Published March 2012 | Version v1
Miscellaneous

Assessment of Severe Accident Management Measure Efficiency with MELCOR 1.8.6 Code

Creators

  • 1. Nuclear Research Institute Rez plc, Praha (Czech Republic)

Description

The basic input data for the MELCOR testing comes from the VVER-1000 input model developed in the NRI. The main identified SA measures to be tested are focused on the prevention of high energetic phenomena (HPME and DCH), hydrogen removal using passive autocatalytic recombiners, in-vessel retention using the external flooding of reactor cavity, and passive system for heat removal from containment. Simulation of the fast primary circuit depressurization was vary simple and generally without any unexpected results. Its simulation was done with one additional flow paths with appropriate control using control functions. Methodology for the simulation of hydrogen removal system (HRS) was more complicated, because mass and energy sources into the containment were simulated using the whole plant input model, which includes relatively simple model of the containment. The study of the HRS itself is done with very detailed stand-alone model of the containment. Simulation of the in-vessel retention requested new modeling of reactor cavity with modeling of flow baffle. The MELCOR code was able to simulate this measure

Part of:
Proceedings of the 18th Pacific Basin Nuclear Conference

Additional details

Publishing Information

Publisher
Pacific Nuclear Council
Imprint Place
La Grange Park (United States)
Imprint Title
Proceedings of the 18th Pacific Basin Nuclear Conference
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[1 p.]

Conference

Title
18. Pacific Basin Nuclear Conference
Acronym
PBNC 2012
Dates
18-23 Mar 2012
Place
Busan (Korea, Republic of)

INIS

Country of Publication
United States
Country of Input or Organization
Korea, Republic of
INIS RN
45032770
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; CONTAINMENT; CONTROL; EFFICIENCY; ENRICHED URANIUM REACTORS; HYDROGEN; M CODES; MANAGEMENT; REACTOR ACCIDENTS; REMOVAL
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ELEMENTS; NONMETALS; REACTORS; SIMULATION

Optional Information