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Development of Nuclear ship Engineering Simulation SYstem (NESSY)

Abstract

NESSY has been developed for design studies of advanced marine reactors as a part of nuclear ship research and development since 1987. Engineering simulation model of the Mutsu, which is the first nuclear ship in Japan, was completed in March of 1993. In this report we concentration on detail description of softwares for Mutsu modeling. The aims of development of NESSY are as follows; (1) Assessment and confirmation on plant performance of an advanced marine reactor in each step of nuclear ship design (2) Development of abnormality diagnosis system and operator support system as a part of enhanced automization study, and study of human interface with hardware The characteristics of NESSY are the followings. (1) Total engineering simulation system simulate simultaneously ship motions, propulsion system behavior, and nuclear plant behavior under given weather and sea conditions. (2) Models based on physical theory as far as possible. (3) The simulator has high extensibility and flexibility. It is able to apply to other reactors, as the simulation model consists of the part of basic model and the part of plant data which are easy to change. After completion of Mutsu modeling, we are planning to utilize this system as one of design  More>>
Authors:
Kusunoki, Tsuyoshi; Kyouya, Masahiko; Takahashi, Teruo; Kobayashi, Hideo; Ochiai, Masa-aki; [1]  Hashidate, Kouji
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Nov 01, 1993
Product Type:
Technical Report
Report Number:
JAERI-M-93-223
Reference Number:
SCA: 210600; PA: JPN-94:001186; EDB-94:044576; ERA-19:012160; NTS-94:017854; SN: 94001163895
Resource Relation:
Other Information: PBD: Nov 1993
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; NS MUTSU; COMPUTERIZED SIMULATION; SHIP PROPULSION REACTORS; REACTOR SIMULATORS; REACTOR OPERATION; AUTOMATION; PRIMARY COOLANT CIRCUITS; STEAM GENERATORS; LOSS OF COOLANT; AUXILIARY SYSTEMS; WEATHER; REACTOR CORES; 210600; POWER REACTORS, MOBILE, PROPULSION, PACKAGE, AND TRANSPORTABLE
OSTI ID:
10131658
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE94748671; TRN: JP9401186
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
186 p.
Announcement Date:
Jul 04, 2005

Citation Formats

Kusunoki, Tsuyoshi, Kyouya, Masahiko, Takahashi, Teruo, Kobayashi, Hideo, Ochiai, Masa-aki, and Hashidate, Kouji. Development of Nuclear ship Engineering Simulation SYstem (NESSY). Japan: N. p., 1993. Web.
Kusunoki, Tsuyoshi, Kyouya, Masahiko, Takahashi, Teruo, Kobayashi, Hideo, Ochiai, Masa-aki, & Hashidate, Kouji. Development of Nuclear ship Engineering Simulation SYstem (NESSY). Japan.
Kusunoki, Tsuyoshi, Kyouya, Masahiko, Takahashi, Teruo, Kobayashi, Hideo, Ochiai, Masa-aki, and Hashidate, Kouji. 1993. "Development of Nuclear ship Engineering Simulation SYstem (NESSY)." Japan.
@misc{etde_10131658,
title = {Development of Nuclear ship Engineering Simulation SYstem (NESSY)}
author = {Kusunoki, Tsuyoshi, Kyouya, Masahiko, Takahashi, Teruo, Kobayashi, Hideo, Ochiai, Masa-aki, and Hashidate, Kouji}
abstractNote = {NESSY has been developed for design studies of advanced marine reactors as a part of nuclear ship research and development since 1987. Engineering simulation model of the Mutsu, which is the first nuclear ship in Japan, was completed in March of 1993. In this report we concentration on detail description of softwares for Mutsu modeling. The aims of development of NESSY are as follows; (1) Assessment and confirmation on plant performance of an advanced marine reactor in each step of nuclear ship design (2) Development of abnormality diagnosis system and operator support system as a part of enhanced automization study, and study of human interface with hardware The characteristics of NESSY are the followings. (1) Total engineering simulation system simulate simultaneously ship motions, propulsion system behavior, and nuclear plant behavior under given weather and sea conditions. (2) Models based on physical theory as far as possible. (3) The simulator has high extensibility and flexibility. It is able to apply to other reactors, as the simulation model consists of the part of basic model and the part of plant data which are easy to change. After completion of Mutsu modeling, we are planning to utilize this system as one of design tools for an advanced marine reactor. (author).}
place = {Japan}
year = {1993}
month = {Nov}
}