno 1 - 10
of 15
pro vyhledávání: '"W. L. Pearl"'
Autor:
W. L. Pearl, W. R. Kassen, S. G. Sawochka, J. W. Kormuth, D. D. Malinowski, W. D. Fletcher, A. D. Miller, W. J. Krotiuk, M. B. Rubin, T. E. Botts, J. R. Powell, Michio Murase, Isao Sumida, Koichi Kotani, Hajime Yamamoto, R. C. Lloyd, S. R. Bierman, E.D. Clayton, B. M. Durst, Zbigniew Jaworowski, Ludwika Kownacka, Kazimierz Grotowski, Krzysztof Kwiatkowski, Dušan Kollár, Lubica Kollárová, Pavel Horváth
Publikováno v:
Nuclear Technology. 37:87-91
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5a69336da9bb332a27a0bda22558000
https://doi.org/10.13182/nt78-a31973
https://doi.org/10.13182/nt78-a31973
Publikováno v:
Nuclear Applications. 1:453-461
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::02ab3bebf5524562c9e3b009fa2058d9
https://doi.org/10.13182/nt65-a20557
https://doi.org/10.13182/nt65-a20557
Publikováno v:
Nuclear Applications. 3:418-432
INCONEL alloy 625® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1500°F (816°C) in specially designed out-of-pile superheat facilities....
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0149cded0039fafb408fcb1832550ff2
https://doi.org/10.13182/nt67-a27840
https://doi.org/10.13182/nt67-a27840
Publikováno v:
Nuclear Science and Engineering. 17:18-29
A versatile boiling water and superheated steam facility was developed for out-of-pile corrosion testing of materials that are being used and considered for application in boiling water reactor (BWR) and superheat reactor (SHR) systems. The following
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ceefc94396be9cf21838eca6b2d4546c
https://doi.org/10.13182/nse63-a17206
https://doi.org/10.13182/nse63-a17206
Autor:
Louis A. Waldman, Menelaos Doumas, J. R. Low, U. E. Wolff, J. S. Armijo, C. R. Bergen, W. R. Martin, J. R. Weir, Paul Cohen, G. R. Taylor, Charles R. Johnson, A. E. Pickett, W. L. Pearl, M. C. Rowland, W. R. Smalley, E. Paxson, D. R. McClintock, H. M. Ferrari, Warren E. Winsche, Herbert Susskind, Walter Becker, W. H. Arlt, T. J. Pashos, R. N. Duncan, J. P. Hoffman, H. E. Williamson, C. J. Baroch, Everett W. Hobart
Publikováno v:
Nuclear Applications. 1:397-401
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::386a9ad89833d1e2bc6f322bb593da15
https://doi.org/10.13182/nt65-a20545
https://doi.org/10.13182/nt65-a20545
Autor:
E. G. Brush, W. L. Pearl
Publikováno v:
CORROSION. 25:99-105
Copper bearing alloys are widely used in steam generation feedwater heaters, and although corrosion rates are minimal, copper corrosion product release has caused some undesirable depositi...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::40821f73d79be03196d715ed4ee16510
https://doi.org/10.5006/0010-9312-25.3.99
https://doi.org/10.5006/0010-9312-25.3.99
Publikováno v:
Nuclear Applications. 1:235-245
Incoloy-800® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1410° F (766° C) in specially designed out-of-pile superheat facilities. The...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e68113ae68f600b9e6523a8142a2fb0e
https://doi.org/10.13182/nt65-a20508
https://doi.org/10.13182/nt65-a20508
Publikováno v:
Corrosion. 17:269t-276t
Results are reported of extensive corrosion testing of carbon and low-alloy steels in a dynamic test loop simulating the various environments found in a nuclear boiling-water-reactor system. Quantitative data and metallographic and visual observation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1456a35173a825a7fbed5cf59c6a500c
https://doi.org/10.5006/0010-9312-17.6.95
https://doi.org/10.5006/0010-9312-17.6.95
Autor:
E. G. Brush, W. L. Pearl
Publikováno v:
CORROSION. 28:129-136
The corrosion and corrosion products released from materials exposed to typical boiling water reactor (BWR) feedwater chemistries were determined over the temperature range of 38 to 204 C ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::266f8a2fd7ebcae6ab11288ca09f768c
https://doi.org/10.5006/0010-9312-28.4.129
https://doi.org/10.5006/0010-9312-28.4.129
Autor:
W. L. Pearl, G. P. Wozadlo
Publikováno v:
Corrosion. 21:260-267
Results are reported for the continuation1 of extensive corrosion testing of carbon steel exposed in a dynamic test loop simulating the various environments found in a nuclear boiling-water-reactor system. Water and steam conditions were based on 20
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c86b299f26b916cd847f66f446fdd4dd
https://doi.org/10.5006/0010-9312-21.8.260
https://doi.org/10.5006/0010-9312-21.8.260