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Nuclear Engineering and Design
Resumen/Descripción – provisto por la editorial en inglés
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.Palabras clave – provistas por la editorial
No disponibles.
Disponibilidad
| Institución detectada | Período | Navegá | Descargá | Solicitá |
|---|---|---|---|---|
| No detectada | desde ene. 1966 / hasta dic. 2023 | ScienceDirect |
Información
Tipo de recurso:
revistas
ISSN impreso
0029-5493
ISSN electrónico
1872-759X
Fecha de publicación
1966-
Cobertura temática
Tabla de contenidos
Uranium dioxide properties for LWR fuel rods
H. Stehle; H. Assmann; F. Wunderlich
Palabras clave: Mechanical Engineering; Waste Management and Disposal; Safety, Risk, Reliability and Quality; General Materials Science; Nuclear Energy and Engineering; Nuclear and High Energy Physics.
Pp. 230-260
Toward a unified approach for thermal nonequilibrium in gas-liquid systems
Owen C. Jones
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 57-73
An active cavity model for flashing
Tai Sung Shin; Owen C. Jones
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 185-196
Inconel X-750 as material for core internals and core components - Status of in-service experience and replacements at siemens kwu group
Hartmut Rubel; Detlef Marschke; Jürgen Tautz; Gerd Micheel
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 329-336
Application of tanh curve fit analysis to fracture toughness data of Japanese RPVS
Y. Sakai; K. Tamanoi; N. Ogura
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 31-39
Summary description of the methods used in the probabilistic risk assessments for NUREG-1150
R.J Breeding; J.C Helton; E.D Gorham; F.T Harper
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 1-27
Integral methods for simulating transient conduction in nuclear reactor components
Wolfgang Wulff
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 113-129
Verification of the VVER-440 pressure vessel neutron fluence calculation by activity measurement
Krassimira Ilieva; Tihomir Apostolov; Ivan Penev; Sergey Belousov; Evgeny Taskaev; Stoyan Antonov; Temenuga Petrova; Petjo Tzokov; Zahari Bojadjiev
Pp. 257-260
Recent experiments for laminar and turbulent film heat transfer in vertical tubes
P.F Peterson; V.E Schrock; S.Z Kuhn
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 157-166
Experimental assessment of neutron fluence for the Kozloduy Unit 1 pressure vessel by scraps and cavity dosimetry
T Apostolov; K Ilieva; S Belousov; T Petrova; Iv Penev; I Popova; S Antonov
Palabras clave: Nuclear and High Energy Physics; Mechanical Engineering; Waste Management and Disposal; General Materials Science; Nuclear Energy and Engineering; Safety, Risk, Reliability and Quality.
Pp. 361-368