Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 32

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

Development of nuclear data processing code FRENDY version 2

Tada, Kenichi; Yamamoto, Akio*; Kunieda, Satoshi; Konno, Chikara; Kondo, Ryoichi; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*

Journal of Nuclear Science and Technology, 10 Pages, 2023/00

Nuclear data processing code is important to connect evaluated nuclear data libraries and radiation transport codes. The nuclear data processing code FRENDY version 1 was released in 2019 to generate ACE formatted cross section files with simple input data. After we released FRENDY version 1, many functions were developed, e.g., neutron multi-group cross section generation, explicit consideration of the resonance interference effect among different nuclides in a material, consideration of the resonance upscattering, ACE file perturbation, and modification of ENDF-6 formatted file. FRENDY version 2 was released including these new functions. It generates GENDF and MATXS formatted neutron multi-group cross section files from an ACE formatted cross section file or an evaluated nuclear data file. This paper explains the features of the new functions implemented in FRENDY version 2 and the verification of the neutron multigroup cross section generation function of this code.

Journal Articles

Development of nuclear data processing code FRENDY version 2

Tada, Kenichi; Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*

Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022) (Internet), 10 Pages, 2022/05

Nuclear data processing is an important interface between an evaluated nuclear data library and nuclear transport calculation codes. JAEA has developed a new nuclear data processing code FRENDY from 2013. FRENDY version 1 generates ACE files which are used for the continuous-energy Monte Carlo codes including PHITS, Serpent, and MCNP; it was released as an open-source software under the 2-clause BSD license in 2019. After FRENDY version 1 was released, many functions are developed: the multi-group neutron cross-section library generation, the statistical uncertainty quantification for the probability tables for unresolved resonance cross-section, the perturbation of the ACE file, and the modification of the ENDF-6 formatted nuclear data file, etc. We released FRENDY version 2 including these functions. This presentation explains the overview of FRENDY and features of the new functions implemented in FRENDY version 2.

Journal Articles

Progress in conceptual design of a pool-type sodium-cooled fast reactor in Japan

Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Miyagawa, Takayuki*; Uchita, Masato*; Suzuno, Tetsuji*; Endo, Junji*; Kubo, Koji*; Murakami, Hisatomo*; Uzawa, Masayuki*; et al.

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 11 Pages, 2022/04

The authors are carrying out conceptual design studies for a pool-type sodium-cooled fast reactor. There are main challenges such as measures against severe earthquake in Japan, thermal hydraulic in a reactor vessel (RV), a decay heat removal system design. When the JP-pool SFR of 650 MWe is installed in Japan, it shall be designed against the severe seismic conditions. Additionally, a newly three-dimensional seismic isolation system is under development.

Journal Articles

Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV

Endo, Shunsuke; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Rovira Leveroni, G.; Terada, Kazushi*; Meigo, Shinichiro; Toh, Yosuke; Segawa, Mariko; et al.

Journal of Nuclear Science and Technology, 59(3), p.318 - 333, 2022/03

 Times Cited Count:2 Percentile:66.98(Nuclear Science & Technology)

Journal Articles

Nondestructive quantitative analysis of difficult-to-measure radionuclides $$^{107}$$Pd and $$^{99}$$Tc

Toh, Yosuke; Segawa, Mariko; Maeda, Makoto; Tsuneyama, Masayuki*; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Ebihara, Mitsuru*

Analytical Chemistry, 93(28), p.9771 - 9777, 2021/07

 Times Cited Count:3 Percentile:25.73(Chemistry, Analytical)

Journal Articles

Progress in long-pulse production of powerful negative ion beams for JT-60SA and ITER

Kojima, Atsushi; Umeda, Naotaka; Hanada, Masaya; Yoshida, Masafumi; Kashiwagi, Mieko; Tobari, Hiroyuki; Watanabe, Kazuhiro; Akino, Noboru; Komata, Masao; Mogaki, Kazuhiko; et al.

