Passive safety systems for decay heat removal of MRX
Creators
- 1. Japan Atomic Energy Research Inst., Ibaraki (Japan). Nuclear Ship System Lab.
Description
The MRX (marine Reactor X) is an advanced marine reactor, its design has been studied in Japan Atomic Energy Research Institute. It is characterized by four features, integral type PWR, in-vessel type control rod drive mechanisms, water-filled containment vessel and passive decay heat removal system. A water-filled containment vessel is of great advantage since it ensures compactness of a reactor plant by realizing compact radiation shielding. The containment vessel also yields passive safety of MRX in the event of a LOCA by passively maintaining core flooding without any emergency water injection. Natural circulation of water in the vessels (reactor and containment vessels) is one of key factors of passive decay heat removal systems of MRX, since decay heat is transferred from fuel rods to atmosphere by natural circulation of the primary water, water in the containment vessel and thermal medium in heat pipe system for the containment vessel water cooling in case of long terms cooling after a LOCA as well as after reactor scram. Thus, the ideal of water-filled containment vessel is considered to be very profitable and significant in safety and economical point of view. This idea is, however, not so familiar for a conventional nuclear system, so experimental and analytical efforts are carried out for evaluation of hydrothermal behaviours in the reactor pressure vessel and in the containment vessel in the event of a LOCA. The results show the effectiveness of the new design concept. Additional work will also be conducted to investigate the practical maintenance of instruments in the containment vessel. (author). 4 refs, 9 figs, 2 tabs
Files
28021949.pdf
Files
(254.4 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:54aaf9ce03858d7efc2813b78b0cf4e6
|
254.4 kB | Preview Download |
Additional details
Publishing Information
- Imprint Title
- Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting
- Imprint Pagination
- 357 p.
- Journal Page Range
- p. 207-218.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--920
Conference
- Title
- Advisory group meeting on technical feasibility and reliability of passive safety systems for nuclear power plants.
- Dates
- 21-24 Nov 1994.
- Place
- Juelich (Germany).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28021949
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CONTAINMENT; DESIGN; NATURAL CONVECTION; REACTOR SAFETY; SAFETY ENGINEERING; SHIP PROPULSION REACTORS; WATER
- Descriptors DEC
- CONVECTION; ENERGY TRANSFER; HEAT TRANSFER; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PROPULSION REACTORS; REACTORS; REMOVAL; SAFETY