Thermo-hydraulic characteristics of ship propulsion reactor in the conditions of ship motions and safety assessment
Creators
- 1. Ship Research Inst., Mitaka, Tokyo (Japan)
Description
A research project from 1995-1999 had a plan to make experimental studies on (1) safety of nuclear ship loaded with an integral ship propulsion reactor (2) effects of pulsating flow on the thermo-hydraulic characteristics of ship propulsion reactor and (3) thermo-hydraulic behaviors of the reactor container at the time of accident in a passively safe ship propulsion reactor. Development of a data base for ship propulsion reactor was attempted using previous experimental data on the thermo-hydraulic characteristics of the reactor in the institute in addition to the present results aiming to make general analytical evaluation for the safety of the engineering-simulation system for nuclear ship. A general data base was obtained by integrating the data list and the analytical program for static characteristics. A test equipment which allows to visualize the pulsating flow was produced and visualization experiments have started. (M.N.)
Additional details
Publishing Information
- Journal Title
- Kokuritsu Kikan Genshiryoku Shiken Kenkyu Seika Hokoku-Sho
- Journal Issue
- no.37
- Journal Page Range
- p. 16.1-16.3
- ISSN
- 0288-8874
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 29065107
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT SHELLS; HYDRODYNAMICS; JAPAN; MOTION; NUCLEAR SHIPS; PULSATIONS; REACTOR SAFETY; RESEARCH PROGRAMS; SHIP PROPULSION REACTORS
- Descriptors DEC
- ASIA; CONTAINMENT; DEVELOPED COUNTRIES; FLUID MECHANICS; MECHANICS; POWER REACTORS; PROPULSION REACTORS; REACTORS; SAFETY; SHIPS