Published 2006 | Version v1
Miscellaneous

A CFD Analysis of Complex Flow Distribution in KSNP Reactor Vessel Lower Structures Based on 3D CAD

  • 1. ENESYS, Taejon (Korea, Republic of)
  • 2. Korea Electric Power Research Institute, Institute, Taejon (Korea, Republic of)
  • 3. Pusan National Univ., Busan (Korea, Republic of)

Description

During design period and commercial operation of a nuclear power plants (NPP) lots of safety analyses are performed because nuclear regulatory body requires the vendor and utility to report lots of simulation results in order to ensure the safe operation of the NPP. In general, the simulations are carried out using vendor-specific design codes and best-estimate system analysis codes. The thermal-hydraulic system codes have powerful features such as multi-phase flow model, phase-change model and event programming. During the past decade, however, computing power has been dramatically enhanced in terms of speed, capability and expenses. On the other hand, mechanistic computational fluid dynamics(CFD) codes also made a progress during these days. Nowadays, commercial CFD programs are applied to very large and complex systems design such as core design, HVAC design and chemical plant buildings. In spite of the recent progress in computing hardware and software the nuclear industry still uses conventional system codes based on lumped parameter model. It is believed to be beneficial to take advantage of advanced commercial CFD codes in safety analysis and design of NPPs

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2006 autumn meeting of the KNS
Dates
2-3 Nov 2006
Place
Kyongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38049379
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BOUNDARY CONDITIONS; C CODES; COMPUTERIZED SIMULATION; DESIGN; PRESSURE DROP; PWR TYPE REACTORS; REACTOR VESSELS; SAFETY ANALYSIS; VELOCITY
Descriptors DEC
COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref, 5 figs, 2 tabs