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Journal Articles

Analysis of a BWR turbine trip experiment by entire plant simulation with spatial kinetics

Asahi, Yoshiro; Suzudo, Tomoaki; Ishikawa, Nobuyuki; Nakatsuka, Toru

Nuclear Science and Engineering, 152(2), p.219 - 235, 2006/02

 Percentile:100(Nuclear Science & Technology)

An analysis of a BWR turbine trip experiment was performed with the THYDE-NEU code. The plant was treated as a closed coolant system whose pressure ranges to the atmospheric pressure. To simulate an entire plant, it was found necessary to have the moisture separator model and to account for reversible pressure drops at a junction with an area change. A spatial kinetics model without a notion of reactivity was applied. It was confirmed that THYDE-NEU can perform a coupled neutronic and thermal-hydraulic null transient at the hot full power. Among factors influencing spatial kinetics in the turbine trip were the temporal behavior of the bypass valve opening, the thermal non-equilibrium model and the manner in which to express the coolant density used in the table look-up of cross sections. By adjusting these factors, it was found possible to generate the scram signal when the core averaged LPRM output reached the prescribed value. The other calculated results also were found satisfactorily in agreement with the experimental results.

JAEA Reports

THYDE-NEU; Nuclear reactor system analysis code

Asahi, Yoshiro

JAERI-Data/Code 2002-002, 332 Pages, 2002/03

JAERI-Data-Code-2002-002.pdf:10.6MB

no abstracts in English

Journal Articles

A Spatial kinetics method ensuring neutronic balance with thermal-hydraulic feedback and its application to a main steam line break

Asahi, Yoshiro; Okumura, Keisuke; Ose, Yasuo*

Nuclear Science and Engineering, 139(1), p.78 - 95, 2001/09

 Times Cited Count:1 Percentile:86.33(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Transient analysis of loss of feed water at PIUS experimental apparatus

Watanabe, Tadashi; Asahi, Yoshiro; *; Anoda, Yoshinari; *; Kukita, Yutaka

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.315 - 320, 1991/00

no abstracts in English

JAEA Reports

THYDE-W; RCS(reactor coolant system) analysis code

Asahi, Yoshiro; Matsumoto, Kiyoshi; Hirano, Masashi

JAERI-M 90-172, 305 Pages, 1990/10

JAERI-M-90-172.pdf:5.1MB

no abstracts in English

Journal Articles

Conceptual design of integrated reactor with inherent safery

Asahi, Yoshiro; *; *

Nuclear Technology, 91, p.28 - 50, 1990/07

 Times Cited Count:2 Percentile:67.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of spectral shift effect on reactor dynamics and its application to RBMK-1000 and light water reactors

Asahi, Yoshiro;

Nuclear Science and Engineering, 101, p.226 - 242, 1989/03

 Times Cited Count:1 Percentile:77.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Loss-of-coolant accident of JRR-2 in a safety analysis for core conversion

Sato, Takeshi; ; Asahi, Yoshiro; ; ; Tsunoda, Junsaku

Japan-China Symp. on Reseach and Test Reactors, 11 Pages, 1988/00

no abstracts in English

Journal Articles

Evaluation of PWR-LOCA under LOFT L2-3 condition

Asahi, Yoshiro; ;

Journal of Nuclear Science and Technology, 24(5), p.365 - 376, 1987/05

 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Improvement of passive safety of reactors

Asahi, Yoshiro; ; *

Nuclear Science and Engineering, 96, p.73 - 84, 1987/00

 Times Cited Count:3 Percentile:45.45(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

THYDE-P2 code; RCS(reactor-coolant system) analysis code

Asahi, Yoshiro; Hirano, Masashi;

JAERI 1300, 172 Pages, 1986/12

JAERI-1300.pdf:4.15MB

no abstracts in English

JAEA Reports

Numerical Jables of Thermodynamic Properties of Sodium

Asahi, Yoshiro; *

JAERI-M 86-088, 46 Pages, 1986/06

JAERI-M-86-088.pdf:1.21MB

no abstracts in English

Journal Articles

Some transient characteristics of PIUS

Asahi, Yoshiro; *

Nuclear Technology, 72, p.24 - 33, 1986/00

 Times Cited Count:2 Percentile:66.59(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A THROUGH CALUCULATION OF 1,100MWe PWR LARGE BREAK LOCA BY THYDE-P1 EM MODEL(SAMPLE CALCULATION RUN 80)

*; Asahi, Yoshiro; Hirano, Masashi

JAERI-M 84-132, 97 Pages, 1984/07

JAERI-M-84-132.pdf:2.14MB

no abstracts in English

Journal Articles

New non-equilibrium thermal-hydraulic model, (I); Theory

Asahi, Yoshiro; *

Journal of Nuclear Science and Technology, 21(9), p.657 - 670, 1984/00

 Times Cited Count:4 Percentile:52.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

New non-equilibrium thermal-hydraulic model, II; Application to LOFT L2-3

Asahi, Yoshiro; *

Journal of Nuclear Science and Technology, 21(10), p.753 - 763, 1984/00

 Times Cited Count:4 Percentile:52.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Principles of PIUS: Some safety-related characteristics

Asahi, Yoshiro; *

Transactions of the American Nuclear Society, 47, p.297 - 298, 1984/00

no abstracts in English

JAEA Reports

The JAERI code system for evaluation of BWR ECCS performance

; ; Asahi, Yoshiro; ; ; ;

JAERI 1283, 238 Pages, 1982/12

JAERI-1283.pdf:10.48MB

no abstracts in English

JAEA Reports

Analysis of PKL Test K9 by THYDE-P Code; CSNI ISP No.10 and THYDE-P Sample Calculation Run 70

; ; Asahi, Yoshiro

JAERI-M 82-115, 63 Pages, 1982/09

JAERI-M-82-115.pdf:1.57MB

no abstracts in English

JAEA Reports

User's Mannual for THYDE-P1

Asahi, Yoshiro

JAERI-M 82-038, 55 Pages, 1982/04

JAERI-M-82-038.pdf:1.04MB

no abstracts in English

31 (Records 1-20 displayed on this page)