|
|
|
|
| LEADER |
02066nma a2200301 u 4500 |
| 001 |
EB001987209 |
| 003 |
EBX01000000000000001150111 |
| 005 |
00000000000000.0 |
| 007 |
cr||||||||||||||||||||| |
| 008 |
210512 ||| eng |
| 020 |
|
|
|a 1919
|
| 020 |
|
|
|a 9789535161172
|
| 020 |
|
|
|a 9789535100188
|
| 100 |
1 |
|
|a Zacarias Mesquita, Amir
|
| 245 |
0 |
0 |
|a Nuclear Reactors
|h Elektronische Ressource
|
| 260 |
|
|
|b IntechOpen
|c 2012
|
| 300 |
|
|
|a 1 electronic resource (352 p.)
|
| 653 |
|
|
|a Electrical engineering / bicssc
|
| 653 |
|
|
|a Electrical engineering
|
| 700 |
1 |
|
|a Zacarias Mesquita, Amir
|
| 041 |
0 |
7 |
|a eng
|2 ISO 639-2
|
| 989 |
|
|
|b DOAB
|a Directory of Open Access Books
|
| 500 |
|
|
|a Creative Commons (cc), https://creativecommons.org/licenses/by/3.0/
|
| 028 |
5 |
0 |
|a 10.5772/1919
|
| 856 |
4 |
0 |
|u https://mts.intechopen.com/storage/books/1462/authors_book/authors_book.pdf
|7 0
|x Verlag
|3 Volltext
|
| 856 |
4 |
2 |
|u https://directory.doabooks.org/handle/20.500.12854/65541
|z DOAB: description of the publication
|
| 082 |
0 |
|
|a 620
|
| 520 |
|
|
|a This book presents a comprehensive review of studies in nuclear reactors technology from authors across the globe. Topics discussed in this compilation include: thermal hydraulic investigation of TRIGA type research reactor, materials testing reactor and high temperature gas-cooled reactor; the use of radiogenic lead recovered from ores as a coolant for fast reactors; decay heat in reactors and spent-fuel pools; present status of two-phase flow studies in reactor components; thermal aspects of conventional and alternative fuels in supercritical water?cooled reactor; two-phase flow coolant behavior in boiling water reactors under earthquake condition; simulation of nuclear reactors core; fuel life control in light-water reactors; methods for monitoring and controlling power in nuclear reactors; structural materials modeling for the next generation of nuclear reactors; application of the results of finite group theory in reactor physics; and the usability of vermiculite as a shield for nuclear reactor.
|