Порівняльний аналіз нейтронно-фізичних характеристик кампанії реактора з використанням різних наборів бібліотек ядерних даних для програмного продукту WIMSD5B

• Date: 2015
• Main Authors: Galchenko, V., Mishyn, A.
• Format: Article
• Language: Ukrainian
• Published: State Scientific and Technical Center for Nuclear and Radiation Safety 2015
• Online Access: https://nuclear-journal.com/index.php/journal/article/view/304
• Journal Title: Nuclear and Radiation Safety

The accuracy and quality of steady-state and transient calculations with 3D core kinetics codes depend heavily on the quality of neutronic constants used in calculations. Current paper presents comparative analysis of VVER-1000 core calculations by means of DYN3D code with neutronic constants prepared using WIMSD5B code with implementation of different nuclear data libraries. The quality of results obtained using WIMSD5B can be improved by means of updating its nuclear data library. Libraries under consideration have been developed as a part of WIMSD Library Update Project (WLUP) held by IAEA and have the following names: ENDFB-6, ENDFB-7, IAEA, JEF2.2, JEFF3.1 and JENDL3. Libraries’ performance was tested by simulating the 8th fuel cycle of KhNPP-2 and comparing simulation results with real operational parameters. Libraries listed above were used for preparation of neutronic constants for VVER-1000 fuel, operated at KhNPP-2 during 1-7 fuel cycles and, as a result, separate neutronic constants’ sets and initial burnup distribution for the 8th fuel cycle were obtained for each library. Simulation and operational data were compared based on such criteria as cycle duration, boron concentration and power peaking factors over core for four different moments of cycle. Results verify that simulation data is in good agreement with operational data, and results obtained using JEF2.2 library are of good quality in terms of criteria listed above.