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Annals of Nuclear Energy
Resumen/Descripción – provisto por la editorial en inglés
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (both fission and fusion), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal.Palabras clave – provistas por la editorial
No disponibles.
Disponibilidad
| Institución detectada | Período | Navegá | Descargá | Solicitá |
|---|---|---|---|---|
| No detectada | desde ene. 1975 / hasta dic. 2023 | ScienceDirect |
Información
Tipo de recurso:
revistas
ISSN impreso
0306-4549
ISSN electrónico
1873-2100
Editor responsable
Elsevier
País de edición
Reino Unido
Fecha de publicación
1975-
Cobertura temática
Tabla de contenidos
Measurement and interpretation of delayed photoneutron effects in multizone criticals with partial D2O moderation
F. Jatuff; A. Lüthi; M. Murphy; T. Williams; R. Chawla
Palabras clave: Nuclear Energy and Engineering.
Pp. 1731-1755
Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data
Alexander Vasiliev; Hakim Ferroukhi; Martin A. Zimmermann; Rakesh Chawla
Palabras clave: Nuclear Energy and Engineering.
Pp. 615-627
HAZOP-study on heavy water research reactor primary cooling system
M. Hashemi-Tilehnoee; A. Pazirandeh; S. Tashakor
Palabras clave: Nuclear Energy and Engineering.
Pp. 428-433
Optimization of a moisture separator reheater
Guijing Li; Changqi Yan; Jianjun Wang
Pp. 537-546
Experimental evaluation of surveillance capsule assemblies for life assessment of CHASNUPP Unit-1 reactor pressure vessel
Sümer Şahin; Asim Saeed
Pp. 90-98
Selection of important initiating events for Level 1 probabilistic safety assessment study at Puspati TRIGA Reactor
M. Maskin; F. Charlie; A. Hassan; P. Prak Tom; Z. Ramli; F. Mohamed
Palabras clave: Nuclear Energy and Engineering.
Pp. 198-210
Neutron deep penetration through reactor pressure vessel and biological concrete shield of VVER-1000 Mock-Up in LR-0 reactor
Michal Košťál; František Cvachovec; Bohumil Jánský; Vojtěch Rypar; Vlastimil Juříček; Davit Harutyunyan; Martin Schulc; Ján Milčák; Evžen Novák; Sergey Zaritsky
Pp. 672-683
A review for identification and selection of initiating events important for Level 1 probabilistic safety assessment study for a 10 MW water water research reactor (VVR)
F. Ameyaw; R.G. Abrefah; S. Yamoah; J.J. Fletcher; S.A. Birikorang
Palabras clave: Nuclear Energy and Engineering.
Pp. 303-314
Modeling upgrade of probabilistically significant SBO scenarios with uncertainty analysis for the evaluation of system power uprate of limited scope
Y. Du; T.H. Liang; Z.W. Zhang; K.S. Liang
Palabras clave: Nuclear Energy and Engineering.
Pp. 513-523
Research on level 1 PSA and risk-informed design for ACP100
Jian Deng; Youyou Xu; Zhifang Qiu; Hang Zhang; Lingjun Wu; Xiaoji Wang; Huanhuan Peng; Zhengyu Du
Palabras clave: Nuclear Energy and Engineering.
Pp. 107542