A Compendium Of Computer Codes For The Safety Analysis Of Fast Breeder Reactors
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Author | : United States. Department of Energy. Division of Reactor Research and Demonstration |
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Total Pages | : 444 |
Release | : 1977 |
Genre | : Breeder reactors |
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Author | : United States. Department of Energy. Division of Reactor Research & Development |
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Total Pages | : 444 |
Release | : 1977 |
Genre | : Nuclear reactors |
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The objective of the compendium is to provide the reader with a guide which briefly describes many of the computer codes used for liquid metal fast breeder reactor safety analyses, since it is for this system that most of the codes have been developed. The compendium is designed to address the following frequently asked questions from individuals in licensing and research and development activities: (1) What does the code do. (2) To what safety problems has it been applied. (3) What are the code's limitations. (4) What is being done to remove these limitations. (5) How does the code compare with experimental observations and other code predictions. (6) What reference documents are available.
Author | : United States. Energy Research and Development Administration. Division of Reactor Research and Development. Safety Analysis Branch |
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Total Pages | : 196 |
Release | : 1975 |
Genre | : Breeder reactors |
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Total Pages | : 612 |
Release | : 1976 |
Genre | : Nuclear energy |
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Total Pages | : 546 |
Release | : 1978 |
Genre | : Government publications |
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Author | : Oak Ridge National Laboratory. Engineering Physics Division |
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Total Pages | : |
Release | : 1979 |
Genre | : Fast reactors |
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Author | : Energy Library |
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Total Pages | : 104 |
Release | : 1978 |
Genre | : Power resources |
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Total Pages | : 548 |
Release | : 1978 |
Genre | : Power resources |
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Total Pages | : 140 |
Release | : 1978-03 |
Genre | : Nuclear engineering |
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