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JAEA Reports

Test methods for robots for nuclear emergency response and decommissioning; Tests for running performances of robots (JAEA-TM-0001, JAEA-TM-0002 and JAEA-TM-0003)

Kawabata, Kuniaki; Yamada, Taichi; Abe, Hiroyuki*

JAEA-Technology 2020-015, 37 Pages, 2020/11

JAEA-Technology-2020-015.pdf:3.81MB

This report describes the test procedures for evaluating running performances of remotely operated robot utilized for nuclear emergency responses and decommissioning. After the accident at Fukushima Daiichi Nuclear Power Station of the Tokyo Electric Power Company Holdings Inc. (FDNPS) occurred, remotely operated robots have been deployed and utilized in the response tasks. Such post-accident work experience and lessons learned are very valuable for developing the robots in the future. Therefore, we were motivated to develop the test methods for performance evaluation of the robot by referring with such experiences and lessons. Based on our examinations, in order to execute the response and decommissioning tasks, the robots are required to run through the space without enough margin and avoiding collisions, to move on stairs while avoiding tumbling or falling down and to drag a cable while avoiding problems caused by the cable entwining around objects. This report describes three test procedures for quantitatively evaluating the performances which are for running narrow passage, climbing up/down on the stairs and running with dragging the cable. Typical course layout and the demonstration of test running are also illustrated for the references.

Journal Articles

Naraha Remote Technology Development Center and robots for nuclear disaster

Kawatsuma, Shinji

Dekomisshoningu Giho, (54), p.24 - 33, 2016/09

It has passed more than five years than Tokyo Electric Power Company's Fukushima Daiichi NPPs accidents occurred by huge tsunamis caused by the earthquake in Pacific Ocean Coast of North East District on March 11, 2011. It is very hard for workers to enter and stay for long time to work for decommissioning, because the radiation dose rate in the reactor buildings is too high to extremely high caused by radioactive materials released. Then the Naraha Remote Development Center has been constructed and taken into full operation in April 2016, which center would accelerate the development of remote technologies conducting decommissioning on the behalf of workers. The center is developing robot simulator system and robot performance testing method which could support developing remote operating equipment and devices. Also the center is preparing and operating remote equipment and devices for nuclear emergency response.

JAEA Reports

Performance test of ex-core high temperature and high pressure water loop test equipment (Contract research)

Nakano, Hiroko; Uehara, Toshiaki; Takeuchi, Tomoaki; Shibata, Hiroshi; Nakamura, Jinichi; Matsui, Yoshinori; Tsuchiya, Kunihiko

JAEA-Technology 2015-049, 61 Pages, 2016/03

JAEA-Technology-2015-049.pdf:14.7MB

In Japan Atomic Energy Agency, we started a research and development so as to monitor the Nuclear Plant Facilities situations during a severe accident, such as a radiation-resistant monitoring camera under a severe accident, a radiation resistant in-water transmission system for conveying the information in-core and a heat-resistant signal cable. As part of advance in a heat-resistant signal cable, we maintained to ex-core high-temperature and pressure water loop test equipment which can be simulated conditions of BWRs and PWRs for evaluation reliability and property of construction sheath materials. This equipment consists of Autoclave, water conditioning tank, water pump, high-pressure metering pump, preheater, heat exchanger and pure water purification equipment. This report describes the basic design and the results of performance tests of construction machinery and tools of ex-core high-temperature and pressure water loop test equipment.

JAEA Reports

Development of an on-site plant analyzer (1); Development of a GUI for building plant models for analyzes and retrieval of real-time plant data

JNC-TN4400 2000-002, 33 Pages, 2000/06

JNC-TN4400-2000-002.pdf:5.22MB

An on-site plant analyzer can provide analysis support in evaluating plant dynamic characteristics when unplanned events occur in a nuclear power station. The plant analyzer contains a plant-dynamics analysis code, which efficiently and quickly analyzes the plant dynamic characteristics. Elements being developed for the on-site plant analyzer include utilities to build plant models for performing analyses and to retrieve plant operation data. The addition of these elements to the analysis code supports the plant-dynamics analysis works in MONJU, in particular, to assist the analyses of start up tests. The system contains the FBR plant-dynamics analysis code "Super-COPD", which is based on the "COPD" code that was used in the safety licensing of MONJU. One feature of the system is that all operations, e.g., assembling plant models for analysis, are prepared using a GUI (Graphical user Interface). In addition to this feature, the system is able to retrieve directly on- and off-line plant data from MIDAS, the Monju Integrated Data Acquisition System. These plant data are used to supply time-dependent boundary conditions for the plant analysis models. For this report, two case studies were performed. First, the analysis result of a turbine trip test at 40% power operation using the full plant model is described. For the second, performance of the IHX model was evaluated using retrieved plant data for boundary conditions. With the development of this system, improvement in the efficiency of analyses of MONJU start-up tests is expected.

