Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors - Info and Reading Options
proceedings and symposium discussions : August 7-10, 1995, Breckenridge, Colorado
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (7th 1995 Breckenridge, Colo.)
"Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors" was published by NACE International in 1995 - Houston, TX, it has 1256 pages and the language of the book is English.
“Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Metadata:
- Title: ➤ Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
- Author: ➤ International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (7th 1995 Breckenridge, Colo.)
- Language: English
- Number of Pages: 1256
- Publisher: NACE International
- Publish Date: 1995
- Publish Location: Houston, TX
“Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Subjects and Themes:
- Subjects: ➤ Congresses - Corrosion - Nuclear power plants - Materials - Water cooled reactors - Effect of radiation on - Pressurized water reactors
Edition Specifications:
- Pagination: 2 v. (xv, 1256 p.) :
Edition Identifiers:
- The Open Library ID: OL3778592M - OL6087498W
- Online Computer Library Center (OCLC) ID: 49520801
- Library of Congress Control Number (LCCN): 2003545470
- ISBN-10: 1877914959
- All ISBNs: 1877914959
AI-generated Review of “Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors”:
"Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors" Description:
The Open Library:
This two-volume set features over 200 papers written by experts from around the world. It presents a variety of topics specific to nuclear power plants using water coolant, such as PWR primary side; PWR secondary side; BWR austenitic/water chemistry; water chemistry PWR and BWR; radiation effects; modeling/life prediction; IASCC; pressure vessel/low-alloy steels; and fuel cladding/wear.
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