Journal of Nuclear Materials

Title Publication Date Language Citations
Handbook of SiC properties for fuel performance modeling2007/09/01English988
Accident tolerant fuels for LWRs: A perspective2014/05/01English692
Ferritic/martensitic steels for next-generation reactors2007/09/01English659
Recent analysis of key plasma wall interactions issues for ITER2009/06/01English646
Helium accumulation in metals during irradiation – where do we stand?2003/12/01English646
Structural materials for Gen-IV nuclear reactors: Challenges and opportunities2008/12/01English607
Recent progress in research on tungsten materials for nuclear fusion applications in Europe2013/01/01English604
A full tungsten divertor for ITER: Physics issues and design status2013/07/01English603
Tungsten as material for plasma-facing components in fusion devices2011/08/01English573
The rate theory of swelling due to void growth in irradiated metals1972/08/01English540
Accident tolerant fuel cladding development: Promise, status, and challenges2018/04/01English537
Intragranular cellular segregation network structure strengthening 316L stainless steel prepared by selective laser melting2016/03/01English523
Materials for the plasma-facing components of fusion reactors2004/08/01English502
Structural materials challenges for advanced reactor systems2009/03/01English467
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys2005/05/01English446
Materials and processes for the effective capture and immobilization of radioiodine: A review2016/03/01English438
The effect of radiation upon diffusion in metals1978/02/01English391
Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys2005/02/01English389
The role of vacancies and dislocations in the nucleation and growth of gas bubbles in irradiated fissile material1959/12/01English387
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding2014/05/01English358
Vacancy defect mobilities and binding energies obtained from annealing studies1978/02/01English351
The relationship between hardness and yield stress in irradiated austenitic and ferritic steels2005/02/01English350
A review of microstructure evolution in zirconium alloys during irradiation1988/10/01English346
Physics basis and design of the ITER plasma-facing components2011/08/01English345
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects2014/05/01English345
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors2015/12/01English340
Primary radiation damage: A review of current understanding and models2018/12/01English340
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments2013/09/01English332
Corrosion and stress corrosion cracking in supercritical water2007/09/01English307
The new SOLPS-ITER code package2015/08/01English307