ENEA “Casaccia” Research Center is collaborating with Idaho National Laboratory performing activities devoted to the validation of the Parallel and Highly Innovative Simulation for INL Code System (PHISICS) neutron simulation code. In such framework, the AER-DYN-002 and AER-DYN-003 control rod (CR) ejection benchmarks were used to validate the coupled codes RELAP5-3D/PHISICS. The AER-DYN-002 benchmark provides a test case of a CR ejection accident in a VVER-440 at hot-zero-power and end-of-cycle conditions assuming an adiabatic fuel and taking into account only the fuel temperature feedback. The AER-DYN-003 benchmark is based on the same problem; however, the moderator density feedback and the coolant heat removal are also considered. A REL...
This thesis analyzes the behavior of the nuclear fuel of a WWER-1000 reactor during a Rod Ejection A...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
The coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently ...
[EN] In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue...
A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the few-group neutro...
<p>In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue. ...
The International Atomic Energy Agency established a Coordinated Research Project (CRP) for EBR-II s...
Chapter 1 – INTRODUCTION Chapter 2 – OVERVIEW OF 3D-NK-TH COUPLED CODES METHODOLOGY 2.1. COUPLED COD...
The objective of this work is to introduce an improvement in best estimate coupled neutronicthermalh...
ENEA is setting up, applying and validating numerical models and an integrated multi-physics approac...
The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of co...
Several institutions plan to couple the fuel performance code TRANSURANUS developed by the European ...
In the framework of the EU funded project NURESAFE, the subchannel code CTF and the neutronics code ...
[EN] In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue...
This paper describes reactor core model used for simulating REA. The model was designed in PARCS uti...
This thesis analyzes the behavior of the nuclear fuel of a WWER-1000 reactor during a Rod Ejection A...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
The coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently ...
[EN] In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue...
A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the few-group neutro...
<p>In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue. ...
The International Atomic Energy Agency established a Coordinated Research Project (CRP) for EBR-II s...
Chapter 1 – INTRODUCTION Chapter 2 – OVERVIEW OF 3D-NK-TH COUPLED CODES METHODOLOGY 2.1. COUPLED COD...
The objective of this work is to introduce an improvement in best estimate coupled neutronicthermalh...
ENEA is setting up, applying and validating numerical models and an integrated multi-physics approac...
The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of co...
Several institutions plan to couple the fuel performance code TRANSURANUS developed by the European ...
In the framework of the EU funded project NURESAFE, the subchannel code CTF and the neutronics code ...
[EN] In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue...
This paper describes reactor core model used for simulating REA. The model was designed in PARCS uti...
This thesis analyzes the behavior of the nuclear fuel of a WWER-1000 reactor during a Rod Ejection A...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
The coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently ...