Published 2004 | Version v1
Computer medium

Downward facing boiling and steam venting under simulated ERVC conditions

  • 1. Pennsylvania State Univ., Dept. of Mechanical and Nuclear Engineering, Pennsylvania State Univ., University Park, PA (United States)
  • 2. Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States)
  • 3. Seoul National Univ., Dept. of Nuclear Engineering, Seoul (Korea, Republic of)
  • 4. Korea Atomic Energy Research Inst., Yuseoung, Taejon (Korea, Republic of)

Description

This study investigates the enhancement of external reactor vessel cooling (ERVC) under severe accident conditions. One feasible method involves the use of an enhanced vessel/insulation design to facilitate steam through the bottleneck of the annular channel between the reactor pressure vessel (RPV) and the surrounding insulation structure. To assess the viability of the enhanced vessel/insulation design, steady-state boiling experiments were performed using test vessels surrounded by an enhanced ERVC insulation structure. When compared to the flow behavior predicted by a steam venting model, good agreement is obtained. Improvement of the steam venting process through the narrow gap location is observed, which in turn leads to the enhancement of local critical heat flux values when compared to the case without using an enhanced vessel/insulation design. Detailed analysis of the experimental video record provides further physical evidence for the buoyancy-driven two-phase flow inside the flow channel as well as the bubble dynamics near the local CHF limit. (author)

Part of:
NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
Imprint Pagination
3690 p.
Journal Page Range
15 p.

Conference

Title
6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
Acronym
NUTHOS-6
Dates
4-8 Oct 2004
Place
Nara (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
36093879
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOILING; COOLING; CRITICAL HEAT FLUX; DESIGN; HEAT TRANSFER; MELTDOWN; REACTOR VESSELS; SIMULATION; STEAM; THERMAL INSULATION; VENTILATION
Descriptors DEC
ACCIDENTS; CONTAINERS; ENERGY TRANSFER; HEAT FLUX; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name THURSDAY October 7, 2004, Paper ID N6P 149.pdf; 14 refs., 12 figs.