Nuclear Fusion, 55(6), p.063006_1 - 063006_9, 2015/06

 Times Cited Count:38 Percentile:89.6(Physics, Fluids & Plasmas)

Significant progresses in the extension of pulse durations of powerful negative ion beams have been made to realize the neutral beam injectors for JT-60SA and ITER. In order to overcome common issues of the long pulse production/acceleration of negative ion beams in JT-60SA and ITER, the new technologies have been developed in the JT-60SA ion source and the MeV accelerator in Japan Atomic Energy Agency. As for the long pulse production of high-current negative ions for JT-60SA ion source, the pulse durations have been successfully increased from 30 s at 13 A on JT-60U to 100 s at 15 A by modifying the JT-60SA ion source, which satisfies the required pulse duration of 100 s and 70% of the rated beam current for JT-60SA. This progress was based on the R&D efforts for the temperature control of the plasma grid and uniform negative ion productions with the modified tent-shaped filter field configuration. Moreover, the each parameter of the required beam energy, current and pulse has been achieved individually by these R&D efforts. The developed techniques are useful to design the ITER ion source because the sustainment of the cesium coverage in large extraction area is one of the common issues between JT-60SA and ITER. As for the long pulse acceleration of high power density beams in the MeV accelerator for ITER, the pulse duration of MeV-class negative ion beams has been extended by more than 2 orders of magnitude by modifying the extraction grid with a high cooling capability and a high-transmission of negative ions. A long pulse acceleration of 60 s has been achieved at 70 MW/m$$^{2}$$ (683 keV, 100 A/m$$^{2}$$) which has reached to the power density of JT-60SA level of 65 MW/m$$^{2}$$.

JAEA Reports

Homogeneity confirmation test of bituminized products

Kinoshita, Junichi; Endo, Masayuki; Uesaka, Takahiro

JAEA-Testing 2012-003, 29 Pages, 2012/11

JAEA-Testing-2012-003.pdf:2.95MB

The comparatively high level liquid radioactive wastes generated from the nuclear facilities in the Nuclear Science Research Institute of JAEA have been treated by the bituminization system. In the future, bituminized products could be disposed of as homogeneously solidified products, if their qualities would meet with the technical standards of homogeneously solidified products which are stipulated in nuclear regulatory law. In this report, we summarized the measurement results of the density and radioactivity of solidified products in order to get basic data for future disposal.

JAEA Reports

Integrity evaluation of removable lid type shielded container

Uesaka, Takahiro; Kozawa, Masachiyo; Matsumoto, Junko; Endo, Masayuki; Kinoshita, Junichi; Suzuki, Takeshi; Suzuki, Hisao; Morishita, Satoru; Sakamoto, Yu

JAEA-Technology 2012-015, 29 Pages, 2012/06

JAEA-Technology-2012-015.pdf:3.22MB

In Japan Atomic Energy Agency Nuclear Science Research Institute waste treatment building No.2 treat intermediate-level solid waste. Solid wastes are reduced in volume by compaction. They are then canned in stainless can, which are subsequently put in 200-liter concrete-lined drums or 1-m$$^{3}$$ concrete containers, filled with concrete. To prepare for disposal in future, be able to make fit with the technical standard of waste package, we were asked to change the lid type shielded container. Therefore due to the change of lid type shielded container, we confirmed integrity of it with evaluation of close volt by drop analysis, evaluation of shielding, and drop test with a prototype model.

Journal Articles

Neutron energy spectra at 180$$^{circ}$$ from 140 MeV proton incident reactions

Iwamoto, Yosuke; Satoh, Daiki; Nakane, Yoshihiro; Nakashima, Hiroshi; Endo, Akira; Sakamoto, Yukio; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; Tamii, Atsushi*; et al.

