Published 2011 | Version v1
Miscellaneous

MCCI simulation comparison between MELCOR and CORQUENCH

  • 1. Univ. of Wisconsin-Madison, Wisconsin (United States)

Description

This paper presents a comparison between the MELCOR and CORQUENCH codes in modeling the progression of a reactor scale ex-vessel core melt. This study investigates the impact of advanced modeling options on the progression of molten corium-concrete interactions (MCCI). Two cooling phenomena, water ingression and melt eruptions, and the crust anchoring phenomenon were shown to largely impact the accident progression. Recommendations are made concerning updating CONRCON-Mod3 within MELCOR and future research activities. (author)

Part of:
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-05-6
Imprint Title
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
Imprint Pagination
766 Megabytes
Journal Page Range
[14 p.]

Conference

Title
14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
Acronym
NURETH-14
Dates
25-30 Sep 2011
Place
Toronto, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47071167
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONCRETES; CORE CATCHERS; CORIUM; MELTDOWN; REACTOR ACCIDENTS; REACTORS; SIMULATION
Descriptors DEC
ACCIDENTS; BUILDING MATERIALS; MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS

Optional Information

Notes
Paper NURETH14-289, 19 refs., 8 tabs., 10 figs.