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Tanaka, Masaaki; Uchibori, Akihiro; Okano, Yasushi; Yokoyama, Kenji; Uwaba, Tomoyuki; Enuma, Yasuhiro; Wakai, Takashi; Asayama, Tai
Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2023/09
The book, JSME Series in Thermal and Nuclear Power Generation Vol.3 Sodium-cooled Fast Reactor, was published as a 30th anniversary memorial project of Power & Energy Systems Division. This paper describes an introduction of the book on a part of key technologies regarding safety assessment, thermal-hydraulics, neutronics, and fuel and material development. This introductory paper also provides an overview of an integrated evaluation system named ARKADIA to offer the best possible solutions for challenges arising during the design process, safety assessment, and operation of a nuclear plant over its life cycle, in active use of the R&D efforts and knowledges on thermal-hydraulics and safety assessment with state-of-the-art numerical analysis technologies.
Okita, Shoichiro
Robutsuri No Kenkyu (Internet), (75), 3 Pages, 2023/03
This paper is a report on the International Conference on Physics of Reactors 2022 (PHYSOR2022), held in Pittsburgh, USA, from 15-19 May 2022.
Yamamoto, Akio*; Chiba, Go*; Kirimura, Kazuki*; Miki, Yosuke*; Yokoyama, Kenji
Nihon Genshiryoku Gakkai-Shi ATOMO
, 60(4), p.241 - 245, 2018/04
no abstracts in English
Suyama, Kenya
Kaku Deta Nyusu (Internet), (117), p.5 - 14, 2017/06
The benchmark calculation is one of the main activities of the Nuclear Science Committee under the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA/NSC). The international benchmark relatively frequently means the benchmark activity carried out by the NEA. In this manuscript, the author discusses the significance of the international benchmark by describing (i) the current status of the benchmark in the field of the reactor physics conducted by the OECD/NEA/NSC, (ii) revision of the neutronics calculation code system to reflect the results of the benchmark, (iii) the benchmark calculation as the asset for the future research and development, (iv) examples of the benchmark calculation based on the experimental data, and (v) how to propose the benchmark in the OECD/NEA/NSC.
Kitano, Akihiro; Takegoshi, Atsushi*; Hazama, Taira
Journal of Nuclear Science and Technology, 53(7), p.992 - 1008, 2016/07
Times Cited Count：9 Percentile：60.26(Nuclear Science & Technology)A feedback reactivity measurement technique was developed based on a reactivity model featuring components that depend on the reactivity coefficients, denoted as reactor power (K
) and reactor vessel inlet temperature (K
). This technique was applied to the feedback reactivity experiment conducted in the Monju system start-up test in May 2010. A thorough evaluation considering all possible biases and uncertainties revealed that the reactivity coefficients can be evaluated with a measurement uncertainty smaller than 3%. The evaluated reactivity coefficients were simulated considering the temperature distribution in the core. The C/E value of K showed good agreement between calculated and measured values within the established uncertainty, and the value of K was consistent with that reported in a previous isothermal temperature coefficient experiment. The measured and calculated fuel subassembly outlet temperatures also agreed well within 0.2
C.
Tada, Kenichi; Hagura, Naoto*
Robutsuri No Kenkyu (Internet), (67), 105 Pages, 2015/03
In 2014 AESJ autumn meeting, the session, that the title name is current condition and future status of the human resources for the reactor physics field, was presented. In this session, the employment status was investigated and the questionnaire was desigined. In this paper, the detail result of the emplyment status and the questionnaire was described.
Suyama, Kenya
Robutsuri No Kenkyu (Internet), (66), p.11 - 14, 2014/03
The development of an original nuclear data processing code has been recognized as the most important issue in Japan. This report describes the background information on the development of it carried out in JAEA.
Tsujimoto, Kazufumi; Tazawa, Yujiro; Oigawa, Hiroyuki; Sasa, Toshinobu; Takano, Hideki
JAERI-Tech 2003-085, 158 Pages, 2003/11
JAERI-Tech-2003-085.pdf:7.79MB
A safety analysis was performed for the Transmutation Physics Experiment Facility which was to research and develop the reactor physics aspects of the nuclear transmutation technology using the accelerator driven subcritical system. Design policies were evaluated for design of each equipment and system which had important role from view point of safety. Classification of safety class for reactor building, system, and equipment was also reconsidered. Based on the results of safety design policy, acceptance criteria for safety evaluation were reestablished and preliminary analysis were performed. Public exposure by the accident for site appropriateness assessment was evaluated based on revised guidelines in safety evaluation contained in the 1990 Recommendations of ICRP. A recritical event was analyzed by utilizing the newest knowledge for core disruptive accident and calculation code as the beyond design basis accident. The analytical results showed that the isolation capability of the container buildings was ensured against the recritical accident.