JAEA Reports

Development of the high current electron accelerator

; Toyama, Shinichi; ; ; Yamazaki, Yoshio; ; Omura, Akiko

JNC-TN9410 2000-007, 376 Pages, 2000/03

JNC-TN9410-2000-007.pdf:15.51MB

According to the Long-Term Program for Partitioning and Transmutation which was published by the Atomic Energy Commission in 1988, study on the transmutation using an electron accelerator, which was a part of the program, has been carried out in the O-arai Engineering Center. It is the study on converting radioactive fission products for example Strontium and Cesium to stable nuclides by photonuclear reaction caused by high energy gamma-ray made by an electron accelerator. It was thought that a 100mA-100MeV (10MW output power) accelerator would be needed in order to carry out the transmutation study in engineering phase. Therefore, development of the High-Current Electron Accelerator whose target had been 20mA-10MeV (200 kW output power) accelerator was carried out as development of elemental technologies on beam stabilization. The conceptual design of the accelerator was started in 1989. In March 1997, the main facility of this accelerator was completed. The test operation was carried out to confiim the performance of the accelerator from January, 1999 to December. As the result, an output of about 14 kW was achieved. In addition, the electron beam of 40 kW could be to accelerate in short time. In this report, the design, fabrication and evalution of performance of the facilities are presented.

JAEA Reports

Development of a standard database for FBR core nuclear design (XI); Analysis of the experimental fast reactor "JOYO" MK-I start up test and oparation data

; Numata, Kazuyuki*

JNC-TN9400 2000-036, 138 Pages, 2000/03

JNC-TN9400-2000-036.pdf:10.16MB

Japan Nuclear Cycle Development lnstitute (JNC) had developed the adjusted nuclear cross-section library in which the results of the JUPITER experiments were renected. Using this adjusted library, the distinct improvement of the accuracy in nuclear design of FBR cores had been achieved. As a recent research, JNC develops a database of other integral data in addition to the JUPITER experiments, aiming at further improvement for accuracy and reliability. ln this report, the authors describe the evaluation of the C/E values and the sensitivity analysis for the Experimental Fast Reactor "JOYO" MK-l core. The minimal criticality, sodium void reactivity worth, fuel assembly worth and burn-up coefficient were analyzed. The results of both the minimal criticality and the fuel assembly worth, which were calculated by the standard analytical method for JUPITER experiments, agreed well with the measured values. 0n the other hand, the results of the sodium void reactivity worth have a tendency to overestimate. As for the burn-up coefficient, it was seen that the C/E values had a dispersion among the operation cycles. The authors judged that further investigation for the estimation of the experimental error will increase the applicability of the integral data to the adjusted library. Furthermore, sensitivity analyses for the minimal criticality, sodium void reactivity worth and fuel assembly worth showed the characteristics of "JOYO" MK-l core in comparison with ZPPR-9 core of JUPITER experiments.

JAEA Reports

None

*

JNC-TJ7400 2000-005, 20 Pages, 2000/02

JNC-TJ7400-2000-005.pdf:1.44MB

no abstracts in English

JAEA Reports

Hydrogen and tritium behaviour in Monju; Validation of an analysis code for tritium transport in fast reactor system, TTT, and estimation for Monju full power operation in future

;

JNC-TN4400 99-002, 192 Pages, 1999/03

JNC-TN4400-99-002.pdf:7.27MB

The tritium transport analysis code, TTT, has been validated using data from the low power test of Monju, and then its behaviour at along term full power operation of Monju in future has been estimated, when the estimated transport and distribution of tritium in the reactor system has been also compared with the result in Joyo and Phenix, which had been already experienced long term operations. The TTT code had been develpped using the tiritium and hydrogen transport model proposed by R. Kumar, ANL, and had been applied to the evaluation in Monju design work. After then, futhermore, the code has been improved using the data from long term operation of Joyo with MK-II core, and in this work the code has been validated for the first time for Monju data. The results from this work are as follows; (1)Comparison of the best fitted tritium source rates from cores in Joyo, Phenix and Monju makes an estimation of the major source from control rods, (2)The calculated tritium concentration in each medium for cooling and its change is a reasonable agreement to the measured, C/E=1.1, (3)The cover gas transport model cosidering isotopic exchange of H and H$$^{3}$$ can reproduce reasonably the measured concentration distirbution of tritium in sodium and cover gas, (4)The tritium concentration in secondary sodium of Monju was about l/50 times as much as the primary one, which shows the acceraration effect on cold tarapping of tritium due to coprecipitation with permeated hydrogen through Evaporater (EV) heat conduction tube walls. The tritium cold trapping efficiency was estimated to be 1 for coprecipitation with hydrogen and 0.3 for isotopic exchange, respectively, (5)Tritium transport and distribution for along term full power operation of Monju in future was estimated, which could involve a excess factor to 4 at the maximum. The tritium concentration in sodium and Steam Generator (SG) water will be substantially saturated after somthing like 10 years full power operation, ...

