Refine your search:     
Report No.
 - 
Search Results: Records 1-12 displayed on this page of 12
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

The Working group on the analysis and management of accidents (WGAMA); A Historical review of major contributions

Herranz, L. E.*; Jacquemain, D.*; Nitheanandan, T.*; Sandberg, N.*; Barr$'e$, F.*; Bechta, S.*; Choi, K.-Y.*; D'Auria, F.*; Lee, R.*; Nakamura, Hideo

Progress in Nuclear Energy, 127, p.103432_1 - 103432_14, 2020/09

 Times Cited Count:4 Percentile:16.23(Nuclear Science & Technology)

Journal Articles

Improvement of core dynamics analysis of control rod withdrawal test in HTGR

Takamatsu, Kuniyoshi; Nakagawa, Shigeaki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(1), p.45 - 56, 2006/03

The HTTR (High Temperature Engineering Test Reactor), which has thermal output of 30MW, coolant inlet temperature of 395$$^{circ}$$C and coolant outlet temperature of 850$$^{circ}$$C/950$$^{circ}$$C, is a first high temperature gas-cooled reactor (HTGR) in Japan. The HTGR has a high inherent safety potential to accident condition. Safety demonstration tests using the HTTR are underway in order to demonstrate such excellent inherent safety features of the HTGR. A one-point core dynamics approximation with one fuel channel model had applied to this analysis. It was found that the analytical model for core dynamics couldn't simulate the reactor power behavior accurately. This report proposes an original method using temperature coefficients of some regions in the core. It is crucial to evaluate this method precisely to simulate a performance of HTGR during the test.

Journal Articles

Vortex dissipation and level dynamics for the layered superconductors with impurities

Fujita, Ayumi

Physical Review B, 64(6), p.064504_1 - 064504_6, 2001/08

 Times Cited Count:0 Percentile:0(Materials Science, Multidisciplinary)

We study parametric level statistics of the discretized excitation spectra inside a moving vortex core in layered superconductors with impurities. The universal conductivity is evaluated numerically for the various values of rescaled vortex velocities $$kappa$$ from the clean case to the dirty limit case. The random matrix theoretical prediction is verified numerically in the large $$kappa$$ regime. On the contrary in the low velocity regime, we observe $$sigma_{xx} propto kappa^{2/3}$$which is consistent with the theoretical result for the super-clean case, where the energy dissipation is due to the Landau-Zener transition which takes place at the points called ``avoided crossing''.

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

Journal Articles

Estimation of net reactivity based on H$$_{infty}$$ estimation theory

Suzuki, Katsuo; Shimazaki, Junya; Shinohara, Yoshikuni

Nihon Genshiryoku Gakkai-Shi, 36(1), p.79 - 88, 1994/01

 Times Cited Count:2 Percentile:28.05(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Application of H$$_{infty}$$ optimal estimator to reactivity estimation of fast breeder reactor

Suzuki, Katsuo; Shimazaki, Junya

JAERI-M 93-062, 28 Pages, 1993/03

JAERI-M-93-062.pdf:0.71MB

no abstracts in English

JAEA Reports

Evaluation of reactivity coefficients for High Temperature Engineering Test reactor(HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Nakagawa, Shigeaki; Nakata, Tetsuo*; *

JAERI-M 90-008, 49 Pages, 1990/02

JAERI-M-90-008.pdf:1.17MB

no abstracts in English

JAEA Reports

Analysis of Space-Time Core Dynamics on Reactor Accident at Chernobyl

; ; ;

JAERI-M 87-059, 57 Pages, 1987/05

JAERI-M-87-059.pdf:1.54MB

no abstracts in English

JAEA Reports

Design of Slab Core Test Facility(SCTF)in Large Scale Reflood Test Pprogram,Part I :Core-I

; Sudo, Yukio; ; ; ; ; ; ; ; Osakabe, Masahiro; et al.

JAERI-M 83-080, 171 Pages, 1983/06

JAERI-M-83-080.pdf:3.9MB

no abstracts in English

JAEA Reports

SCTF Core-I Test Results(System Pressure Effects on Reflooding Phenomena)

; Sudo, Yukio; ; Osakabe, Masahiro; ;

JAERI-M 82-075, 36 Pages, 1982/07

JAERI-M-82-075.pdf:1.01MB

no abstracts in English

12 (Records 1-12 displayed on this page)
  • 1