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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

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 SaeedORCID

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