Refine your search:     
Report No.
 - 
Search Results: Records 1-11 displayed on this page of 11
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Mock-up test of the modified STACY (Performance check of water feed and drain system)

Seki, Masakazu; Maekawa, Tomoyuki; Izawa, Kazuhiko; Sono, Hiroki

JAEA-Technology 2017-038, 52 Pages, 2018/03

JAEA-Technology-2017-038.pdf:4.6MB

The Japan Atomic Energy Agency is conducting a reactor modification project of the Static Experiment Critical Facility (STACY). In the modification, STACY is to be converted from a thermal reactor using solution fuel into that using fuel rods and light water moderator. Reactivity of the modified STACY core is controlled by the water level fed in the core tank as well as the present STACY. In order to verify the basic design of the water feed and drain system of the modified STACY, we constructed a mockup test apparatus with almost the same structure and specifications as the modified STACY. In the mockup test, performance checks were pursued regarding limitation of maximum flow of water feeding, adjustment of the flow rate of water feeding, stop of water feeding and others. This report describes the outline and results of the mock-up test of the water feed and drain system of the modified STACY.

Journal Articles

Contributions to the decommissioning of Fukushima Daiichi Nuclear Power Station by JAEA Naraha Remote Technology Development Center

Daido, Hiroyuki; Kawatsuma, Shinji; Kojima, Hisayuki; Ishihara, Masahiro; Nakayama, Shinichi

Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet), 8 Pages, 2017/00

JAEA Reports

Annual report on experimental operation of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system in 2001 fiscal year (Contract research)

Hayashi, Koji; Inagaki, Yoshiyuki; Kato, Michio; Fujisaki, Katsuo*; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.

JAERI-Tech 2005-032, 46 Pages, 2005/06

JAERI-Tech-2005-032.pdf:4.79MB

This is annual report on the experimental operation of the mock-up test facility with a full-scale reaction tube for the HTTR hydrogen production system in 2001 fiscal year. The first experimental operation was performed during two weeks from March 1, 2002 to March 13, 2002 to test on the thermal hydraulic performance of the steam reformer and also to train the operators. The thermal hydraulic performance test of the steam reformer was performed to evaluate the heat transfer characteristics between helium gas and process gas in the steam reformer. This report is summarized with an overview of the test, the results and its operation records.

JAEA Reports

Verification of HTTR hydrogen production system analysis code using experimental data of mock-up model test facility with a full-scale reaction tube; Cooling system of the secondary helium gas using steam generator and radiator (Contract research)

Sato, Hiroyuki; Ohashi, Hirofumi; Inaba, Yoshitomo; Maeda, Yukimasa; Takeda, Tetsuaki; Nishihara, Tetsuo; Inagaki, Yoshiyuki

JAERI-Tech 2005-014, 89 Pages, 2005/03

JAERI-Tech-2005-014.pdf:7.25MB

In a hydrogen production system using HTTR, it is required to control a secondary helium gas temperature within an allowable value at an intermediate heat exchanger (IHX) inlet to prevent a reactor scram. To mitigate thermal disturbance of the secondary helium gas caused by the hydrogen production system, a cooling system of the secondary helium gas using a steam generator(SG) and a radiator will be installed at the downstream of the chemical reactor. In order to verify a numerical analysis code of the cooling system, numerical analysis has been conducted. The pressure controllability in SG is highly affected by the heat transfer characteristics of air which flows outside of the heat exchanger tube of the radiator. In order to verify a numerical analysis code of the cooling system, the heat transfer characteristics of air has been investigated with experimental results of a mock-up model test. It was confirmed that numerical analysis results were agreed well with experimental results, and the analysis code was successfully verified.

Journal Articles

Development of ITER divertor vertical target with annular flow concept, 2; Development of brazing technique for CFC/CuCrZr joint and heating test of large-scale mock-up

Ezato, Koichiro; Dairaku, Masayuki; Taniguchi, Masaki; Sato, Kazuyoshi; Suzuki, Satoshi; Akiba, Masato; Ibbott, C.*; Tivey, R.*

Fusion Science and Technology, 46(4), p.530 - 540, 2004/12

 Times Cited Count:14 Percentile:68.23(Nuclear Science & Technology)

