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Journal Articles

Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state

Yamane, Yuichi

Journal of Nuclear Science and Technology, 14 Pages, 2022/04

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

The reactivity was estimated from a time profile of neutron count rate or a simulated data in a quasi-steady state after sudden change of reactivity or external neutron source strength. The estimation was based on the equation of power in subcritical quasi-steady state. The purpose of the study is to develop the method of timely reactivity estimation from complicated time profile of neutron count rate. The developed method was applied to the data simulating neutron count rate created by using one-point kinetics code, AGNES, and Poisson-distributed random noise and to the transient subcritical experiment data measured by using TRACY. The result shows that the difference of the estimated and reference value was within about 5% or less for ($$rho$$${$}$ $$>$$ -1) for simulated data and within about 7% or less for $$rho$$${$}$ $$simeq$$ -1.4 and -3.1 for the experimental data. It was also shown that the possibility of the reactivity estimation several ten seconds after the status change.

Journal Articles

A Linear Equation of characteristic time profile of power in subcritical quasi-steady state

Yamane, Yuichi

Journal of Nuclear Science and Technology, 57(8), p.926 - 931, 2020/08

 Times Cited Count:1 Percentile:21.02(Nuclear Science & Technology)

An equation of power in subcritical quasi-steady state has been derived based on one-point kinetics equations for the purpose of utilizing it for the development of timely reactivity estimation from complicated time profile of neutron count rate. It linearly relates power, $$P$$, to a new variable $$q$$, which is a function of time differential of the power. It has been confirmed by using one-point kinetics code, AGNES, that the calculated points ($$q, P$$) are perfectly in a line described by the new equation and that points ($$q, P$$) calculated from transient subcritical experiments by using TRACY made a line with a slope indicated by the new equation.

Journal Articles

Determination of reactivity and neutron flux using modified neural network for HTGR

Subekti, M.*; Kudo, Kazuhiko*; Nabeshima, Kunihiko; Takamatsu, Kuniyoshi

Atom Indonesia, 43(2), p.93 - 102, 2017/08

Reactor kinetics based on point kinetic model have been generally applied as the standard method for neutronics codes. As the central control rod (C-CR) withdrawal test has demonstrated in a prismatic core of HTTR, the transient calculation of kinetic parameter, such as reactivity and neutron fluxes, requires a new method to shorten calculation-process time. Development of neural network method was applied to point kinetic model as the necessity of real-time calculation that could work in parallel with the digital reactivity meter. The combination of TDNN and Jordan RNN, such as TD-Jordan RNN, was the result of the modeling approach. The application of TD-Jordan RNN with adequate learning, tested offline, determined results accurately even when signal inputs were noisy. Furthermore, the preprocessing for neural network input utilized noise reduction as one of the equations to transform two of twelve time-delayed inputs into power corrected inputs.

Journal Articles

Experiments and validation analyses of HTTR on loss of forced cooling under 30% reactor power

Takamatsu, Kuniyoshi; Tochio, Daisuke; Nakagawa, Shigeaki; Takada, Shoji; Yan, X.; Sawa, Kazuhiro; Sakaba, Nariaki; Kunitomi, Kazuhiko

Journal of Nuclear Science and Technology, 51(11-12), p.1427 - 1443, 2014/11

 Times Cited Count:11 Percentile:68.79(Nuclear Science & Technology)

In a safety demonstration test involving a loss of both reactor reactivity control and core cooling, HTGRs such as the HTTR, which is the only HTGR in Japan, demonstrate that the reactor power would stabilize spontaneously. In the test at an initial power of 30%, when the insertion of all control rods was disabled and all gas circulators were tripped to reduce the coolant flow rate to zero, a reactor transient was initiated and examined. The results confirmed that the reactor power would decrease immediately and become effectively zero.

Journal Articles

The Prediction of Boron concentrations in blood for patients of boron neutron capture therapy, 2

Shibata, Yasushi*; Matsumura, Akira*; Yamamoto, Tetsuya*; Akutsu, Hiroyoshi*; Yasuda, Susumu*; Nakai, Kei*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Hori, Naohiko; et al.

Research and Development in Neutron Capture Therapy, p.1055 - 1060, 2002/09

We prospectively investigated the predictability of blood boron concentrations using the data obtained at the first craniotomy after infusion of a low dose of sodium undecahydroclosododecaborate (BSH). Nine patients with malignant glial tumors underwent Boron neutron capture therapy (BNCT) at the Japan Atomic Energy Research Institute (JAERI) between 1995 and 2001. In 7 patients, 1g of BSH was infused before the first tumor removal and boron concentrations were determined using prompt gamma ray analysis (PGA). Then, 12 hours before BNCT, patients were infused at a dose of 100mg/kg BSH, and the boron concentrations were determined again. The boron biodistribution data showed a biexponential pharmacokinetic profile. If the final boron concentration at 6 or 9 hours after the end of the infusion is within the 95% confidence interval of the prediction, direct prediction from biexponential fit will reduce the error of blood boron concentrations during irradiation to around 6%.

JAEA Reports

REARA: Reactor kinetic analysis program for various events of reactivity insertion

Shimakawa, Satoshi; Tabata, Toshio; Komukai, Bunsaku

JAERI-Data/Code 99-045, p.31 - 0, 1999/11

JAERI-Data-Code-99-045.pdf:1.22MB

no abstracts in English

Journal Articles

Evaluation of F-factor for delayed integral counting method

Yamane, Tsuyoshi; Takeuchi, Mitsuo; Shimakawa, Satoshi; Kaneko, Yoshihiko*

Nihon Genshiryoku Gakkai-Shi, 40(2), p.122 - 123, 1998/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of the equivalent fundamental-mode source strength

G.D.Spriggs*; R.D.Busch*; Sakurai, Takeshi; Okajima, Shigeaki

Transactions of the American Nuclear Society, 76, p.374 - 375, 1997/06

no abstracts in English

Journal Articles

Delayed integral counting method for rod drop experiments

Kaneko, Yoshihiko*; Yamane, Tsuyoshi; Shimakawa, Satoshi; Yamashita, Kiyonobu

Nihon Genshiryoku Gakkai-Shi, 38(11), p.907 - 911, 1996/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Solution of 1-D multi-group time-dependent diffusion equations using the coupled reactors theory

Nagaya, Yasunobu; *

Annals of Nuclear Energy, 22(7), p.421 - 440, 1995/00

 Times Cited Count:7 Percentile:60.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Concept of a passive safety light water reactor system requiring reduced maintenance efforts

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Watanabe, Hironori

Transactions of the American Nuclear Society, 69, p.539 - 540, 1993/00

no abstracts in English

Journal Articles

Development of method to determine instability threshold with RETRAN code

Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

Nihon Genshiryoku Gakkai-Shi, 34(9), p.879 - 888, 1992/09

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

Development of the NSRR Digital Simulator

; Inabe, Teruo

JAERI-M 84-203, 67 Pages, 1984/11

JAERI-M-84-203.pdf:1.46MB

no abstracts in English

Journal Articles

Evaluation of effective energy deposition in test fuel during power burst experiments in NSRR

Onishi, Nobuaki; Inabe, Teruo

Journal of Nuclear Science and Technology, 19(7), p.528 - 542, 1982/00

 Times Cited Count:10 Percentile:71.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Reactor Physics Characteristics of the NSRR(Nuclear Safety Research Reactor)

; Inabe, Teruo;

Nihon Genshiryoku Gakkai-Shi, 17(6), p.314 - 321, 1975/06

no abstracts in English

19 (Records 1-19 displayed on this page)
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