Scale model test and transient analysis of steam injector driven passive core injection system for innovative-simplified nuclear power plant
- 1. Tokyo Electric Power Co., Inc., R and D Center, Yokohama, Kanagawa (Japan)
- 2. Hokkaido Univ., Graduate School of Engineering, Sapporo, Hokkaido (JP)
Description
A Steam Injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater. This provides SI with capability to serve also as a direct-contact feed-water heater that heats up feed-water by using extracted steam from the turbine. We are developing technology for 'Innovative Simplified Nuclear Power Plants' in order to further improve the economy and safety of nuclear power plants. Our technology development aims to significantly simplify equipment and reduce physical quantities by applying 'High-Efficiency SI', which are applicable to a wide range of operation regimes beyond the performance and applicable range of existing SIs and enables unprecedented multistage and parallel operation, to the low-pressure feed-water heaters and Emergency Core Cooling Systems (ECCS) of nuclear power plants, as well as achieve high inherent safety to prevent severe accidents by keeping the core covered with water (a severe accident-free concept). The innovative-simplified nuclear power plant consists of a simplified feed-water heating system, a passive core injection system and a passive containment cooling system. This report describes the results of the scale model test, and the transient analysis of SI-driven passive core injection system. A part of this report are fruits of research which is carried out by Tokyo Electric Power Company (TEPCO), Toshiba Corporation, and seven universities in Japan, funded from the Ministry of Economy, Trade and Industry (METI) of Japan as the national public research-funded program. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [5 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39048701
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ECCS; FEEDWATER HEATERS; HIGH PRESSURE COOLANT INJECTION; LOW PRESSURE COOLANT INJECTION; NUMERICAL ANALYSIS; SCALE MODELS; STEAM INJECTION; STEAM JET EJECTORS; T CODES; TRANSIENTS; VALIDATION; VOID FRACTION
- Descriptors DEC
- COMPUTER CODES; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID INJECTION; HEATERS; MATHEMATICS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; STRUCTURAL MODELS; TESTING; THERMAL REACTORS; VAPOR JET EJECTORS; WATER COOLED REACTORS; WATER MODERATED 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 Final Paper, Paper ID ICONE15-10427.pdf; 10 refs., 11 figs., 1 tab.