Journal of the Korean Physical Society, 59(2), p.1753 - 1756, 2011/08

 Times Cited Count:2 Percentile:20.2(Physics, Multidisciplinary)

Neutron production cross sections of carbon and iron targets for 140 MeV proton at 180$$^{circ}$$ were measured at the RCNP cyclotron facility. The neutron energy spectra were obtained by using the time-of-flight technique in the energy range above 1 MeV. The results of carbon and iron targets were compared with experimental data for 113 MeV (p,xn) reactions at 150 deg by Meier et al. Our data gave good agreements with them in spite of different incident energies and angles. Calculations were performed with different intranuclear cascade models (Bertini, ISOBAR, and JQMD) implemented in the PHITS code. Calculated results with the ISOBAR and JQMD models roughly agreed with the experimental data for iron targets, although Bertini could not reproduce the high energy neutrons above 10 MeV.

Journal Articles

Experimental method for neutron elastic scattering cross-section measurement in intermediate energy region at RCNP

Satoh, Daiki; Iwamoto, Yosuke; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; Sanami, Toshiya*; Sato, Tatsuhiko; Endo, Akira; Sakamoto, Yukio; Nakane, Yoshihiro; et al.

Progress in Nuclear Science and Technology (Internet), 1, p.20 - 23, 2011/02

An experimental method and data processing procedure have been developed for the measurement of neutron elastic scattering cross sections in intermediate energy region above 100 MeV. The data were obtained at Research Center for Nuclear Physics (RCNP) in Osaka University by utilizing a $$^{7}$$Li(p,n) quasi-monoenergetic neutron source and Time-of-Flight (TOF) technique.

Journal Articles

Measurement of neutron elastic scattering cross sections for carbon at 134 MeV

Satoh, Daiki; Iwamoto, Yosuke; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; Sato, Tatsuhiko; Endo, Akira; Sakamoto, Yukio; Nakane, Yoshihiro; Nakashima, Hiroshi; et al.

Radiation Measurements, 45(10), p.1159 - 1162, 2010/12

 Times Cited Count:1 Percentile:10.01(Nuclear Science & Technology)

Elastic neutron-scattering cross sections for carbon nucleus have been measured by using 134-MeV monoenergetic neutron beam in Research Center for Nuclear Physics (RCNP), Osaka University. The measured angles were set at 6$$^{circ}$$, 8$$^{circ}$$, and 15$$^{circ}$$ in laboratory system. The liquid organic scintillators, whose size is 12.7 cm in diameter and 12.7 cm in thickness, were mounted at each angle as neutron detector. In the off-line analysis, the events of elastic-neutron scattering were extracted on basis of the Time-of-Flight (TOF) information. The results were compared with the data measured by the groupe of U.C. Davis with a recoil proton spectrometer and the evaluations of the nuclear data libraries, JENDL/HE-2007 and ENDF/B-VII.0. Our results show a good agreement with the data of U.C. Davis. This indicates that our experimental method based on the TOF teqnique is appropriate to the measurement of elastic neutron-scattering cross section in this energy region. In addition, we exhibit that the data of ENDF/B-VII.0 represent the experimental data, but JENDL/HE-2007 underestimates about 30$${%}$$ in the forward angle region.

Journal Articles

Measurements and Monte Carlo calculations of neutron production cross-sections at 180$$^{circ}$$ for the 140 MeV proton incident reactions on carbon, iron, and gold

Iwamoto, Yosuke; Satoh, Daiki; Hagiwara, Masayuki*; Yashima, Hiroshi*; Nakane, Yoshihiro; Tamii, Atsushi*; Iwase, Hiroshi*; Endo, Akira; Nakashima, Hiroshi; Sakamoto, Yukio; et al.

