Published March 1995
| Version v1
Journal article
MONJU function test
- 1. Power Reactor and Nuclear Fuel Development Corp., Tsuruga, Fukui (Japan). Monju Construction Office
Description
The function test of MONJU was conducted from May 1991 to December 1992 in order to confirm individual systems' functions and their integrated function. The reactor cooling system, plant control system, refueling system and containment vessel were verified their expected functions, under the air atmosphere, argon gas filled and sodium filled conditions, step by step. In the integrated function test on the reactor cooling system, data were obtained to improve analytical precision of the codes on plant dynamic, SUPER-COPD, and natural circulation, NATURAL. (author)
Additional details
Publishing Information
- Journal Title
- Donen Giho
- Journal Issue
- no.93
- Journal Page Range
- p. 18-31.
- ISSN
- 0289-6605
- CODEN
- DOGIEL
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 27002418
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCURACY; FUEL ELEMENTS; MONJU REACTOR; N CODES; NATURAL CONVECTION; PERFORMANCE TESTING; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; REMOTE HANDLING EQUIPMENT; S CODES
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; CONTAINERS; CONTROL SYSTEMS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS HANDLING EQUIPMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS; TESTING