Nuclear reactor analysis /
Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of...
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| Autor principal: | |
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| Otros Autores: | |
| Formato: | Libro |
| Lenguaje: | Inglés |
| Publicado: |
New York :
Wiley,
[c1976]
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| Materias: | |
| Acceso en línea: | Tapa Indice |
| Aporte de: | Registro referencial: Solicitar el recurso aquí |
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| 245 | 1 | 0 | |a Nuclear reactor analysis / |c James J. Duderstadt, Louis J. Hamilton. |
| 260 | # | # | |a New York : |b Wiley, |c [c1976] |
| 300 | # | # | |a xvii, 650 p. : |b il. ; |c 26 cm. |
| 504 | # | # | |a Incluye referencias bibliográficas e índices. |
| 520 | # | # | |a Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores. This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural. The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermal-hydraulics or materials studies, which play a major role in determining a reactor design. |
| 020 | # | # | |a 0471223638 |
| 100 | 1 | # | |a Duderstadt, James J., |d 1942- |
| 700 | 1 | # | |a Hamilton, Louis J., |d 1941- |e joint author. |
| 080 | # | # | |a 621.039.51 |
| 650 | # | 0 | |a Nuclear reactors |x Design and construction. |
| 650 | # | 0 | |a Nuclear engineering. |
| 650 | # | 0 | |a Nuclear fission. |
| 650 | # | 7 | |a Nuclear physics. |2 inist |
| 650 | # | 7 | |a Nuclear power. |2 inist |
| 650 | # | 7 | |a Neutron transport. |2 inist |
| 650 | # | 7 | |a Física nuclear. |2 inist |
| 650 | # | 7 | |a Energía nuclear utilizable. |2 inist |
| 690 | # | # | |a Ingeniería nuclear |b Laboratorio II. |
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