Published 2019 | Version v1
Miscellaneous Restricted

Assessment of re-criticality in severe accident configurations using MCNP and MELCOR

Description

The paper presents a method to evaluate the potential re-criticality issues in severe accident configurations. This method is developed by Tractebel ENGIE, using respectively MCNP and a dataset of MELCOR calculations. The work has focused on the in-vessel phase and more particularly on a TMI-2-like configuration. A model based on a corium sphere approximation associated to the detailed WIMS10 fuel characterization has allowed us to highlight some degraded configurations presenting re-criticality risks associated to the intact fuel rods that remain in the core. The resulting distributions of the multiplication factor (keff) in function of several parameters (core degradation fraction, boron concentration in water, core burnup, moderator and fuel temperature,...) has allowed us to identify the more sensitive parameters regarding the re-criticality risk. The core degradation fraction is the major parameter, even for a high level of degradation, which highlights the influence of the intact peripheral fuel rods. The boron concentration in the water injected after the accident also plays an important role: even with a relatively high core degradation fraction (about 60%) and a consequent boron concentration (1500 ppm) the re-criticality risk cannot be excluded. These conclusions being well dependent on the assumptions and conservatisms of the study Finally a 'surrogate model' - regression model based on artificial neural network - is presented for the prediction of the multiplication factor for TMI-2-like configurations.

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Additional details

Publishing Information

Imprint Pagination
10 p.
Report number
INIS-FR--21-0263

Conference

Title
ICNC 2019 - 11. international conference on nuclear criticality safety
Dates
15-20 Sep 2019
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
52015208
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; CORIUM; CRITICALITY; M CODES; MELTDOWN; PARAMETRIC ANALYSIS; RISK ASSESSMENT
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; REACTOR ACCIDENTS; SEVERE ACCIDENTS; SIMULATION

Optional Information

Notes
6 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses