Published 2011 | Version v1
Miscellaneous

Steam condensation induced water hammer simulations for different pipelines

  • 1. KFKI Atomic Energy Research Inst. (AEKI) of the Hungarian Academy of Sciences, Thermo-hydraulic Department, Budapest (Hungary)

Description

We investigate steam condensation induced water hammer (CIWH) phenomena and present theoretical results for different kind of pipelines. We analyze the process with the WAHA3 model based on two-phase flow six first-order partial differential equations that present one dimensional, surface averaged mass, momentum and energy balances. A second order accurate high-resolution shock-capturing numerical scheme was applied with different kind of limiters in the numerical calculations. At first, we present calculations for various pipelines in the VVER-440-312 type nuclear reactor. Our recent calculation clearly shows that the six conditions of Griffith are only necessary conditions for CIWH but not sufficient. As second results we performed calculations for various geometries and compare with the theory of Chun. (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
[9 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
47071289
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; PIPELINES; STEAM; TWO-PHASE FLOW; VAPOR CONDENSATION; WATER HAMMER; WWER TYPE REACTORS
Descriptors DEC
ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Paper NURETH14-048, 13 refs., 2 tabs., 1 fig