Published 1996
| Version v1
Miscellaneous
Analysis of thermal-hydraulics of a marine reactor in an oscillating acceleration field
Description
In this study the RETRAN-03 code was modified to analyze the thermal-hydraulic transients under three-dimensional ship motions for the application to the future marine reactors. First Japanese nuclear ship MUTSU reactor have been analyzed under various ship motions to verify this code. As results, typical thermal-hydraulic characteristics of marine reactors such as flow rate oscillations and S/G water level oscillations are successfully simulated at various conditions
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- 3566 p.
- Journal Page Range
- p. 1193-1198
Conference
- Title
- 1996 spring meeting of the KNS
- Dates
- 31 May - 1 Jun 1996
- Place
- Cheju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37120258
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCELERATION; FLOW RATE; OSCILLATIONS; R CODES; REACTORS; STEAM GENERATORS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- BOILERS; COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICS; VAPOR GENERATORS
Optional Information
- Notes
- 4 refs, 9 figs