This review surveys the behaviour d graphite under loading conditions in which the stressing is on the whole tensile. The performance of a recently introduced model of graphite failure is reviewed in relation to the modeis from which it was developed, and against data obtained from a wide range of experiments on the failure and deformation properties of graphite In tension and bend. The new mod...

In this paper, we used a neutron diffusion hybrid equation with an external neutron source to calculate nuclear power factors in each fuel element in the reactor core. We used the nodal expansion method to obtain the neutron flux for a given control rods bank position. The results were compared with results obtained for eigenvalue problem near criticality condition and fixed source problem duri...

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...

The Gas-Cooled Fast Reactor (GFR) is one of the reactor concepts selected by Generation IV International Forum (GIF) for next generation innovative nuclear energy systems. It was among a group more than 100 prototypes and his commercial availability expected 2030. GFR has common goals as rest GIF advanced types: economy, safety, proliferation resistance, sustainability. Several fuel design such...

In this paper we report on a research project in which the user interface for a research nuclear reactor was specified using a combination of formal notations. The goal of the project was to evaluate the use of a combination of techniques and to assess their utility in specifying a user interface for a non-trivial safety-critical application. We conclude that the techniques worked well and scal...

The TIESTE-MINOSSE code, developed at the ENEA to preliminarily investigate core dynamics relevant to metal cooled fast reactor and ADS, has been implemented to analyse transients in the RC1 1 MW swimming pool TRIGA reactor existing at the Casaccia Centre. In the first part of the work, the TIESTE-MINOSSE improvement and validation on TRIGA dynamics is described. In particular, reactivity inser...

Accelerator-Driven Systems (ADS) could be employed to incinerate minor actinides and so partly contribute to answer the problem of nuclear waste management. An ADS consists of the coupling of a subcritical fast reactor to a particle accelerator via a heavy material spallation target. The on-line reactivity monitoring of such an ADS is a serious issue regarding its safety. In order to study the ...

At present work, under initial inventory with Th and U, the evolution of nuclides in subcritical devices under given thermal, fast, hardening fast and fission neutron field are studied without the detail structure of sub-critical device and the burn-up being considered. It is supposed that the subcritical reactor consists of uniform in which the flux of neutron is homogeneous. The fissile nucli...

Two benchmarks for the qualification of the pressure vessel fluence calculational methodology were formulated and are brieily described. The Pool Critical Assembly (PCA) benchmark is based on the experiments performed at the PCA in Oak Ridge. The measured quantities to be compared against the calculated values are the equivalent fission fluxes at several locations in front, behind, and inside t...

Underwater vehicle is designed to ensure the security of country sea boundary, providing harsh requirements for its power system design. Conventional power sources, such as battery and Stirling engine, are featured with low power and short lifetime. Micronuclear reactor power source featured with higher power density and longer lifetime would strongly meet the demands of unmanned underwater veh...