Published 2004 | Version v1
Computer medium

Two-phase flow in natural circulation system of the integrated modular water reactor (IMR)

  • 1. Kyoto Univ., Dept. of Nuclear Engineering, Kyoto (Japan)
  • 2. Mitsubishi Heavy Industries Ltd., Nuclear Systems Engineering Dept., Yokohama, Kanagawa (Japan)
  • 3. Mitsubishi Heavy Industries Ltd., Reactor Core Engineering Dept., Yokohama, Kanagawa (Japan)

Description

Two-phase flow thermal-hydraulics in the design aspect of the Integrated Modular water Reactor (IMR) has being numerically analyzed assisted by the α-flow code. A basic design concept of this small-scale advanced light water reactor adopts the two innovative heat transfer and safety systems, one of which is the Hybrid Heat Transport System (HHTS). The HHTS, combining functions for power and pressure controls, utilizes a two-phase natural circulation passing through the riser and the downcomer section in the reactor vessel. Our concerns have been therefore focused on the analyses of phase distribution in these sections to assure stable reactor operations. The predicted results indicated fairly uniform void distributions in both sections. Degree of the vapor flowing into the downcomer section was also estimated, which is one of the important factors affecting the design of the HHTS. (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
11 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
36093877
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; HEAT; HYBRID SYSTEMS; MODULAR STRUCTURES; NATURAL CONVECTION; NUMERICAL ANALYSIS; THERMAL HYDRAULICS; TRANSPORT; TWO-PHASE FLOW; WATER COOLED REACTORS
Descriptors DEC
CONVECTION; ENERGY; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MATHEMATICS; MECHANICS; REACTORS

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 THUSDAY October 7, 2004, Paper ID N6P 132.pdf; 5 refs., 20 figs.