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JAEA Reports

Application of Cherenkov light observation to reactor measurements, 3; Evaluation of spent fuel elements of LWRs with Cherenkov light estimation system

Yamamoto, Keiichi; Takeuchi, Tomoaki; Hayashi, Takayasu*; Kosuge, Fumiaki*; Tsuchiya, Kunihiko

JAEA-Testing 2016-002, 25 Pages, 2016/11

JAEA-Testing-2016-002.pdf:4.97MB

Development of the reactor measurement system has been carried out to obtain the real-time in-core nuclear and thermal information, where the quantitative measurement of brightness of Cherenkov light was investigated. The system would be applied as a monitoring system in severe accidents and for the advanced operation management technology in existing LWRs. This report summarized the modification of Cherenkov light estimation system described JAEA-Testing 2015-001 and the result of the burn-up evaluation by Cherenkov light image emitted from spent fuel elements of LWRs with the modified system.

JAEA Reports

Application of Cherenkov light observation to reactor measurements, 2; Design and trial fabrication of Cherenkov light estimation system

Yamamoto, Keiichi; Takeuchi, Tomoaki; Hayashi, Takayasu*; Kosuge, Fumiaki*; Sano, Tadafumi*; Tsuchiya, Kunihiko

JAEA-Testing 2015-001, 25 Pages, 2015/11

JAEA-Testing-2015-001.pdf:3.52MB

Development of the reactor measurement system was started to obtain the real-time in-core nuclear and thermal information, where the quantitative measurement of brightness of Cherenkov light was investigated. This report was summarized the results of design and trial fabrication of the Cherenkov light estimation system from thermal power evaluation from Cherenkov light image emitted from the fuel elements. The developed Cherenkov light estimation system was verified with the Cherenkov light image emitted from the fuels in the core of Kyoto University Research Reactor (KUR). From the results, it is necessary to improve the observation method of Cherenkov light in the reactor and the evaluation method of the brightness of Cherenkov light. In future, the system will be applied for the evaluation of burn-up of spent fuels from the Cherenkov light emitted from the spent fuel assemblies in LWRs.

JAEA Reports

Application of Cherenkov light observation to reactor measurements, 1; Estimation of reactor power from Cherenkov light intensity

Yamamoto, Keiichi; Takeuchi, Tomoaki; Sano, Tadafumi*; Homma, Ryohei*; Kimura, Nobuaki; Otsuka, Noriaki; Kosuge, Fumiaki*; Nakajima, Ken*; Tsuchiya, Kunihiko

JAEA-Technology 2014-028, 56 Pages, 2015/01

JAEA-Technology-2014-028.pdf:9.23MB

Development of the reactor measurement system was started to obtain real-time in-core nuclear and thermal information, where the quantity measurement of brightness of Cherenkov light was applied. The system would be applied as monitoring system in severe accidents and for advanced operation management technology in existing LWRs. In this report, the calculation and the observation results were summarized about the quantity of the Cherenkov light caused by the $$gamma$$ and $$beta$$ ray emitted from the fuels in the core of Kyoto University Research Reactor.

Journal Articles

Measurement of neutron flux in the AVR

; ; ; ; H.Brixy*; J.Oehmen*; R.Hecker*; H.-J.Hantke*

Juel-2467, 43 Pages, 1991/04

no abstracts in English

Journal Articles

Demonstration tests of the high temperature wide range neutron monitoring system in the AVR

; ; ; ; J.Oehmen*; H.Brixy*; R.Hecker*

Juel-2468, 40 Pages, 1991/04

no abstracts in English

Journal Articles

Magunetic sensors for nuclear reactors

MAG-82-165, p.83 - 92, 1982/00

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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