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JAEA Reports

Summaries of research and development activities by using JAERI computer system in FY2004 (April 1, 2004 - March 31, 2005)

Information Systems Operating Division

JAERI-Review 2005-032, 151 Pages, 2005/08

JAERI-Review-2005-032.pdf:11.51MB

Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Research Institute (JAERI) installed large computer systems including super-computers in order to support research and development activities in JAERI. CCSE operates and manages the computer system and network system. This report presents usage records of the JAERI computer system and the big users' research and development activities by using the computer system in FY2004 (April 1, 2004 - March 31, 2005).

JAEA Reports

Summaries of research and development activities by using JAERI computer system in FY2003 (April 1, 2003 - March 31, 2004)

Center for Promotion of Computational Science and Engineering

JAERI-Review 2005-008, 199 Pages, 2005/03

JAERI-Review-2005-008.pdf:30.15MB

The Center for Promotion of Computational Science and Engineering (CCSE) in Japan Atomic Energy Research Institute (JAERI) installed large computer system including super-computers in order to support research and development activities in JAERI. CCSE is also operate anad manage the computer system and network system. This report presents the survey results of research and development activities by using JAERI computer system in FY2003.

JAEA Reports

Surveillance system for radiation monitoring in HTTR

Nakazawa, Takashi; Kikuchi, Hisaki; Yasu, Katsuji; Yoshino, Toshiaki; Ashikagaya, Yoshinobu; Sato, Koichi; Minowa, Yuji; Nomura, Toshibumi

JAERI-Tech 2001-010, 125 Pages, 2001/03

JAERI-Tech-2001-010.pdf:7.4MB

no abstracts in English

JAEA Reports

None

Shinohara, Yoshinori*; Tsujimoto, Keiichi*

JNC TJ1400 2000-002, 280 Pages, 2000/02

JNC-TJ1400-2000-002.pdf:9.57MB

no abstracts in English

JAEA Reports

None

Shinohara, Yoshinori*; Tsujimoto, Keiichi*

JNC TJ1400 2000-001, 137 Pages, 2000/02

JNC-TJ1400-2000-001.pdf:4.19MB

no abstracts in English

JAEA Reports

Development of whole core thermal-hydraulic analysis program ACT (III); Coupling core module with primary heat transport system module

Otaka, Masahiko; Ohshima, Hiroyuki

JNC TN9400 98-004, 34 Pages, 1998/10

JNC-TN9400-98-004.pdf:1.44MB

A whole core thermal hydraulic analysis program ACT is being developed for the purpose of evaluating detailed in-core thermal hydraulic phenomena of fast reactors including inter-wrapper flow under various reactor operation conditions. In this work, the core module as a main part of the ACT developed last year, which simulates thermal-hydraulics in the subassemblies and the inter-subassembly gaps, was coupled with an one dimensional plant system thermal-hydraulic analysis code LEDHER to simulate transients in the primary heat transport system and to give appropriate boundary conditions to the core model. The effective algorithm to couple these two calculation modules was developed, which required minimum modification of them. In order to couple these two calculation modules on the computing system, parallel computing technique using PVM(Parallel Virtual Machine) programming environment was applied. The code system was applied to analyze an out-of-pile sodium experiment simulating core with 7 subassemblies under transient condition for code verification. It was confirmed that analytical results show a similar tendency of experimental results.

JAEA Reports

None

Asaharam Shinya*

PNC TJ1064 98-002, 109 Pages, 1998/02

PNC-TJ1064-98-002.pdf:8.48MB

None

JAEA Reports

Advanced graphical user interface to the MAAP/Fugen simulator system

Lund

PNC TN3410 98-002, 34 Pages, 1998/01

PNC-TN3410-98-002.pdf:6.11MB

A new and improved Graphical User Interface (GUI) to the Modular Accident Analysis Program for FUGEN (MAAP/FUGEN) has been developed and implemented at Fugen. The new user interface is a superset of the existing GUI to MAAP - the MAAP/FUGEN/GRAAPH - in the meaning that it contains all the features of the GRAAPH, but in addition offers a number of new features. The new interface, named MAAP-PICASSO is based on the Picasso-3 technology developed by Institutt for Energiteknikk/OECD Halden Reactor Project. The main difference between the MAAP-PICASSO and MAAP-FUGEN-GRAAPH GUIs is that the MAAP-PICASSO GUI is completely decoupled from the numerical simulator. This gives a far higher flexibility regarding enhancement of the GUI, connection to other, external software and user friendliness. It also includes techniques for presenting 2 byte character set - i.e. displaying text in Japanese characters. A special software has been developed for automatic extraction and reuse of the graphical plant information provided in MAAP/GRAPH into Picasso language. This software-has been demonstrated not only on the Fugen plant data, but also other Nuclear Power Plant picture definitions provided by Fauske Inc. The new GUI requires a minimal modification of the MAAP code itself However, these modification is only for parameter communication and is not intrusive to the numerical computations of MAAP itself. The GUI has been developed using modular and object-oriented programming techniques, which makes it relatively easy to extend and modify to fulfill present and future requirements from the users at Fugen, and makes it compatible with future versions of the MAAP code. MAAP-PICASSO is developed on and currently running only on HP UNIX workstations. However, a new NT-based version of Picasso-3 will be released from the Halden Project in February 1998. This will further enhance the applicability and usability of the MAAP-PICASSO GUI.

Journal Articles