Nuclear Instruments and Methods in Physics Research A, 620(2-3), p.484 - 489, 2010/08

 Times Cited Count:7 Percentile:51.7(Instruments & Instrumentation)

The neutron production cross sections of carbon, iron, and gold targets with 140 MeV protons at 180$$^{circ}$$ were measured at the RCNP cyclotron facility. The time-of-flight technique was used to obtain the neutron energy spectra in the energy range above 1 MeV. The carbon and iron target results were compared with the experimental data from 113 MeV (p,xn) reactions at 150$$^{circ}$$ reported by Meier et al. Our data agreed well with them in spite of different incident energies and angles. Calculations were then performed using different intra-nuclear cascade models (Bertini, ISOBAR, and JQMD) implemented with PHITS code. The results calculated using the ISOBAR and JQMD models roughly agreed with the experimental iron and gold target data, but the Bertini could not reproduce the high energy neutrons above 10 MeV.

Journal Articles

The H-Invitational Database (H-InvDB); A Comprehensive annotation resource for human genes and transcripts

Yamasaki, Chisato*; Murakami, Katsuhiko*; Fujii, Yasuyuki*; Sato, Yoshiharu*; Harada, Erimi*; Takeda, Junichi*; Taniya, Takayuki*; Sakate, Ryuichi*; Kikugawa, Shingo*; Shimada, Makoto*; et al.

Nucleic Acids Research, 36(Database), p.D793 - D799, 2008/01

 Times Cited Count:51 Percentile:71.37(Biochemistry & Molecular Biology)

Here we report the new features and improvements in our latest release of the H-Invitational Database, a comprehensive annotation resource for human genes and transcripts. H-InvDB, originally developed as an integrated database of the human transcriptome based on extensive annotation of large sets of fulllength cDNA (FLcDNA) clones, now provides annotation for 120 558 human mRNAs extracted from the International Nucleotide Sequence Databases (INSD), in addition to 54 978 human FLcDNAs, in the latest release H-InvDB. We mapped those human transcripts onto the human genome sequences (NCBI build 36.1) and determined 34 699 human gene clusters, which could define 34 057 protein-coding and 642 non-protein-coding loci; 858 transcribed loci overlapped with predicted pseudogenes.

JAEA Reports

Development of resistance welding process (4); Preparation of pressuring enclosed creep test specimen of 7A mateial)

Endo, Hideo; Seki, Masayuki; ; *; *

JNC TN8410 2001-004, 45 Pages, 2001/02

JNC-TN8410-2001-004.pdf:6.53MB

(1)Purpose. Mechanical strength in the position welded by resistance welding system was examined in 1999. The test specimens were destroyed in the welding position in a shorter time than expected in the creep tsst. Therefore, test specimens were prepared to evaluate the cause of destruction. (2)Procedure. Inner-pressure enclosed creep test specimens were prepared by resistance welding method. Cladding material with low deviation of thickness and high re-crystallization rate was used. Heat treatment after resistance welding was performed to remove the influence of residual stress and the precipitation of carbides. (3)Summary of result. (a)Before preparation of specimens, the welding condition was fixed. Three test specimens were prepared. Two specimens without heat treatment were transported to MMS in Oarai Engineering Center on Aug, 4, 2000. One specimen with heat treatment was transported to MMS after evaluating the residual stress to get optimum heat treatment condition. (b)Specimens were prepared with welding end plugs to both ends of ferritic ODS cladding. Enclosing sides were welded with highly strong Ferritic/Martensitic steel end plugs. The other sides were welded with ferritic ODS end plugs. (3)Some kinds of electrical wave data were obtained during performing welding. position was evaluated with supersonic detector after performing welding. (4)Mechanical strength of welding position in high temperature 800$$^{circ}$$C was confirmed to be equal to or larger than that of cladding material. (4)Conclusion. The highly qualified specimens in the present were successfully prepared.

