The validation process is done to ensure the performance of nuclear codes compared to
experimental results and to determine the degree of reliability of codes output. The …

This paper presents the results of thermal-hydraulic calculations of a large break loss of
coolant accident (LBLOCA) analysis for a VVER-1000/V446 unit at Bushehr nuclear power …

The calculations performed for the design and operation of a Nuclear Power Plant (NPP) are
a key factor for its safety analyses. The standard for the computational analysis of NPPs is …

The presented article discusses develo** and validation of a VVER 1000 TRACE V5. 0p5
model. Develo** such model for a TRACE computer code is important as it increases the …

Abstract The OECD/NEA Benchmark on NPP Kalinin Unit 3 “Switching-off of one of the four
operating main circulation pumps at nominal power” based on measurements is at its end …

Codes And Methods Improvements for VVER comprehensive safety assessment D3.1 - A
comprehensive review of the available VVER data Page 1 This project has received funding …

This paper presents the results of comparison between CFD code FloEFD and an
experiment in Kozloduy NPP concerning coolant mixing. This comparison is done with …

Calculations using the coupled code system DYN3D/ATHLET were performed in the frame
of the OECD/NEA MSLB benchmark for a VVER-1000 reactor. The coolant mixing inside the …

Generally, the thermal hydraulic (TH) codes need the results of Neutron Kinetics (NK) codes
providing the reactivity properties to calculate neutron flux. Then the TH codes perform the …

Summary This Deliverable 3.3 on “Definition report of SB LOCA+ SG tubing break
benchmark” is a part of CAMIVVER, WP3, Task 3.3:“SB LOCA specification+ SG line break …