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.

User's manual of a support systems for human reliability analysis; JASPAHR version 1.5

Yokobayashi, Masao; Kinoshita, Naoki*; Tamura, Kazuo*

JAERI-Data/Code 2000-015, p.102 - 0, 2000/03

JAERI-Data-Code-2000-015.pdf:13.92MB

no abstracts in English

Conceptual design of operator support system under seismic conditions

Oikawa, Tetsukuni; Muramatsu, Ken; Kasahara, Takeo*; Kawamata, Kazuhiko*; Morota, Hidetsugu*

Proceedings of 5th International Conference on Probabilistic Safety Assessment and Management (PSAM-5), p.2119 - 2125, 2000/00

no abstracts in English

Burn-up reactivity measurements of the Joyo MK-II core

; Nagaoki, Yoshihiro

PNC TN9410 97-022, 34 Pages, 1997/02

PNC-TN9410-97-022.pdf:1.05MB

The core averaged burn-up reactivity has been measured and calculated for the Joyo MK-II core. In order to evaluate the relationship between the calculational error of burn-up reactivity and the nuclear data or calculated neutron flux, the burn-up reactivity for an individual fuel subassembly(S/A) must be measured. So the burn-up reactivity measurement test was conducted on the MK-II core. The burn-up reactivity for a driver fuel S/A was measured as a substitution reactivity worth between two S/As at different burn-ups. In the test a fuel S/A with a burn-up of 1 GWd/t was substituted by two S/As with 37 and 62 GWd/t, respectively. The substitutions were carried out at the core center(row 0), middle of the fuel region(row 2)and the border region of the fuel and reflector(row 4). The calculated burn-up reactivity worth performed by the core management code system "MAGI" was compared with the measured value. The results obtained were as follows: (1)Measured substitution reactivity worth(at row 0) between 1 and 37 GWd/t fuel S/A was -0.19%k/kk' and that between 1 and 62 GWd/t was -0.28%k/kk'. (2)Relative distribution of the reactivity worth between 1 and 37 GWd/t agreed with that between 1 and 62 GWd/t. The relative value normalized at core center was 0.67 for the row 2 and 0.28 for the row 4. (3)The C/E value was 1.031.05 for the substitution between 1 and 37 GWd/t and 0.940.95 between 1 and 62 GWd/t at the row 0 and 2. It was clear that the C/E values at the row 4 are higher than those at the row 0 and 2 by 57%. An analysis of the burn-up dependency on the C/E value of the burn-up reactivity worth is being performed in detail. Presents, the PIE of the fuel S/A used for the measurement is under way.

Surveys of System Safety Assessment Methods (II)

Sayama, Hayatoshi*; Suzuki, Kazuhiko*; Shimada, Yukiyasu*

PNC TJ1612 96-001, 84 Pages, 1996/03

PNC-TJ1612-96-001.pdf:2.5MB

no abstracts in English

Research of technology for supporting operators in profound understanding(1); Observations and trial formulation of knowledge dependency of plant operator behavior

Yoshikawa, Shinji; Ozawa, Kenji; ; Odo, Toshihiro

PNC TN9410 95-160, 18 Pages, 1995/06

PNC-TN9410-95-160.pdf:0.89MB

This paper presents a study on knowledge dependency of plant operator behavior. The ultimate purpose of this study is to establish a methodology to support human operators in forming an integral understanding (i.e., mental model) of target plants, and thus to enhance potential performance in unexpected situations and in non routine cognitive tasks. The authors conducted a series of experiments to acquire behavioral data of two plant anomalies not included in the training curriculum. A formulation methodology of operator protocols has been proposed from the observations of the acquired behavioral data. It has been concluded that engaged plant operators have sufficient knowledge about physical phenomena of the major components, and that possible improvements of operators' cognitive performance can be expected mainly by knowledge enhancement about utilization strategy of physical information.

Integration of knowledge management support system for the decommissioning of nuclear facilities, 3

Iguchi, Yukihiro; Yanagihara, Satoshi*; Tezuka, Masashi; Koda, Yuya; Kato, Yasuaki

no journal, , 

no abstracts in English

Confirmation of effect sustainability after decontamination and prediction of future air dose rate change

Nishiuchi, Masashi*; Suzuki, Satoshi*; Kawase, Keiichi; Watanabe, Masanori; Yamashita, Takuya

no journal, , 

By monitoring air dose rate etc. for public facilities where decontamination work was completed, we confirmed the status of maintaining decontamination effect, and predicted future air dose rate change by "The Restoration Support System for Environment (RESET)" and "prediction model of ambient dose equivalent rate" developed by JAEA. As a result, it became clear that the decontamination effect was maintained, and the future air dose rate was predicted to be reduced by about 30% after 10 years. This survey was conducted in response to concerns of municipalities. The research results were reported to the relevant municipalities and was used as the basic data residents correspondence etc. in the municipalities.