JAEA Reports

Development of resistance welding process; Manufacture of test specimens for ODS steel strength evaluation

Endo, Hideo; Seki, Masayuki; ; *; *

JNC TN8410 2000-007, 89 Pages, 2000/03

JNC-TN8410-2000-007.pdf:6.28MB

(1)Outline of examination. Various test specimens were made to evaluate and confirm the weld strength properties of the oxide dispersion strengthened (ODS) cladding tube material (martensitic and ferritic steel), which had been manufactured in JFY 1997. The examination consisted of tensile tests (RT,650$$^{circ}$$C, 700$$^{circ}$$C, 800$$^{circ}$$C), internal pressure creep tests, internal pressure burst tests, and a rapid heating burst tests. (2)Examination results. The results of the tensile tests are as follows: (ferritic and martensitic) (a)All test specimens from RT to 700$$^{circ}$$C failed in the tube. The weld zones had not failed. (b)The test specimens at 800$$^{circ}$$C failed in the weld zones. There was little elongation. (ferritic) (a)The weld zone had fine grain structure and carbide precipitates. (martensitic) (a)Carbide had precipitated in the weld zone. From these results, the strength of weld zone decreased extremely at temperatures exceeding the endurance limit (700$$^{circ}$$C) All of the internal pressure burst test specimens and the rapid heating burst test specimens failed in the tube and not the weld zone. (3)The quality assurance method of the test specimens. The weld reliability of the test specimens were confirmed by the process control of the welding conditions, by using control test specimens, and ultrasonic testing. Confirmation of the process control of the welding conditions; current wave, the voltage waveform, the accelerogram, and the displacement ripple in the welding process was recorded to assure an abnormal value had not occurred. (Process control of welding condition) The results the current waveform, voltage waveform, accelerogram, and the displacement waveform were excellent. (test specimens) The weld joint was excellent based on metallography examination. (Ultrasonic testing) The length of the weld joint was measured and found to be adequate. The reliability the weld joint can be assured by using the above-mentioned method.

JAEA Reports

None

Endo, Hideo; Seki, Masayuki; ; *; *; *

JNC TN8430 2000-002, 30 Pages, 1999/12

JNC-TN8430-2000-002.pdf:1.62MB

None

JAEA Reports

JOYO 75MWt Start-up test report; PT-12 Heat transfer characteristics of IHX and DHX

Doi, Motoo*; Endo, Masayuki*; *; *; *; Wada, Hozumi*; Hirose, Tadashi*

PNC TN941 80-65, 269 Pages, 1980/05

PNC-TN941-80-65.pdf:48.51MB

The purpose of this test is to confirm that the heat transfer characteristics of the intermediate heat exchangers (IHX) and the dump heat exchangers (DHX) satisfy their design values. Each primary and secondary heat transport systems has two loops (A&B) and each secondary loop has two DHX's as terminal heat exchangers. The IHX/DHX heat transfer characteristics are measured under normal steady-state operating conditions (at 25, 40, 50, 65 and 75MWt), and also under special steady-state conditions (low sodium temperature, low secondary sodium flow rate) The major test results were : (1)The heat transfer coeffients of the IHX's and the DHX's measured in the reactor power range of 50 to 75 MWt closely matched predicted values. (2)The pressure drop in the DHX air flow, duct based on measured blower outlet pressure was less than the predicted value. This report presents the results of these plant tests.

JAEA Reports

Experimental fast reactor "JOYO" power-up test report; Power coefficient (NT-34)

