Published January 18, 2011 | Version v1
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Analysis of the TMI-2 accident with the code ATHLET-CD

  • 1. GRS mbH, Koeln (Germany)

Description

Thermal-hydraulic phenomena play a decisive role for the course of severe accidents in light water reactors. Therefore, the simulation of such accidents with computer codes requires comprehensive and detailed modelling of these processes. The system code ATHLET-CD is being developed for a realistic simulation of accidents with core degradation and for the evaluation of accident management measures. It applies the detailed and validated models of the thermal-hydraulic code ATHLET in an efficient coupling with dedicated models for core degradation and fission product behaviour. The capabilities of the current code version are demonstrated by a calculation of the Three Mile Islands unit 2 (TMI-2) accident. The first three phases of the accident, up to the melt relocation into the lower plenum, were successfully simulated by the code in a reasonable computing time. The calculated system pressure and pressurizer level after pump trip, during pump restart and until core slump are in acceptable agreement with the measured data. The calculated hydrogen production up to pump restart is in accordance with the value deduced from plant examination. However the hydrogen generation during the quench phase following the pump restart as well as the amount of liquid melt at the end of Phase 3 are underestimated in comparison with deduced values. Further model extensions mainly regarding the quenching of degraded core material, fracture and relocation of solid fuel rods as well as the simulation of the debris bed behaviour are necessary to further improve the simulation. (authors)

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Part of:
In-Vessel Coolability. Workshop Proceedings, in collaboration with EC-SARNET

Additional details

Publishing Information

Imprint Title
In-Vessel Coolability. Workshop Proceedings, in collaboration with EC-SARNET
Imprint Pagination
572 p.
Journal Page Range
p. 413-438
Report number
NEA-CSNI-R--2010-11

Conference

Title
Workshop on In-Vessel Coolability
Dates
12-14 Oct 2009
Place
Issy-les-Moulineaux (France)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
48026399
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
A CODES; COMPUTERIZED SIMULATION; MELTDOWN; REACTOR ACCIDENT SIMULATION; THERMAL HYDRAULICS; THREE MILE ISLAND-2 REACTOR; VALIDATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
11 refs.