The first fabrication and heating test of a large-scale CFC monoblock divertor mock-up using annular flow concept have been performed to demonstrate its manufacturability and thermo-mechanical performance. Prior to the fabrication of the mock-up, brazed joint tests between the CFC monoblock and the CuCrZr tube have been carried out to find the suitable heat treatment mitigating loss of the high mechanical strength of the CuCrZr material. Basic mechanical examination on CuCrZr undergoing the brazing heat treatment and FEM analyses are also performed to support the design of the mock-up. High heat flux tests on the large-scale divertor mock-up have been performed in an ion beam facility. The mock-up has successfully withstood more than 1,000 thermal cycles of $$rm 20 MW/m^2$$ for 15 s and 3,000 cycles more than $$rm 10 MW/m^2$$ for 15 s, which simulates the heat load condition of the ITER divertor. No degradation of the thermal performance of the mock-up has been observed throughout the thermal cycle test.

Journal Articles

Performance test results of mock-up test facility of HTTR hydrogen production system

Ohashi, Hirofumi; Inaba, Yoshitomo; Nishihara, Tetsuo; Inagaki, Yoshiyuki; Takeda, Tetsuaki; Hayashi, Koji; Katanishi, Shoji; Takada, Shoji; Ogawa, Masuro; Shiozawa, Shusaku

Journal of Nuclear Science and Technology, 41(3), p.385 - 392, 2004/03

 Times Cited Count:16 Percentile:70.63(Nuclear Science & Technology)

Prior to construction of a HTTR hydrogen production system, a mock-up test facility was constructed to investigate transient behavior of the hydrogen production system and to establish system controllability. The Mock-up test facility with a full-scale reaction tube is an approximately 1/30 scale model of the HTTR hydrogen production system and an electric heater is used as a heat source instead of a reactor. Before the mock-up test, a performance test of the test facility was carried out in the same pressure and temperature conditions as those of the HTTR hydrogen production system to investigate its performance such as hydrogen production ability, controllability and so on. It was confirmed that hydrogen was stably produced with a hot helium gas about 120Nm$$^{3}$$/h which satisfy the design value and thermal disturbance of helium gas during the start-up could be mitigated within the design value by using a steam generator.

JAEA Reports

Catalytic activity of catalysts for steam reforming reaction (Contract research)

Ohashi, Hirofumi; Inagaki, Yoshiyuki

JAERI-Tech 2003-046, 47 Pages, 2003/05

JAERI-Tech-2003-046.pdf:3.15MB

no abstracts in English

JAEA Reports

Performance test results of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system (Contract research)

Inagaki, Yoshiyuki; Hayashi, Koji; Kato, Michio; Fujisaki, Katsuo; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.

JAERI-Tech 2003-034, 129 Pages, 2003/05

JAERI-Tech-2003-034.pdf:7.62MB

no abstracts in English

Journal Articles

Mock-up test of remote controlled dismantling apparatus for large-sized vessels

Kimura, Masanori; Myodo, Masato; Okane, Shogo; Miyajima, Kazutoshi

Proceeding of International Waste Management Symposium 2002 (WM '02) (CD-ROM), 14 Pages, 2002/00

no abstracts in English

JAEA Reports

Inspection of heat transfer tubes after mock-up tests of minituarized apparatus for the acid recovery evaporator (Contract research)

Hamada, Shozo; Fukaya, Kiyoshi*; Kato, Chiaki; Yanagihara, Takao; Doi, Masamitsu*; Kiuchi, Kiyoshi

JAERI-Tech 2001-063, 49 Pages, 2001/10

JAERI-Tech-2001-063.pdf:13.39MB

The demonstration test for the acid recovery evaporator and the dissolver used in the major equipment of Rokkasho Reprocessing Plant (RRP), has been carried out. The mock-up miniature equipment has been employed to it. This test had been performed from April in 1998. The total time of demonstration test using the mock-up equipment is about two and half years, which corresponds to about 20,000 hours. After that, four of the seven heat transfer tubes used in the evaporator were drawn out and the corrosion level and the mechanical properties were evaluated for one of them. As a result, intergranular corrosion was recognized in the inner surface of the heat transfer tube and the corrosion depth at the grain boundary was statistically shown to be about one grain from the inner surface. Further, no change in mechanical properties was observed and growth of intergranular cracks in the inner surface of the specimen was found after flattering test.

Journal Articles

Advance in the water jet cutting technology for nuclear reactor decommissioning in JAERI

; ; Yahiro, Teruo*

2nd Pacific RIM Int. Conf. on Water JET Cutting, 11 Pages, 1989/00

no abstracts in English

11 (Records 1-11 displayed on this page)
  • 1