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JAEA Reports

The 3rd technological meeting of Tokai reprocessing plant

Maki, Akira; ; Taguchi, Katsuya; ; Shimizu, Ryo; Shoji, Kenji;

JNC-TN8410 2001-012, 185 Pages, 2001/04

JNC-TN8410-2001-012.pdf:9.61MB

"The third technological meeting of Tokai Reprocessing plant (TRP)" was held in JNFL Rokkasyo site on March 14$$^{th}$$, 2001. The technical meetings have been held in the past two times. The first one was about the present status and future plan of the TRP and second one was about safety evaluation work on the TRP. At this time, the meeting focussed on the corrosion experrience, in-service inspection technology and future maintenance plan. The report contains the proceedings, transparancies and questionnaires of the meeting are contained.

JAEA Reports

None

; ; ; Takeda, Seiichiro; *; Fujisaku, Kazuhiko*; *

PNC-TN8410 98-116, 147 Pages, 1998/08

PNC-TN8410-98-116.pdf:8.6MB

None

JAEA Reports

None

*; *; ; *; *; Ito, Kenji

PNC-TJ2164 97-004, 38 Pages, 1997/10

PNC-TJ2164-97-004.pdf:3.34MB

JAEA Reports

None

PNC-TN1410 97-031, 638 Pages, 1997/08

PNC-TN1410-97-031.pdf:12.12MB

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ1409 97-012, 25 Pages, 1997/03

PNC-TJ1409-97-012.pdf:0.54MB

no abstracts in English

JAEA Reports

None

*; *; *; *; *

PNC-TJ9124 93-010, 186 Pages, 1993/03

PNC-TJ9124-93-010.pdf:4.37MB

None

JAEA Reports

Introduction of Nuclear Instrumentations and Radiation Measurements in Experimental Fast Reactor 「JOYO」

;

PNC-TN9420 92-005, 83 Pages, 1992/04

PNC-TN9420-92-005.pdf:2.17MB

This report introduces the nuclear instrumentation system and major R&D (research and development) activities using radiation measurement techniques in Experimental Fast Reactor "JOYO". In the introduction of the nuclear instrumentation system, following items are described; (1)system function (2)roles as a reactor plant equipment (3)specifications and charactelistics of neutron detectors, (4)construction and layout of the system. For reactor dosimetry at various irradiation tests and surveillance tests, multi-foil method employed in "JOYO", neutron fluence evaluation using activation foils and HAFM (Helium Accumulation Fluence Monitor) under development are described briefly. The failed fuel detection system and some experimental equipments using radiation measurement techniques are also introduced here with main results obtained by a series of fuel failure simulation experiments. In addition, following R&Ds are picked up as some examples based on radiation measurement technology; (1)burn-up measurement of spent fuel subassembly (2)measurement and evaluation of radiation source distributions (radioactive corrosion products)

JAEA Reports

None

; Sumino, Kozo; ; ; ; ; Terunuma, Seiichi

PNC-TN9410 91-376, 79 Pages, 1991/11

PNC-TN9410-91-376.pdf:1.9MB

None

JAEA Reports

Computer application techniques at 50MW steam generator test facility (I); Development of operation surveillance ( or operation monitoring) system for FBR plant

*; *; *

PNC-TN941 81-52, 296 Pages, 1981/02

PNC-TN941-81-52.pdf:17.15MB

Recently surveillance systems for nuclear power plants are increasingly required for the improvement of plant safety and availability. In order to establish the surveillance system of the prototype fast breeder reactor "MONJU", some techniques have been developed and applied to the 50MW Steam Generator Test Facility ty at OEC. As the first stage of the development, information display techniques for the plant operators and some anomalous state detection techniques are discussed in this paper. The operators can obtain such plant informations as digital and graphic outputs by cathode ray tubes (CRTs) and print out by a lineprinter and typewriters. Also the operators are informed of results of anomalous diagnosis by annunciator alarms moment by moment. Application tests of the anomalous state detection techniques have been carried out. These techniques include a cross check technique of multi-measuring system, a automatic detection system of a small scale sodium-water reaction, a differential alarm and prediction method of the time of anomalous occurrance and a display method of degree of superheat of evaporator (EV) outlet steam. It was concluded by our evaluation of the test results that those techniques are applicable to the "MONJU" design without major modification. We will develop new techniques and improve these systems to make them applicable to "MONJU", considering the "man-machine system", using this test facility.

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