Design, fabrication and installation of reactor internals for prototype FBR
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Tsuruga (Japan). Monju Construction Office
- 2. Mitsubishi Heavy Industries Co., Ltd., Kobe (Japan). Kobe Shipyard and Machinery Works
Description
Monju, a 280 MWe prototype fast breeder reactor, completed its construction in April 1991, and is now under preoperational tests for the forthcoming initial criticality. The design study of reactor internals (R/I), for 300 MWe class FBR based on the design experience of Monju R/I, and the fabrication and the installation of Monju R/I are described herein. The Reactor Structure is made up of a reactor vessel (RV), a core, R/I, and a shield plug. The RV forms coolant boundary and supports R/I. The shield plug is mounted on the RV pedestal and serves as a lid of RV and loads fuel handling machine and control rod driving mechanisms. R/I is composed of core support plates (CSP) and a core barrel and their supporting structures to RV, and supports core elements (C/E), such as fuel subassemblies, blanket fuel subassemblies, control rods and neutron shielding subassemblies. It also provides a coolant path from the inlet Plenum to each of C/E. R/I has various functions, such as distribution of a coolant, the hydraulic hold-down for C/E and prevention of fuel subassembly misloading. The core barrel is a cylindrical structure surrounding C/E and prevents C/E from deforming either by thermal expansion or by a seismic load, At first , some features of a R/I design are described, and then the fabrication and the installation of Monju R/I are described
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers (ASME).
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0637-5
- Imprint Title
- 2nd ASME-JSME international conference on nuclear engineering -- 1993
- Imprint Pagination
- 914 p.
- Journal Page Range
- p. 835-839.
Conference
- Title
- 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
- Dates
- 21-24 Mar 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058930
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; FABRICATION; HYDRAULICS; INSTALLATION; MONJU REACTOR; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR CORE RESTRAINTS; STRESS ANALYSIS
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; RESTRAINTS; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-930352--.