Published 2015 | Version v1
Book

CFD based buoyant stratification factor for augmenting lumped parameter hydrogen concentration predictions

  • 1. Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai (India)
  • 2. Atomic Energy Regulatory Board, Mumbai (India)

Description

Hydrogen distribution inside nuclear reactors containment following postulated design basis accident (DBA) and beyond design basis accident (BDBA) is a challenge and has become more evident after the Three-Mile-Island (TMI) in 1979 in USA, Chernobyl disaster 1989 and the recent Fukushima hydrogen explosion in 2011. The assessment of hydrogen transport behavior in typical multi-compartment containment geometries of the NPPs was initially based on the simplified assumption of uniform mixing of hydrogen in the entire containment atmosphere. This approach was subsequently evolved into a lumped parameter simulation considering a network of compartments interconnected by junctions. Yet, it was not satisfactory enough as the stratification of hydrogen within a compartment could not be predicted. Computational Fluid Dynamics (CFD) codes have the potential to address the local stratification issues by performing more detailed spatial calculations after considering the buoyancy terms on a highly localized basis. BARC has proposed a new approach where the lumped parameter calculation is improved using stratification factors obtained by CFD modelling. The present paper highlights the evolution of stratification factor for augmenting the lumped parameter predictions using two approaches. In the first approach, a stratification factor has been established on the basis of review of experimental data available in open literature. Since the experiments are almost always performed in smaller geometries as compared to the actual containment scale, a scaling assisted CFD simulation methodology has been used to derive these factors for nuclear reactor in the next approach. (author)

Part of:
Proceedings of the international workshops on NPPs-safety and sustainability and new horizons in nuclear reactor thermal-hydraulics and safety

Additional details

Publishing Information

Publisher
Atomic Energy Regulatory Board
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international workshops on NPPs-safety and sustainability and new horizons in nuclear reactor thermal-hydraulics and safety
Imprint Pagination
769 p.
Journal Page Range
6 p.

Conference

Title
international workshop on NPPs-safety and sustainability; NHNRTHS-2015: international workshop on new horizons in nuclear reactor thermal-hydraulics and safety
Acronym
CANSAS-2015
Dates
8-11 Dec 2015
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
48073089
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; DESIGN-BASIS ACCIDENTS; FLUID MECHANICS; HYDROGEN; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; CONTAINMENT; ELEMENTS; ENGINEERED SAFETY SYSTEMS; MECHANICS; NONMETALS; SAFETY; SIMULATION

Optional Information

Notes
7 refs., 6 figs., 1 tab.