Neutronics Analysis of Full MOX BWR Core Simulation Experiments FUBILA
نویسندگان
چکیده
منابع مشابه
Analysis of Core Physics Experiments of High Moderation Full MOX LWR
The 2003-2004 activity of Reactor Integral Test WG under Subcommittee on Reactor Constants of Japanese Nuclear Data Committee will be presented. During this period, the WG carried out integral tests of JENDL-3.3, ENDF/B-VI and JEFF 3.0 for reactor applications. Some results of integral tests for other latest libraries, JEFF-3.1, ENDF/B-VII, etc. will be also presented. Nuclear Data Library in D...
متن کاملFull MOX ABWR neutron characterization with void increase: the FUBILA Program
CEA and JNES have undertaken a first-of-a-kind full MOX core physics experiments, FUBILA, in the EOLE critical facility of the CEA Cadarache centre. The experiments have been designed to obtain core physics data of high burn up 9x9 and 10x10 BWR MOX assemblies operating conditions. The experimental program, consisting in eight different core configurations, started in January 2005 and finished ...
متن کاملNeutronics Analysis of the TRIGA Vienna Mixed Core
The 250 kW TRIGA Mark II research reactor, Vienna, operates since 7 March 1962. The initial criticality was achieved with the first core loading of 57 fuel elements (FE) of same type (Aluminium clad fuel with 20% enrichment). Later on due to fuel consumption SST clad 20% enriched FE (s) have been added to compensate the reactor core burn-up. In 1975 high enriched (HEU) TRIGA fuel (FLIP fuel = F...
متن کاملNeutronics Modeling and Simulation of Sharp for Fast Reactor Analysis
Reactor design is an iterative process among various disciplines such as reactor physics, thermal fluid dynamics, mechanics, reactor and plant dynamics, fuel behavior, and instrumentation and control, and requires a wide range of modeling and simulation tools that can accurately predict key system performance and safety characteristics. Most code systems for fast reactor design were initiated m...
متن کاملAn Approach to Numerical Simulation and Analysis of Molten Corium Coolability in a Bwr Lower Head
The paper discusses an application of the Computational Fluid Dynamics (CFD) method to support the development and validation of a computationally-affordable method named Effective Convectivity Model (ECM) for simulation of turbulent natural convection heat transfer and phase changes in a decay-heated corium pool in the Boiling Water Reactor (BWR) lower head. The CFD method simulations enable d...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: Journal of Nuclear Science and Technology
سال: 2011
ISSN: 0022-3131
DOI: 10.3327/jnst.48.398