JAEA Reports

None

*; *; *; *

JNC-TJ7440 99-001, 151 Pages, 1999/01

JNC-TJ7440-99-001.pdf:10.35MB

no abstracts in English

JAEA Reports

None

Hirata, Yoichi*; *

PNC-TJ7439 98-003, 171 Pages, 1998/08

PNC-TJ7439-98-003.pdf:15.85MB

None

JAEA Reports

None

*; Toida, Masaru*; Shiogama, Yukihiro*; *; *; Fukazawa, E.*; Tanaka, M.*

PNC-TJ1100 98-004, 88 Pages, 1998/02

PNC-TJ1100-98-004.pdf:2.23MB

None

JAEA Reports

None

*; Toida, Masaru*; Shiogama, Yukihiro*; *; *; Fukazawa, E.*; Tanaka, M.*

PNC-TJ1100 98-003, 204 Pages, 1998/02

PNC-TJ1100-98-003.pdf:5.88MB

None

Journal Articles

Development of superconducting cavities for high intensity proton accelerator at JAERI

Ouchi, Nobuo; Kusano, Joichi; Akaoka, Nobuo*; Takeuchi, Suehiro; Hasegawa, Kazuo; Mizumoto, Motoharu; Inoue, Hitoshi*; *; Noguchi, Shuichi*; *; et al.

Development of Large Scale Superconducting Radio Frequency (SRF) Technologies, p.50 - 55, 1998/00

no abstracts in English

Journal Articles

Application of a Phoswich detector for simultaneous counting of $$alpha$$- and $$beta$$($$gamma$$)-rays in a rotating drum-cell type monitor

Usuda, Shigekazu; Yasuda, Kenichiro; Sakurai, Satoshi; Takahashi, Toshiyuki; Gunji, Hideho*; P.Howarth*

INMM 39th Annual Meeting Proceedings (CD-ROM), 27, 6 Pages, 1998/00

no abstracts in English

Journal Articles

Improvement of a rotating drum-cell type alpha monitor and its performance test

Usuda, Shigekazu; Yasuda, Kenichiro; Sakurai, Satoshi; Takahashi, Toshiyuki; Gunji, Hideho*

Dai-18-Kai Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Nenji Taikai Hobunshu, p.142 - 148, 1997/11

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ7439 96-005, 83 Pages, 1996/12

PNC-TJ7439-96-005.pdf:1.52MB

no abstracts in English

JAEA Reports

Operation and maintenance experience on the fuel handling systems and storage facilities of "MONJU", 1

; ; ; ; ; ; Kaito, Yasuaki; ; Kotaka, Yoshinori; ; et al.

PNC-TN2410 96-005, 339 Pages, 1996/03

PNC-TN2410-96-005.pdf:14.53MB

Construction of the 'Monju' fuel handling systems was completed in April, 1992. From March 1991 to August 1992, pre-commissioning tests were carried out. In December 1992, all the systems of Monju were transfered to PNC, and commissioning tests and reactor physics tests, were started. For the first time, during these physics tests, the fuel handling systems were operated for one of the commissioning tests 'Loading to Criticality', without significant problems. 168 fuel sub-assemblies were loaded into the core and the first criticality was achieved on 5th April 1994. The fuel handling systems continued in operation for the 'Loading to Full Size of the Core', power distribution test and for cleaning discharged dummy sub-assemblies. To keep these fuel handling systems working somothly and satisfactorily annual maintenance has been carried out since 1992. This paper describes the operation and maintenance experience of fuel handling systems after the pre-commissioning tests and future study items for system reliability improvement.

JAEA Reports

None

Kanno, Takeshi; Fujita, Tomoo; Sugita, Yutaka

PNC-TN8410 95-179, 19 Pages, 1995/05

PNC-TN8410-95-179.pdf:0.67MB

None

JAEA Reports

None

;

PNC-TN2410 95-035, 53 Pages, 1995/05

PNC-TN2410-95-035.pdf:4.98MB

None

JAEA Reports

None

*; *; *

PNC-TJ2678 95-007, 134 Pages, 1995/03

PNC-TJ2678-95-007.pdf:4.2MB

None

40 (Records 1-20 displayed on this page)