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Journal Articles

Implementation of resource information server for meta scheduling

Koide, Hiroshi; Yamagishi, Nobuhiro*; Takemiya, Hiroshi*; Hayashi, Takuya*; Kasahara, Hironori*

Keisan Kogaku Koenkai Rombunshu, p.357 - 360, 2000/05

no abstracts in English

JAEA Reports

TCMD Intranet system integration (Part 2)

Kon, Tetsuro

JNC-TN8440 2000-004, 93 Pages, 2000/03

JNC-TN8440-2000-004.pdf:3.7MB

TCMD (Tokai Construction Maintenance Division) Intranet System Integration has started in 1995. The first active activities between 1995 and 1996 has reported in a previous PNC report (PNC PN8440 97-032 TCMD Intranet System Integration Part 1). This is the second active activity's report between 1997 and 1999. Main content of this report is as follows. TCMD Intranet System Integration has completed by TCMD LAN system construction with high-speed LAN equipments and WINS services. TCMD group scheduler and conference rooms appointment system has developed by the operation of Exchange Server 5.5. The plant construction management data base system has developed ---ACCESS 97/SQL Server 6.5 version. The plant construction management data base system has also developed---Internet Explorer / Active Server Pages version. The formal TCMD homepage service has begun in l998.

JAEA Reports

Operation system concept for high-level radioactive wastes disposal facility

*; *; Tanai, Kenji

JNC-TN8400 99-050, 94 Pages, 1999/11

JNC-TN8400-99-050.pdf:3.86MB

This paper reports on the evaluations of operational activities for a High Level Radioactive Wastes Disposal Facility, from initial acceptance of vitrified waste at a surface facility to emplacement engineered barriers in underground facilities. The purpose of this analysis is to confirm the technical feasibility of geological disposal. First, the basic design and repository system requirements are identified. Second, operational activities in surface facilities, access facilities and underground facilities are described. The required procedures and equipment, suitable for specific emplacement concepts and configurations for engineered barrier systems are discussed for specific examples. Countermeasures for potential adverse events or conditions are based on extensive civil engineering and mining experiences in Japan and abroad. The time schedule is also evaluated on the basis of these concepts. In addition, the concept of stationary and mobile radiation control areas is studied based on experiences and practice in current nuclear facilities. Finally future research and development items are summarized.

JAEA Reports

Investigations on repository layouts

Tanai, Kenji; Iwasa, Kengo; Hasegawa, Hiroshi; Goke, Mitsuo*; Horita, Masakuni*; Noda, Masaru*

JNC-TN8400 99-044, 140 Pages, 1999/11

JNC-TN8400-99-044.pdf:7.85MB

This report consists of three items: (1)Study of the repository configuration, (2)Study of the surface facilities configuration for construction, operation and buckfilling, (3)Planning schedule, In the repository configuration, the basic factors influencing the design of the repository configuration are presented, and the results of studies of various possible repository configurations are presented for both hard and soft rock systems. Here, the minimum conditions regarding geological environment required to guide design are assumed, because it is difficult to determine the repository configuration without considering specific conditions of a disposal site. In the surface facility configuration, it is illustrated based on the results of construction, operation, buckfilling studies for underground disposal facility and EIS report of CANADA. In the schedule, the overall schedule corresponding to the repository layout is outlined in link with the milestone of disposal schedule set forth in the government's basic policy. The assumptions and the basic conditions are summarized to examine the General Schedule from start of construction to closure of a repository. This summaly is based on the technologies to be used for construction, operation and closure of a repository. The basic national policies form the framework for this review of the general schedule.

JAEA Reports

Backfilling of the underground facilities on a disposal site

Sugita, Yutaka; Fujita, Tomo; Tanai, Kenji; Hasegawa, Hiroshi; Furuichi, Mitsuaki*; Okutsu, Kazuo*; Miura, K.*

