Published May 2009 | Version v1
Miscellaneous

Numerical Simulation of RCCS under LPCC Accident in PMR600 Using CFD

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

The Reactor Cavity Cooling System (RCCS) is the ultimate heat sink of the core decay heat under accident conditions. RCCS has a capability to limit the reactor pressure vessel temperature under the design safety limit following accidents such as High Pressure Conduction Cooling (HPCC) and Low Pressure Conduction Cooling (LPCC). The initiating event for LPCC is the guillotine rupture of a coaxial pipe or a simultaneous break of all the connecting pipes between the reactor pressure vessel and the heat transport system. A simulation for LPCC accident of PMR600 was conducted by using the GAMMA+ code. The GAMMA+ code, which is developed to analyze the thermo-fluid transients in HTGR, is a system code and it treats the momentum and energy transfer differently from the computational fluid dynamics (CFD). There might exist the difference between the estimations using GAMMA+ and CFD. In a previous study the steady state performance of RCCS in HTGR (High Temperature Gas-Cooled Reactor) was calculated using the computational fluid dynamics with the porous medium approach and the axisymmetric assumption. Even though this assumption reduces the computational time significantly, it changes the RCCS tube shape. This may change the behavior of RCCS. In this study, we develop three candidates of RCCS for CFD, conduct the unsteady simulations for the LPCC accident, and compare the results with the GAMMA+ code. By doing this, we can find a suitable model for RCCS when CFD is conducted with the axisymmetric assumption

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2009 spring meeting of the KNS
Dates
18-23 May 2009
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40099326
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT; HEAT SINKS; HTGR TYPE REACTORS; PERFORMANCE; PIPES; PRESSURE VESSELS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; SIMULATION
Descriptors DEC
CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; SINKS; TUBES

Optional Information

Notes
5 refs, 4 figs, 1 tab