Advanced marine reactor MRX and its application for electricity and heat co-generation
Creators
- 1. Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken (Japan)
- 2. Research Organization for Information Science and Technology, Tokai-mura, Naka-gun, Ibaraki-ken (Japan)
Description
The basic concept of an innovative advanced marine reactor MRX has been established by design study toward the goals of light-weightiness, compactness, and safety and reliability improvement with adoption of several new technologies. The MRX is the integral-type PWR aimed for use of ship propulsion. Adoption of a water-filled containment makes the reactor light-weighted and compact greatly. The total weight and volume of the reactor are 1600 tons and 1210 m3, which are equivalent to halves of the Mutsu, although the reactor power of MRX is three times greater. An engineered safety system of the MRX is a simplified passive system, function of which is confirmed by the safety analysis to be able to keep the reactor integrity even in a case of accident. Reliability of the system is evaluated by the PSA and revealed to have two orders smaller core damage occurrence frequency than existing PWRs. The MRX can be applied to an energy supply system of electricity and heat co-generation. Concept of the nuclear energy supply system is designed to generate electricity, heat and fresh water. The nuclear barge is shown to be a possible nuclear energy supply system with advantage of being easily moveable. (author)
Files
31058473.pdf
Files
(899.4 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:ef9dda3ab07d62af4cea8bead6443b9d
|
899.4 kB | Preview Download |
Additional details
Publishing Information
- Imprint Title
- Small power and heat generation systems on the basis of propulsion and innovative reactor technologies. Proceedings of an advisory group meeting
- Imprint Pagination
- 196 p.
- Journal Page Range
- p. 85-106
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1172
Conference
- Title
- Advisory group meeting on small power and heat generation systems on the basis of propulsion and innovative reactor technologies
- Dates
- 20-24 Jul 1998
- Place
- Obninsk (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31058473
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COGENERATION; DESALINATION PLANTS; DESIGN; DUAL-PURPOSE POWER PLANTS; FEASIBILITY STUDIES; JAPAN; POWER GENERATION; PWR TYPE REACTORS; REACTOR SAFETY; RELIABILITY; SHIP PROPULSION REACTORS; SPECIFICATIONS
- Descriptors DEC
- ASIA; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; INDUSTRIAL PLANTS; POWER GENERATION; POWER PLANTS; POWER REACTORS; PROPULSION REACTORS; REACTORS; SAFETY; STEAM GENERATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 16 refs, 14 figs, 8 tabs