Construction and function tests of experimental fast reactor 'JOYO'
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
Experimental fast reactor ''JOYO'' is the first sodium cooled fast reactor using Pu-U mixed oxide fuel. The construction of the reactor started in March, 1970 and reached initial criticality at 11:07 a.m. on April 24, 1977. The power of ''JOYO'' will reach 50 MWt in the initial power-up test and after further tests going to 75 MWt, the modification of the core is expected. ''JOYO'' will then start working as an irradiation test reactor at 100 MWt. The results of the use of the reactor together with the operational and maintenance experience will contribute to the development of the prototype fast breeder reactor ''MONJU'' and the following breeder reactors of Japan. In this report, the schedule and outline of the construction, technical problems which were met during construction, reconstruction due to design review, results of the function tests and the experience of initial fuel loading to reach initial criticality are given. (auth.)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.19.680Additional details
Additional titles
- Original title (Japanese)
- 高速実験炉「常陽」の建設と機能試験
Identifiers
- DOI
- 10.3327/jaesj.19.680;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 19
- Journal Issue
- 10
- Journal Page Range
- p. 680-694
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53100843
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BUILDINGS; CONSTRUCTION; CRITICALITY; FUEL ASSEMBLIES; HEAT EXCHANGERS; JOYO REACTOR; LEAK TESTING; PERFORMANCE TESTING; PLANNING; PRIMARY COOLANT CIRCUITS; REACTOR FUELING; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR VESSELS; REGULATIONS; SODIUM; SPECIFICATIONS
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; CONTAINERS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LAWS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MAINTENANCE; METALS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTOR OPERATION; REACTORS; RESEARCH AND TEST REACTORS; TESTING
Optional Information
- Notes
- 5284800; This record replaces 09399057