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JAEA Reports

Maintenance of the auxiliary component cooling water system and the general cooling water system in HTTR

Kameyama, Yasuhiko; Watanabe, Shuji; Inoi, Hiroyuki; Shimizu, Yasunori; Aragaki, Etsushi; Shinozaki, Masayuki; Ota, Yukimaru

JAEA-Testing 2008-001, 63 Pages, 2008/03

JAEA-Testing-2008-001.pdf:20.97MB

The High Temperature Engineering Test Reactor (HTTR) has the Auxiliary Component Cooling Water System (ACCWS) and the General Cooling Water System (GCWS). ACCWS supplies the cooling water to the many facilities those are necessary to operate and cool the reactor. GCWS supplies the cooling water to the many facilities those are necessary to operate and cool the reactor in normal circumstances. Two kinds of the cooling water are cooled with the Cooling Tower. Each facility has the circulation pump, the cooling tower, the piping, the valve, the strainer and the injection system of the chemical solution. And these two facilities are operating all the year. This report describes maintenance items, improvements and management of the ACCWS and the GCWS.

JAEA Reports

Maintenance of gaseous radwaste treatment system in HTTR

Yamazaki, Kazunori; Kameyama, Yasuhiko; Inoi, Hiroyuki; Arakaki, Etsushi; Shinozaki, Masayuki; Ota, Yukimaru

JAEA-Testing 2008-002, 52 Pages, 2008/03

JAEA-Testing-2008-002.pdf:15.54MB

The High Temperature Engineering Test Reactor (HTTR) has the Gaseous Radwaste Treatment System (GRTS). This system appropriately collects all potentially radioactive gases discharged from the plant. After the gases are decayed with the Decay tank and decreased with the Filtering system, the gases are discharged into the atmosphere under monitoring. This system is maintained every year for keeping the performance. The maintenance is very important. Furthermore, the maintenance is profitable for designing a new High Temperature Gas cooled Reactor. This report describes the newly developed, maintenance items and improvements of the GRTS.

JAEA Reports

Examination of fabric of protective clothing suitable for sweltering radiation work; Influence on survey of contamination (MOX) in wet condition with sweat

Horikoshi, Yoshinori; Nemoto, Norio; Kurosawa, Shigeyuki*; Takasaki, Koji; Mizuniwa, Harumi

JAEA-Testing 2008-003, 29 Pages, 2008/04

JAEA-Testing-2008-003.pdf:1.65MB

In the Plutonium Fuel Technical Development Center, protective clothing suitable for sweltering radiation work was examined. Since it worried about the influence of wet protective clothing with sweat on detection of MOX powder contamination, Detection situations, the diffusion of contamination, and the osmosis and penetrability to wet protective clothing were examined about the present fabric and other new fabrics. As a result of examination, it was confirmed that the influence of detection on alpha ray in the wet condition of new fabrics was smaller than the current fabric. This report compiled the result of examination and points in the fabric selection suitable for protective clothing.

JAEA Reports

Replacement of radiation monitors in the lead cells of JMTR Hot Laboratory

Kato, Yoshiaki; Yamamoto, Toshio; Takada, Fumiki; Omi, Masao; Nakagawa, Tetsuya

JAEA-Testing 2008-004, 22 Pages, 2008/06

JAEA-Testing-2008-004.pdf:5.88MB

This report is concerned with replacement of the radiation monitors in the lead cells of JMTR Hot Laboratory in the 2007 fiscal year. It was carried out on two of seven systems of the radiation monitors. The designing, producing, installing, adjusting and inspecting were described.

JAEA Reports

Installation of remote-handling typed EBSD-OIM analyzer for heavy irradiated reactor materials

Kato, Yoshiaki; Miwa, Yukio; Takada, Fumiki; Omi, Masao; Nakagawa, Tetsuya

JAEA-Testing 2008-005, 48 Pages, 2008/06

JAEA-Testing-2008-005.pdf:13.36MB

This report is concerned with the EBSD-OIM analyzer for irradiated reactor materials, which was installed in the JMTR Hot Laboratory. As the first time in the world, it was installed in a hot cell as one of the examination facilities for irradiated nuclear materials and contributes to studies on IASCC (irradiation aided stress corrosion cracking) and IGSCC (irradiation grain boundary stress corrosion cracking). Its maintenance and operating experiences were described.

JAEA Reports

Application of measuring apparatus for non-condensable gas concentration to LSTF experiment

Kamiwaki, Tadayoshi; Owada, Akihiko; Takeda, Takeshi; Nakamura, Hideo

JAEA-Testing 2008-006, 77 Pages, 2008/07

JAEA-Testing-2008-006.pdf:6.32MB

Non-condensable gas for the pressurization of accumulator (ACC) tanks of emergency core cooling system may flow into the primary system during loss-of-coolant accidents (LOCAs) in a pressurized water reactor (PWR) after the ACC coolant injection is completed. Since the non-condensable gas may travel to and accumulates in steam generators (SGs) U-tubes, primary cooling and depressurization via SG secondary-side depressurization would become ineffective because of the degradation of condensation heat transfer in SG U-tubes. Since quantitative measurement of gas concentration is necessary to clarify the influences of non-condensable gas on the depressurization in ROSA/LSTF experiments that simulate PWR LOCAs and transients, an apparatus using a Zirconia oxygen sensor has been developed to directly measure the gas concentration in steam by introducing air as the non-condensable gas for the ACC pressurization. This apparatus is improved and applied to LSTF experiments where the gas concentration is measured directly in vessel upper head where gas may pass through with steam and in SG outlet plenum where gas accumulates. This report describes the improvement of the apparatus and the results of oxygen gas measurement characterization tests and the LSTF secondary-side depressurization experiments.

JAEA Reports

GEOMASS system

Oyama, Takuya; Saegusa, Hiromitsu

JAEA-Testing 2008-007, 248 Pages, 2009/03

JAEA-Testing-2008-007.pdf:44.09MB

As a part of the research and development regarding characterisation of deep geological environment, the GEOMASS (GEOlogical Modelling Analysis And Simulation Software) system has been developed by the Japan Atomic Energy Agency in order to carry out geological and hydrogeological modelling and groundwater flow simulation and so on. The GEOMASS system integrates a commercial geological interpretation system (Earth Vision$$^{tiny{textregistered}}$$), which is used for geological modelling and visualisation, with a proprietary code for groundwater flow (FracAffinity). This integrated system allows users to make rapid improvement of models as data increases. Also, it is possible to perform more realistic groundwater flow simulation due to the capability of modelling the rock mass as a continuum with discrete hydro-structural features in the rock. This paper consists of "Overview of GEOMASS system", "FracAffinity Theoretical Background" and "FracAffinity User Guide" and is edited as a GEOMASS system manual. "Overview of GEOMASS system" describes the outline of this system. "FracAffinity Theoretical Background" describes the information of technical background of FracAffinity software. "FracAffinity User Guide" describes the structure of the FracAffinity input files, the usage of FracAffinity Interface and flow-solver.

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