Nuclear Code Evaluation Special Committee of Nuclear Code Research Committee
JAERI-Conf 2000-018, 342 Pages, 2001/01
JAERI-Conf-2000-018.pdf:19.4MB
no abstracts in English
Ida, Toshikazu*; Suyama, Kenya; Shimazu, Yoichiro*; *; Matsumoto, Hideki*; Shiraki, Takako*
Nihon Genshiryoku Gakkai-Shi, 42(9), p.903 - 906, 2000/09
no abstracts in English
Ishikawa, Nobuyuki; Nakatsuka, Toru; Iwamura, Takamichi
JAERI-Conf 2000-010, 267 Pages, 2000/06
JAERI-Conf-2000-010.pdf:18.03MB
no abstracts in English
; Numata, Kazuyuki*; ; *; Oigawa, Hiroyuki*
JNC TY9400 2000-006, 162 Pages, 2000/04
JNC-TY9400-2000-006.pdf:4.57MB
no abstracts in English
Wada, Hiroaki
JNC TN8400 2000-015, 37 Pages, 2000/03
This report describes the study done within the period of time when I was postdoctoral research worker at Japan Nuclear Cycle Development Institute. The report includes two parts as follows. (1) Exact Solution of Electric Transitions for High Energy photons. Technologies for creating high-energy 
beams have been rapidly developed. These advancements make the research using high-energy -rays more important. The electric transition rates for high-energy -rays were formulated. The electric multipole fields were treated strictly in the process of calculating the electric transition rates and the nuclear states were taken as the harmonic oscillator wave functions. (2) Production of the isomeric state of 
Cs in the thermal neutron capture reaction 
Cs(n, )Cs. In order to obtain precise data of the neutron capture cross section of the reaction Cs(n, )Cs, the production probability of isomer state 
Cs was measured in this work. The 1436 keV -ray emitted from both of 
Cs and Cs was measured. A production ratio of Cs to (Cs and Cs) was deduced from time dependence of peak counts of 1436keV -ray. The probability of the production of CS was obtained as 0.75
0.18 and this value revised the effective cross section upwards 92%. The effective cross section 
and the thermal neutron capture cross section 
were obtained as =0.290.02 b and =0.270.03 b with taking into account the production of 
Cs.
JRR-3 Operation Division; Research Reactor Utilization Division
JAERI-Tech 2000-027, p.194 - 0, 2000/03
JAERI-Tech-2000-027.pdf:8.47MB
no abstracts in English
Iwamura, Takamichi
Genshiryoku eye, 46(1), p.19 - 23, 2000/00
no abstracts in English
Dietze, K.
JNC TN9400 99-089, 20 Pages, 1999/11
The integral experiments performed at the Rossendorf fast-thermal coupled reactor RRR/SEG have been reanalyzed using the JNC route for reactor calculation JENDL3.2/SLAROM / CITATION / JOINT / PERKY. The Rossendorf experiments comprise sample reactivity measurements with pure fission products and structural material in five configurations with different neutron and adjoint spectra. The shapes of the adjoint spectra have been designed to get high sensitivities to neutron capture or the scattering effect. The calculated neutron and adjoint spectra are in good agreement with former results obtained with the European route JEF2.2/ECCO/ERANOS. The C/E-values of the central reactivity worths of samples under investigation are given. Deviations in the results of both routes are due to the different libraries, codes, and self-shielding treatments used in the calculations. Results outside of the error are discussed.
Mizuta, Shunji; ;
JNC TN9400 99-082, 60 Pages, 1999/10
The density measurement of the internal creep specimens irradiated in FFTF/MOTA (Fast Flux Test Facility / Material open Test Assembly) was conducted MMF (Materia1 Monitoring Facility) and accurate separation of swelling strain from total strain leaded in the derivation of the irradiation creep coefficients. Irradiation creep coefficients for PNC 316, 15Cr-20Ni base S.S. and 14Cr-25Ni base S.S. were systematically expressed, while thermal creep coefficients K, under irradiation were separately expressed for above three steels. The results obtained are follows, (1)The effect of stress induced swelling was recognized in the temperature range from 405 to 605C. The swelling in high stress specimens have a tendency to increasing swelling. (2)The irradiation creep coefficients derived from PNC316 and l5Cr-20Ni are similar to that of derived from 20%CW316S.S., CW316Ti and CW15-15Ti which were reported by other authors. (3)The irradiation creep coefficient derived from gas pressurized tube irradiation using FFTF/MOTA expressed appropriately irradiation creep strain from fuel pins using FFTF/MFA-2(15Cr-2ONi base S.S.).
; Toyama, Shinichi; Nomura, Masahiro; Hirano, Koichiro; Yamazaki, Yoshio; Sato, Isamu
JNC TN9400 99-073, 18 Pages, 1999/08
A short traveling wave accelerator with a traveling wave resonant ring is proposed for high beam current accelerators (including the linear accelerator, circular accelerator and storage ring). It is a normal conducting accelerator. The CW beam current can be as high as 10A. Such kind of accelerator unit has large beam holes for damping all of the cavity high order modes in order to avoid the resonant buildup of the fields that would cause multibunch instabilities at high currents. It has high efficiency, high power input capability and low K
. It is called "single mode" type. Even though beams are accelerated off the crest for phase stability in circular accelerator, the cavities do not need detuning.
; Aoto, Kazumi;
JNC TN9400 99-061, 32 Pages, 1999/07
In this report, reconstruction of magnetic charges induced by mechanical damages in a test piece of SUS304 stainless steel is performed as a part of eforts to establish a passive nondestructive testing method on the basis of the inspection of leakage magnetic field. The approach for solving this typical ill-posed inverse problem is selected as a way in the least square method category. Concerning the ill-poseness of the system of equations, an iteration algorithm is adopted to its solving in which the designations of initial profile, the weight coefficients and the total number of iterations are taken as means of reqularization. From examples using simulated input data, it is verified that the approach gives good reconstruction results in case of signals with a relative high S/N ratio. For improving the robustness of the proposed method, a Galerkin procedure with base functions chosen as the Daubechies' wavelet is also introduced for discretizing the governing equation. By comparing the reconstruction results of the least square method and those using wavelet discretization, it is found that the wavelet used approach is more feasible in the inversion of noise polluted signals. Reconstruction of 1-D and 2-D magnetic charges with the least square strategy and reconstruction of an 1-D problem with the wavelet used method are carried out from both simulated and measured magnetic field signals which are used as the validation of the proposed inversion strategy.