JNC-TN8400 99-039, 58 Pages, 1999/11

JNC-TN8400-99-039.pdf:3.19MB

Regarding disposal techniques of high-level radioactive waste (HLW), the HLW is vitrified and then stored for cooling for a period of 30 to 50 years. After cooling, the HLW is isolated in the deep underground. The concept of geological disposal is based on the requirement to enclose the HLW in the deep underground for the long-term durability of the human's environmental safety. Backfilling of a repository is a unique activity on the geological disposal. If underground tunnels excavated to construct the repository are left, they may have significant influences on the barrier performance of an entire repository, such as: the mechanical stability of a tunnel may be damaged by rock stresses and a tunnel may provide a fast pathway for ground water flow. Therefore, the underground facilities are expected to be backfilled with a backfilling material after emplacement of the HLW and a buffer material. The material for the backfilling of the underground facilities is backfilling material. In this report, bentonite-aggregate mixture is considered, as one of the candidate materials for the backfilling material. Aggregate imitates the muck that is generated during construction phase of the underground facilities. The combination of backfilling, plugging and grouting is considered in some underground situations. Plug is composed of concrete material or clay-based one. Grouting material is concrete material or clay-based one, too. In this report, the concept of the backfilling, mechanical and hydrological characteristics of the bentonite-aggregate mixture, the function, work methods and a schedule of the backfilling materials, plugging and grouting are considered, and items of quality control for the bentonite-aggregate mixture, concrete material and grouting are listed.

JAEA Reports

None

; ; Shimizu, Kazuhiko; Miyahara, Kaname; ; Hasegawa, Hiroshi; Iwasa, Kengo

JNC-TN1400 99-008, 656 Pages, 1999/04

JNC-TN1400-99-008.pdf:34.68MB

None

JAEA Reports

None

JNC-TN6450 99-001, 39 Pages, 1999/01

JNC-TN6450-99-001.pdf:1.85MB

JAEA Reports

Process condition monitoring at FUGEN

Lund

PNC-TN3410 98-001, 14 Pages, 1998/01

PNC-TN3410-98-001.pdf:3.07MB

At the FUGEN Power Station a system for online monitoring of selected process component behavior, CONFU (CONdition monitoring at FUgen) has been implemented. This system is based on MOCOM (Model Based Condition Monitoring System), developed at IFE/OECD Halden Reactor Project. The system is currently monitoring the heat exchangers for the Reactor Auxiliary Cooling Water System. These heat exchangers has shown a slowly degrading performance over time due to fouling, i.e. accumulation of a heat resisting layer of organic material on the sea water side. This slow degradation, which is not detected by the conventional control and alarm systems, is not an operational, but rather a maintenance problem. CONFU is using dynamically updated mathematical models to compute the performance degradation of the heat exchangers, expressed in overall heat transfer, heat transfer coefficients or heat exchanger efficiency. The results of testing CONFU on real plant data identify the expected degradation trends. The data from CONFU can, in addition to give the plant operator a good impression of the component's operational state, be utilized by the maintenance planning personnel for determination of the most optimal maintenance schedule. Furthermore, the process models in CONFU have been used for simulation purposes.

JAEA Reports

None

PNC-TN1100 98-002, 208 Pages, 1997/12

PNC-TN1100-98-002.pdf:6.97MB

no abstracts in English

JAEA Reports

None

; ; ; ; ; ;

PNC-TN9080 92-009, 24 Pages, 1992/04

PNC-TN9080-92-009.pdf:0.94MB

None

JAEA Reports

None

; ; ; ; ; ;

PNC-TN9080 92-008, 52 Pages, 1992/04

PNC-TN9080-92-008.pdf:1.72MB

None

Oral presentation

Decommissioning of Tokai Reprocessing Plant (TRP), 2; Approach to the decommissioning schedule

Akiyama, Kazuki; Taguchi, Katsuya; Nagasato, Yoshihiko

no journal, , 

Tokai Reprocessing Plant is the chemical plant having approximately 30 facilities. Moreover TRP has the particularity that must start the decommissioning while treating radioactive waste. Especially it is important to vitrify high radioactive waste. JAEA worked out the decommissioning schedule for TRP having these particularities. In this presentation, the basic thought of 70-years-schedule is described.

Oral presentation

Current status of JRR-3 and the expected schedule until the operation restarts

Matsue, Hideaki; Osakabe, Toyotaka; Abe, Kazuhide

no journal, , 

no abstracts in English

Oral presentation

Optimal scheduling of inspection process for fast reactor via integer programming

Suzuki, Masaaki*; Ito, Mari*; Hashidate, Ryuta; Takahashi, Keita; Yada, Hiroki; Takaya, Shigeru

no journal, , 

14 (Records 1-14 displayed on this page)
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