Analysis of steam line break of SMART using RETRAN-3D/INT
Creators
- 1. Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering
Description
RETRAN-3D has been modified to be suitable to safety analysis for integral type marine reactor with modular helical-coiled steam generator cassettes. The modified RETRAN-3D, RETRAN-3D/INT, has helical coil heat conductor model and heat transfer coefficient models for tube and shell sides of helical-coiled steam generator. In addition, moving models are added to simulate the effect of ship motions such as inclination, heaving, rolling and so on. RETRAN-3D/INT has been verified with natural circulation experiment conducted in Seoul National University and the analysis results for the first Japanese nuclear ship, MUTSU. In this study, the safety analysis for SMART, which has been developed by Korea Atomic Energy Research Institute, is performed to examine the applicability of RETRAN-3D/INT to the safety analysis of SMART. The steam line break is selected as reference case. The break type is assumed to the guillotine break. The loss of offsite power is considered as a coincident event and the failure of single train of passive residual heat removal system is assumed as single failure. From the results, it is found that RETRAN-3D/INT can appropriately simulate the transient of SMART and the improvement of non-condensable gas model is required. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-11: Proceedings of the 11th international conference on nuclear engineering
- Imprint Pagination
- [3610 p.]
- Journal Page Range
- [7 p.]
Conference
- Title
- 11. international conference on nuclear engineering
- Acronym
- ICONE-11
- Dates
- 20-23 Apr 2003
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35073066
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESALINATION REACTORS; HEAT TRANSFER; INTEGRATED COOLING SYSTEMS; OUTAGES; POWER LOSSES; PRIMARY COOLANT CIRCUITS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; RHR SYSTEMS; RUPTURES; SAFETY ANALYSIS; SHIP PROPULSION REACTORS; STEAM GENERATORS; STEAM LINES
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; COOLING SYSTEMS; ENERGY LOSSES; ENERGY SYSTEMS; ENERGY TRANSFER; FAILURES; LOSSES; PIPELINES; POWER REACTORS; PROPULSION REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; VAPOR GENERATORS
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, Track No. 11, Session 11-6, ICONE-36230