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JAEA Reports

Development of an intense positron source(II); An adaptive estimate of a superconducting Magnet for a positron focusing device

; *; *; *; ; *; *

PNC TN9410 98-053, 43 Pages, 1998/04

PNC-TN9410-98-053.pdf:3.62MB

In the Power Reactor and Nuclear Fuel Development Corporation (PNC), the following are examined as part of an application technology using a high power electron linac : monochromatic gamma ray sources, free electron lasers, and intense positron sources. This report describes an adaptive estimate of a superconducting magnet in order to efficiently converge a positron beam for the development of an intense positron source. By comparing the intensity of a positron beam using a superconducting magnet with a normal conducting magnet, the intensity obtained was more than double. In addition, a small magnet was manufactured in order to examine the characteristics of the superconducting magnet as a solenoid coil. An excitement test was carried out with rated current. As a result of measuring the maximum magnetic field on the central axis, we achieved 5.6 Tesla, which was the designed value. Therefore, it was confirmed to function as a focusing device, when the superconducting magnet was used to converge the positron beam.

JAEA Reports

None

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

PNC TJ2164 97-004, 38 Pages, 1997/10

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

JAEA Reports

Performance evaluation on reactor power control by H$$^{infty}$$ controller with gain scaling

Ishikawa, Nobuyuki; Suzuki, Katsuo

JAERI-Research 97-038, 17 Pages, 1997/05

JAERI-Research-97-038.pdf:0.56MB

no abstracts in English

JAEA Reports

None

PNC TJ1612 97-001, 69 Pages, 1997/03

PNC-TJ1612-97-001.pdf:2.25MB

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 TJ1409 97-011, 25 Pages, 1997/03

PNC-TJ1409-97-011.pdf:0.59MB

None

JAEA Reports

Implementation of an MRACnn System on an FBR Building Block Type Simulator

Ugolini; Yoshikawa, Shinji; Ozawa, Kenji

PNC TN9410 95-253, 13 Pages, 1995/10

PNC-TN9410-95-253.pdf:0.5MB

This report presents the implementation of the a model reference adaptive control system based on the artificial neural network technique (MRAC$$_{nn}$$) in a fast breeder reactor (FBR) building block type (BBT) simulator representing the Monju prototype reactor. The purpose of this report is to improve the control of the outlet steam temperature of the three evaporators of the Monju prototype reactor. The connection between the MRAC$$_{nn}$$ system and the BBT simulator is achieved through an external shared memory accessible by both systems. The MRAC$$_{nn}$$ system calculates the demand for the position of the feedwater valve replacing the signal of a PID controller collocated inside the heat transport system model of the Monju prototype reactor. Two series of simulation tests havc been performed, one with one loop connected to the MRAC$$_{nn}$$ system (leaving the remaining two connected to the original PID controller), and the other with three loops connected to the MRAC$$_{nn}$$ system. In both simulation tests the MRAC$$_{nn}$$ system performed better than the PID controller, keeping the outlet steam temperature of the evaporators closer to the required set point value through all the transients.

JAEA Reports

None

Haga, Kazuo; ; ; ; Seino, Hiroshi; ;

PNC TN9420 92-013, 226 Pages, 1992/10

PNC-TN9420-92-013.pdf:9.04MB

None

JAEA Reports

None

; ; ; Tanabe, Hiromi; ; ;

PNC TN9080 92-006, 21 Pages, 1992/04

PNC-TN9080-92-006.pdf:0.76MB

None

JAEA Reports

A Study on the reliability of the FBR reactor shutdown system; Design study for the large scale FBR

PNC TN9410 91-286, 117 Pages, 1991/08

PNC-TN9410-91-286.pdf:9.35MB

A conventional type of RSS in a large scale FBR was designed and its unavailability was analyzed with fault-tree. Reliability of logic circuits of the reaetor protection system is relatively high when compared to that of the control rod insertion. Contributing factors to the unavailabity are multiple failures of detection systems, and failure to insert rods such as failure to deratch or rod jamming. Then the new concept of control rod release mechanism was introduced in the RSS design. The thermal-hydraulic characteristics of the mechanism was analyzed using computer codes SSC-L and AQUA. Further, qualitative analysis of the common cause failure for the RSS was tried with the generic cause approach. The reactor protection systems of the backup RSS are diversified by the self actuated control rod release mechanism. With such a mechanism, the number of common cause factors were decreased for postulated LOF event.

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC TN9360 91-002, 110 Pages, 1991/08

PNC-TN9360-91-002.pdf:4.67MB

no abstracts in English

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC TN9360 91-001, 83 Pages, 1991/01

PNC-TN9360-91-001.pdf:3.6MB

no abstracts in English

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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