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Journal Articles

Considerations on phenomena scaling for BEPU

Nakamura, Hideo

Proceedings of ANS International Conference on Best Estimate Plus Uncertainties Methods (BEPU 2018) (USB Flash Drive), 8 Pages, 2018/00

no abstracts in English

JAEA Reports

Thermal design study of lead-bismuth cooled accelerator driven system, 1; Study on thermal hydraulic behavior under normal operation condition

Akimoto, Hajime; Sugawara, Takanori

JAEA-Data/Code 2016-008, 87 Pages, 2016/09

JAEA-Data-Code-2016-008.pdf:15.62MB

Thermal hydraulic behavior in a lead-bismuth cooled accelerator driven system (ADS) is analyzed under normal operation condition. Input data for the ADS version of J-TRAC code have been constructed to integrate the conceptual design. The core part of the ADS is modeled in detail to evaluate the core radial power profile effect on the core cooling. As the result of the analyses, the followings are found; (1) Both maximum clad temperature and fuel temperature are below the design limits. (2) The radial power profile has little effect on the coolant flow distribution among fuel assemblies. (3) The radial power profile has little effect on the heat transfer coefficients along fuel rods. (4) The thermal hydraulic behaviors along four steam generators are identical. The thermal hydraulic behaviors along two pumps are also identical. A fast running input data is developed by the simplification of the detailed input data based on the findings mentioned above.

JAEA Reports

Development of thermal-hydraulic design code for transmutation system with lead-bismuth cooled accelerator driven reactor

Akimoto, Hajime

JAEA-Data/Code 2014-031, 75 Pages, 2015/03

JAEA-Data-Code-2014-031.pdf:37.23MB

A thermal-hydraulic analysis code for transmutation system with lead-bismuth cooled accelerator-driven system (ADS) has been developed using the Japanese-version of Transient Reactor Analysis Code (J-TRAC) as the framework to apply the design studies of ADS. To identify the required capabilities of the thermal-hydraulic analysis code for ADS, previous thermal-hydraulic analyses of light water reactors, sodium-cooled fast reactor and ADS have been surveyed. To make up for insufficient capabilities of the J-TRAC code as a thermal-hydraulic analysis code of ADS, physical properties of lead-bismuth eutectic (LBE), argon gas and nitride nuclear fuel were implemented to the J-TRAC code. It was confirmed that the implemented capabilities worked as expected through verification calculations on (1) single-phase LBE flow, (2) heat transfer in a fuel assembly, and (3) heat transfer in a steam generator.

JAEA Reports

Sensitivity analysis on flammable gas dispersion and explosion in HTTR hydrogen production system with fire and explosion analysis code system -P2A- (Contract research)

Inaba, Yoshitomo; Nishihara, Tetsuo

JAERI-Tech 2005-033, 206 Pages, 2005/07

JAERI-Tech-2005-033.pdf:34.71MB

In this report, we investigated the effects of jet for the dispersion and explosion analysis of leaked gas, obstacles, position of an ignition point and cell size for the gas explosion analysis, and atmospheric stability for the dispersion analysis of the leaked gas, with PHOENICS, AutoReaGas, and AUTODYN. Then, we carried out two accident analyses about combustible fluid leakage based on the investigation results of these effects. As a result, it was shown that important buildings related to safety was hardly affected by the explosion of the leaked gas.

JAEA Reports

Development of dynamic analysis code for HTTR hydrogen production system (Contract research)

Maeda, Yukimasa; Nishihara, Tetsuo; Ohashi, Hirofumi; Sato, Hiroyuki; Inagaki, Yoshiyuki

JAERI-Data/Code 2005-001, 149 Pages, 2005/03

JAERI-Data-Code-2005-001.pdf:12.66MB

A heat and mass balance analysis code (N-HYPAC) has been developed to investigate transient behavior in the HTTR hydrogen production system. The code can analyze heat and mass transfer (temperature and mass and pressure distributions of process and helium gases) and behavior of the control system under both static state(case of steady operation) and dynamic state(case of transient operation). Analysis model of helium and process gases from IHX to secondary helium loop and hydrogen production system has been constructed. This report describes analytical flow sheet, construction of the code, basic equations, method to treat the input data, estimation of the preliminary analysis.

JAEA Reports

Development of heat and mass balance analysis code in out-of-pile hydrogen production system for HTTR heat utilization system (Contract research)

Inaba, Yoshitomo; Inagaki, Yoshiyuki; Hayashi, Koji; *

JAERI-Data/Code 99-009, 93 Pages, 1999/03

JAERI-Data-Code-99-009.pdf:2.74MB

no abstracts in English

JAEA Reports

Development of analytical code 'ACCORD' for incore and plant dynamics of high temperature gas-cooled reactor

Takeda, Takeshi; Tachibana, Yukio; Kunitomi, Kazuhiko; Itakura, Hirofumi*

JAERI-Data/Code 96-032, 147 Pages, 1996/11

JAERI-Data-Code-96-032.pdf:4.58MB

no abstracts in English

JAEA Reports

Benchmark calculations by the nuclearcriticality safety analysis code system JACS(MGCL, KENO-IV)

Nomura, Yasushi; Katakura, Junichi; Naito, Yoshitaka; Komuro, Yuichi; Okuno, Hiroshi

JAERI 1303, 152 Pages, 1986/11

JAERI-1303.pdf:4.56MB

no abstracts in English

Journal Articles

Safety research on BWR LOCA

; Murao, Yoshio; Tasaka, Kanji

Nippon Genshiryoku Gakkai-Shi, 28(10), p.887 - 907, 1986/00

no abstracts in English

JAEA Reports

Users' Manual for the FTA-J(Fault Tree Analysis - JAERI) Code System

; Watanabe, Norio; *; *; *;

JAERI-M 83-169, 160 Pages, 1983/11

JAERI-M-83-169.pdf:4.36MB

no abstracts in English

JAEA Reports

Investigation of Reflood Models by Coupling REFLA-1D and Multi-Loop System Model

; Murao, Yoshio

JAERI-M 83-147, 49 Pages, 1983/09

JAERI-M-83-147.pdf:1.13MB

no abstracts in English

Journal Articles

Blowdown force analysis of piping system under LOCA conditions using BLOWDOWN code

; *

Nucl.Eng.Des., 76, p.121 - 135, 1983/00

 Times Cited Count:1 Percentile:76.47

no abstracts in English

Oral presentation

Scaling in V&V for safety analysis

Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

V&V and scaling for nuclear safety analysis

Nakamura, Hideo

no journal, , 

no abstracts in English

14 (Records 1-14 displayed on this page)
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