Towards establishment of an efficient approach for validation of PWR full core Monte Carlo simulations at hot zero power conditions

• DOI: 10.1016/j.pnucene.2024.105203
• Publication Date: 2024-04-12T20:09:14Z
• Authors: L. Berry; A. Vasiliev; M. Hursin; D. Rochman; M. Frankl; H. Ferroukhi
• Keywords: Burnup; Control rod; Core model; Neutron Transport

The use of Monte-Carlo (MC) simulations for neutronic reactor core physics has been high interest since long. Resulting MC models would be relevant, e.g., high-resolution assessments the local neutron flux and power gradients, generally beyond modeling capabilities engineering deterministic codes regular full simulations. Such particular importance advancement operation safety or, example, to support designing new materials testing experimental programs at operational reactors, advanced cores, etc. Nevertheless, MC-based core-follow burnup calculations are still challenging routine applications. Therefore, Laboratory Reactor Physics Thermal-Hydraulics (LRT) developed in recent years a "cycle-check-up" (CHUP) concept. It allows transfer operating conditions (coolant fuel temperatures, density moderator, boron concentration, position control rods) burned isotopic compositions from validated reference models, based on state-of-the-art CASMO5/SIMULATE5/SNF, codes, such as Serpent 2.2 or MCNP6®. This article presents work performed optimization methodology. is newly adaptive clustering maximize accuracy while keeping memory consumption constant. In addition, thanks availability access additional data Swiss plants, start-up tests PWRs, there valuable opportunity extend validation database Burnup Credit applications using reactors data. paper ongoing towards verification (V&V) configurations against results models. radial distribution model pin-wise composition was verified, yielding relative deviations [-9, 6]% range nodal solver. Additionally, hot zero (HZP) conditions, analysis measurements showed −100 ± 2 pcm deviation criticality, which considered an excellent agreement.