Refine your search:     
Report No.
 - 
Search Results: Records 1-12 displayed on this page of 12
  • 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

Plan and reports of coupled irradiation (JRR-3 and JOYO of research reactors) and hot facilities work (WASTEF, JMTR-HL, MMF and FMF); R&D project on irradiation damage management technology for structural materials of long-life nuclear plant

Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.

JAEA-Technology 2009-072, 144 Pages, 2010/03

JAEA-Technology-2009-072.pdf:45.01MB

"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.

Journal Articles

Application of systems engineering to decommissioning of nuclear fuel cycle facilities

Sugitsue, Noritake; Tanaka, Yoshio; Tokizawa, Takayuki; Annen, Sotonori; Yonekawa, Shigeru; Nakakura, Hiroyuki*; Tokuyasu, Takashi*; Aritomi, Tadahiko*

Dekomisshoningu Giho, (30), p.53 - 66, 2004/09

In the Ningyo-Toge Environmental Engineering Center, we clarify a relation of all works about the decommissioning. And, as an information base to plan promotion of efficiency of a work, we develop the Decommissioning Engineering System. The Decommissioning Engineering System consists of the function to do work support of a decommissioning, the function to gather the results information the decommissioning technology and the general evaluation function of the decommissioning plan on the basis of facilities information collected by three-dimensional CAD. The decommissioning of the nuclear fuel cycle facility has the characteristics that a period from the plan to the decommissioning is long in comparison with the general chemical plant. And the peculiarity to handle radioactive waste is a reason. In addition the System Decontamination, Dismantling, Treatment and Waste disposal are each other influence it closely in the decommissioning process. Therefore as for the decommissioning process, system engineering is important.

Journal Articles

None

Saikuru Kiko Giho, (5), p.15 - 20, 1999/12

None

JAEA Reports

None

; ; ; ;

PNC TN6700 98-006, 106 Pages, 1998/04

PNC-TN6700-98-006.pdf:2.27MB

no abstracts in English

JAEA Reports

None

; ;

PNC TN6700 98-005, 54 Pages, 1998/04

PNC-TN6700-98-005.pdf:1.07MB

no abstracts in English

Journal Articles

History and current status of development of gas centrifuge Uranium enrichment technology at Ningyo

6th Workshop on separation phenomena(SPLG'98), 0 Pages, 1998/00

None

JAEA Reports

None

; ;

PNC TN6700 98-001, 10 Pages, 1996/09

PNC-TN6700-98-001.pdf:0.2MB

None

Journal Articles

None

Donen Giho, (92), p.88 - 92, 1994/12

None

JAEA Reports

Development of control rod guide system of Joyo

; Kawai, Masashi; ; ; ; Okubo, Toshiyuki;

PNC TN9410 94-094, 69 Pages, 1994/03

PNC-TN9410-94-094.pdf:1.7MB

As the final step of development of a control rod guide system (rod guider), it has been conducted to display information concerning the rod guider operation and the current plant conditions on a CRT in Japanese, to tell information for operators and to predict more accurately the stroke of each control rod to be driven at a reactor power adjustment operation since 1992, in oder to improve a function of man-machine interface of the rod guider. The development of the rod guider was completed with the following good results as expected. (1)The function of man-machine interface of the rod guider was improved to display information on a CRT in Japanese. (2)The voice guidance contributed to obtain higher operational reliability and to lower the load on the operators. (3)The rod guider provided the same function as operation manuals of Joyo because all operation procedures in the manuals were inputted into the rod guider. And the timely operation guides provided by the rod guider evabled non-skilled operators to control the reactor in the same manner as the experienced ones. (4)The difference of the predicted and actual rod stroke to be driven at the reactor power adjustment operation was reduced to less than $$pm$$0.2mm by both the existing inverse multiplication method and the experiences gained in the past five reactor power adjustment operations.

Journal Articles

None

; ; Suto, O.;

Nihon Genshiryoku Gakkai-Shi, 35(11), 967 Pages, 1993/11

JAEA Reports

None

; ; ;

PNC TN1420 93-009, 16 Pages, 1993/07

PNC-TN1420-93-009.pdf:0.31MB

no abstracts in English

Journal Articles

None

Nihon Genshiryoku Gakkai-Shi, , 

None

12 (Records 1-12 displayed on this page)
  • 1