*; Endo, Masayuki*; Sekiguchi, Yoshiyuki*

PNC TN941 80-06, 83 Pages, 1980/01

PNC-TN941-80-06.pdf:5.28MB

This report describes the results of the power coefficient test (NT-34) that was planned and performed as a part of the power-up testing of the Experimental Fast Reactor "JOYO". The purpose of this test is to measure the reactivity chauge against the power increase (power coefficient) by measuring the reactor thermal power and excess reactivity at steps of the power ascension procedure. This testing was made from July through August in 1978, and the followings were confirmed. (1)The power coefficient was negative in all power range through 50MW rated power, and could be fitted with good reproducibility as follows. Power coefficient f$$_{p}$$ (%$$Delta$$K/K/MW) = -5.93 $$times$$ 10$$^{-5}$$P-6.05 $$times$$ (10$$^{-3}$$. P: Reactor thermal Power (MW) for 11MW ≦ P ≦ 53MW. The power coefficient was linear against the powar and became less negative with range 10MW (-6.6$$times$$10$$^{-3}$$%$$Delta$$K/K/MW) through 50MW (-9.0$$times$$10$$^{-3}$$ %$$Delta$$K/K/MW). (2)The experimental error was from +4.6% to -9.7%, and the dominant parts were the systematic errors. Particularly, the maximum error was derived from the difference of the thermal expansion between the extension pipes of the control rods and the reactor vessel. The error range was biased to the negative direction because the control rod worth used in this testing was seemed to be a few percent larger than the real worth by reasons of the change of the shadowiug effect, the change of the core fuel arrangement and the burn-up of control rods. (3)There was no significant difference between the results of the power ascent and descent. The reactor attained enough equilibrium of reactivity and thermal condition within about 20 minutes.

JAEA Reports

Experimental fast reactor "JOYO" power-up test report; Thermal power calibratioa (PT-11)

*; Endo, Masayuki*; *; *; *; Sekiguchi, Yoshiyuki*

PNC TN941 79-179, 198 Pages, 1979/10

PNC-TN941-79-179.pdf:5.09MB

This report describes the results of the thermal power calibration test (PT-11) that was planned and performed as part of the power-up testing of the Experimental Fast Reactor "JOYO". The purpose of this test is to calibrate the Power Range Monitors (PRM) and Intermediate Range Monitors (IRM) by measuring the reactor thermal power at several levels from low power through the rated power of 50 MWt. The reactor thermal power was determined by measuring the inlet and outlet temperature and the flow rate of the primary main coolant. After this procedure, PRM and IRM were adjusted to coincide with the reactor thermal power by regulating the electronic amplifiers. Thes testing was made from April through August 1978, and followings were confirmed. (1)The PRM indicators show good linearity with the reactor thermal power. (2)The PRM indicators overlap with the IRM indicators over more than three decades. (3)The PRM indicators changes depending on the operating histry of the reactor. The PRM indicators is lower than the reactor thermal power immediately after start-up. Then that increases gradually and comes to stable in about one week after start-up. The maximum drifting value is about 6 per cent.

JAEA Reports

Isothermal reactivity coefficient of JOYO reactor

Hirose, Tadashi*; *; Nanashima, Takeshi*; *; *; Endo, Masayuki*

PNC TN941 79-119, 31 Pages, 1979/08

PNC-TN941-79-119.pdf:0.96MB

The isothermal reactivity coefficient of JOYO reactor was measured for the minimum critical core configuration and for the initial power up core configuration. The isothermal reactivity coefficient was obtained at every 10$$^{circ}$$C increase or decrease of primary coolant temperature by measuring excess reactivity of the reactor core. The average rate of sodium temperature, change was about $$pm$$6$$^{circ}$$C/hr. The temperature dependency of latch position and hold position of regulating rods was also investigated, which had an infuluence on the critical point. Results are as follows; (1)The measured value of isothermal reactivity coefficient for 64 (minimum critical mass core) and 70 (Initial core) core sub-assemblies were -3.67 $$times$$10$$^{-3}$$ %$$Delta$$K/K/$$^{circ}$$C and -3.77$$times$$10$$^{-3}$$%$$Delta$$K/K/$$^{circ}$$C respectively which were in good ageement with design value of -3.63 $$times$$10$$^{-3}$$%$$Delta$$K/K/$$^{circ}$$C. (2)Analysed value for 70 core sub-assemblies configulation was -3.76 $$times$$10$$^{-3}$$%$$Delta$$K/K/$$^{circ}$$C (analysed by CITATION code with JFSVII micro cross-section).

32 (Records 1-20 displayed on this page)