[en] The object of this work is to validate the attached code COBRA-TF/PARCS in a scenario of asymmetric injection of boron in a PWR reactor of three loops. This is intended to check the newly developed model of transport of boron code COBRA-TF and the routines of interpolation of effective section based on the concentration of boron implemented Parcs v2.7, demonstrating its proper functioning and its validity for the analysis of transient in nuclear safety.

[en] The aim of this study is to test the RELAP5/PARCS v2.7 connected code. The results show the pint PT_UPV is an unstable point and the axial obtained power distribution shows a pierced profile in the bottom of the core, typical of unstable cores.

[en] This work is the continuation of the work presented previously in the thirty-ninth meeting annual of the Spanish Nuclear society. The semi-automatic translation of the Thermo-hydraulic model TRAC-BF1 Peach Bottom Turbine Trip to TRACE was presented in such work. This article is intended to validate the model obtained in TRACE, why compare the model results result from the translation with the Benchmark results: NEA/OECD BWR Peach Bottom Turbine Trip (PBTT), in particular is of the extreme scenario 2 of exercise 3, in which there is SCRAM in the reactor. Among other data present in the (transitional) Benchmark , are: total power, axial profile of power, pressure Dome, total reactivity and its components. (Author)

[en] This paper presents the results from the calculation of the steady state simulation with model of CFD (computational fluid dynamic) operating under conditions of operation at full power (Hot Full Power). Development and the CFD model results show the usefulness of these codes for calculating 3D of the variable thermohydraulics of these reactors.

[en] Stability analysis in time domain and 3-D make into an operation map new point (PT_UPV) of Peach Bottom NPP, using a coupled code. The results show the point PT_UPV is an unstable point and the relative power distribution shows a pierced profile in the bottom of the core, typical of unstable cores.

[en] This article is a step in the simulation of the injection, transport and mixing of boron in the reactor, increasing the capabilities of the TRACBF1/NEM code. This article presents the changes in the source code for TRACBF1/NEM, to be able to simulate the injection of boron in a more realistic way.

[en] The simulation of the behavior of nuclear reactor core is especially important in the design, operation and safety of the plant. It is for this importance has decided to make a model of a 3D vessel coupled codes TRACE / PARCS, this model aims to be a more realistic way than previous models that used lD components.

[en] Due to the importance of calculating sensitivity and uncertainty in the calculation of field engineering, and especially in the nuclear world, it has been decided to present the main features of the new module present in the new version of SCALE 6.2 (currently beta 3 version) called SAMPLER. This module allows the calculation of uncertainty in a wide range of effective sections, neutron parameters, composition and physical parameters. However, the calculation of sensitivity is not present in the beta 3 release. Even so, this module can be helpful for participants of the proposed Benchmark by Expert Group on Uncertainty Analysis in Modelling (UAM-LWR), as well as to analysts in general. (Author)

[en] The use of radiation detectors Dual energy (dual energy) is a powerful tool for identification of materials subjected to X-ray analysis. Given a photon spectrum emitted by an X-ray tube, at low energies, the absorption of radiation depends mainly on the effective atomic number and thickness of the material. In contrast, higher energy levels, above 100 kilovolts, the energy absorbed depends, above all, the material density.

[en] The parallelization allows the use of numerous processors (or cores) that work together to obtain the solution to a single problem. This not only reduces computing time, but it also increases the amount of available memory on a cluster. They can therefore solve large-scale problems. In order to validate the parallelization of COBRA-TF has been modeled at the level of sub a fuel element type PWR and has simulated a small stationary, obtaining a considerable acceleration in the simulation in parallel compared with the sequential case.