Published December 2020 | Version v1
Report

Mexico: Study of Hydrogen Distribution in a BWR MARK II Containment as Result of Emergency Water Injection During the Evolution of a Severe Accident

  • 1. Departamento de Sistemas Nucleares, Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca S/N, La Marquesa, Ocoyoacac, Estado de México, C.P. 52750 (Mexico)

Description

In this paper, the design basis accident (DBA) of a BWR/5 evolving to severe accident, by disabling all ECCSs, is the scenario chosen to study hydrogen generation in core, and then to determine the hydrogen distribution in the drywell. Alternative scenarios are simulated by allowing the recovery of the high pressure cooling system (HPCS) at different times during this scenario. The code RELAP/SCDAPSIM was used to simulate the severe accident scenarios, and the code GASFLOW was used to compute the 3D hydrogen distribution in a drywell of a Mark II primary containment. Results of hydrogen and fission product generation in core, as well as state of core degradation are presented. Then, a comparison of results of hydrogen concentration in drywell between the base case and the cases where coolant injection is recovers is presented. (author)

Part of:
Developments in the Analysis and Management of Combustible Gases in Severe Accidents in Water Cooled Reactors following the Fukushima Daiichi Accident. Supplementary Files

Additional details

Publishing Information

ISBN
978-92-0-132020-9
Imprint Title
Developments in the Analysis and Management of Combustible Gases in Severe Accidents in Water Cooled Reactors following the Fukushima Daiichi Accident. Supplementary Files
Imprint Pagination
330 p.
Journal Page Range
p. 215-224
ISSN
1011-4289
Report number
IAEA-TECDOC--1939(SUPPLEMENTARY FILES)

Conference

Title
Technical Meeting on Hydrogen Management in Severe Accidents
Dates
25-28 Sep 2018
Place
Vienna (Austria)

Optional Information

Notes
5 refs., 9 figs.