JOPSS - Search Results

JAEA Reports

None

*; Shimada, Takashi*

PNC TN244 84-04, 87 Pages, 1984/07

PNC-TN244-84-04.pdf:2.48MB

no abstracts in English

JAEA Reports

Operational Experience from the Experimental Fast Reactor Joyo

*; *; *; *; *

PNC TN941 82-217, 48 Pages, 1982/10

PNC-TN941-82-217.pdf:1.08MB

None

JAEA Reports

Experience with, and Programme of, FBR and HWR Development in Japan

*; *; *

PNC TN341 83-25, 17 Pages, 1982/09

PNC-TN341-83-25.pdf:0.5MB

Experience with, and programme of, FBR and HWR development in Japan. Nuclear power generation in Japan is moving forward on the long-term development programme of nuclear power from the LWR to the FBR, essentially in the same way as in other advanced nuclear countries. In this development programme the unique HWR is also included; It can use plutonium produced in LWRS together with depleted uranium before the introduction of commercial FBRs. This report describes the status of the FBR and HWR development project being carried out by the power reactor and nuclear fuel development corporation (PNC) based upon the long-term programme on research, development and utilization of nuclear energy in Japan. Operational experience and technical results are shown for the experimental fast reactor Joyo (100 MW(th)), which reached initial criticality in 1977. The status of the 280 MW(e) prototype reactor Monju, under constructionas of 1982, is described. The conceptual design of the subsequent 1000MW(e) ...

JAEA Reports

The second integrated leak rate of the JOYO pressure containment vessel

*; Enomoto, Toshihiko*; *; *; *; *; *

PNC TN943 80-01, 70 Pages, 1980/03

PNC-TN943-80-01.pdf:1.78MB

In December 1979, the integrated leak rate test (ILRT) of the JOYO reactor pressure containment vessel was conducted, as part of the JOYO annual inspection, to confirm the leaktightness of the containment vessel. The test was tbe second ILRT perfomed since initial sodium fill (the first ILRT was carried out in February, 1978). As a result of the test, leak rates of 0.034 0.021 %/day by the absolute pressure method and of 0.0390.006 %/day by the reference chamber method were obtained. These leak rates were almost the same as those obtained in the first test which were 0.0360.011 %/day and 0.036 0.008 %/day, respectively. After combining results from local leak tests and correcting for measuring errors, and the compensated leak rate was found to be well within the leak rate limit of 1.90 %/day which was established by the safety criteria of the containment. These test results demonstrate that the JOYO containment vessel manitains the leaktightness which is required for the functional integrity of the containment in an accidental condition. The successful completion of both the first and second ILRT showed that the test methods and procedures used for leak tests of the JOYO Liquid Metal Fast Reactor are accurate and practical.

JAEA Reports

"JOYO" Start-up test report; Initial criticality test

Yamamoto, Hisashi*; *; *; Sekiguchi, Yoshiyuki*; *; *

PNC TN941 80-04, 221 Pages, 1980/01

PNC-TN941-80-04.pdf:29.27MB

Critical approach test started from March 16, 1977. The core had been loaded with dummy sub-assemblies of 55, blanket sub-assemblies of 203, and reflectors of 48, in the early stage of the functional test period. The neutron source of an antimony-beryllium type was loaded at a position just outside the predicted critical core. The source intensity was of approximate 10 $^{10}$ n/sec. Three extra neutron counting channels were provided for monitoring the counting rates during the tests. In the critical approach, the dummy sub-assemblies (and some blanket sub-assemblies) were replaced by core sub-assemblies from the core center with fifteen steps. A criterion was applied to number of fuels to be loaded at each step, which was limited within half the number of fuels to be loaded to the critical core estimated by inverse multiplication curves. The effect which was caused by neutron multiplication of fuels at the in-vessel fuel storage rack was estimated, and the inverse multiplication curve was corrected. The criticality was achieved on April 24 with 64 fuel sub-assemblies, which was predicted as 61 5.