Zobrazeno 1 - 10
of 35
pro vyhledávání: '"W. A. Byers"'
Autor:
W. A. Byers, G. Wang
Publikováno v:
Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management.
It is essential to understand how crud build-up leads to elevated cladding temperatures and abnormal cladding corrosion for Boiling Water Reactor (BWR) fuel. With a heated rod test loop configuration, the influence of water chemistry on crud build-up
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2beb179ad2ce1cffe11eb39e7566cf02
https://doi.org/10.1115/icone26-82626
https://doi.org/10.1115/icone26-82626
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :2245
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::60881a951be32c98e4303fb9f028976a
https://doi.org/10.1299/jsmeicone.2019.27.2245
https://doi.org/10.1299/jsmeicone.2019.27.2245
Publikováno v:
Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues.
Corrosion products deposit on Pressurized Water Reactor (PWR) fuel rod cladding surfaces and can create a number of issues including increased cladding temperature, elevated cladding corrosion, and the precipitation of boron species within the deposi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4305bbbe8c1de08bbe7a9c7bf4dcfa2b
https://doi.org/10.1115/icone22-31265
https://doi.org/10.1115/icone22-31265
Publikováno v:
Journal of Solution Chemistry. 29:541-559
The solubility in water of anhydrous lithium monoborate has been determinedat 300 to 360°C. Equilibrium constants for the isocoulombic solubilityreactionLiBO2 (s) + H+ (aq) + H2O (1) = Li+ (aq) + H3BO3 (aq)have been calculated from measured concentr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::383fc46173abce6bbc4cbb4e5c9070a7
https://doi.org/10.1023/a:1005194129783
https://doi.org/10.1023/a:1005194129783
Publikováno v:
Polymer Engineering and Science. 33:645-650
Thin plasma polymerized films of tetramethyl germanium are deposited at various substrate temperatures. The influence of substrate temperature on the deposition rate, composition, structure, and electrical properties of the films is discussed. With a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::81572da2227e04f40d62ce9a6ed71ba1
https://doi.org/10.1002/pen.760331010
https://doi.org/10.1002/pen.760331010
Publikováno v:
Surgery, gynecologyobstetrics. 82
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=pmid________::017e61d87e719889c69021625fcd59b9
https://pubmed.ncbi.nlm.nih.gov/21011705
https://pubmed.ncbi.nlm.nih.gov/21011705
Autor:
W G, Byers
Publikováno v:
Canadian Medical Association journal. 27(4)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=pmid________::23ff84d611b582da1948bf751f0a50be
https://pubmed.ncbi.nlm.nih.gov/20318882
https://pubmed.ncbi.nlm.nih.gov/20318882
Autor:
W. A. Byers
Publikováno v:
18th International Conference on Nuclear Engineering: Volume 5.
Knowledge of the quantity and distribution of core deposits (crud) can be useful in many ways. Trending the amount of crud can show the effects of coolant chemistry changes and crud remediation efforts. The crud distribution reflects the locations of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6da22ee3fb7d6acf7fe9f1d5494af5d5
https://doi.org/10.1115/icone18-30218
https://doi.org/10.1115/icone18-30218
Publikováno v:
Volume 3: Thermal Hydraulics; Instrumentation and Controls.
In order to understand crud formation on the fuel rod cladding surfaces of pressurized water reactors (PWRs), a crud Thermal-Hydraulic test facility referred to as the Westinghouse Advanced Loop Tester (WALT) was built at the Westinghouse Science and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9bcce351b7973b09dcfc2213a33990d3
https://doi.org/10.1115/icone16-48480
https://doi.org/10.1115/icone16-48480
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :ICONE1510-ICONE1510
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1cb4375370140d3f2582b2ed993731b1
https://doi.org/10.1299/jsmeicone.2007.15._icone1510_361
https://doi.org/10.1299/jsmeicone.2007.15._icone1510_361