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The neutron wavelength resolution, Bragg-edge measurement ability and future prospects regarding the neutron count rate were investigated at AISTANS. The wavelength resolution evaluated by Bragg-edge analysis using an iron powder sample is in reasonably good agreement with calculations at neutron wavelengths of 0.2–0.3 nm. Bragg-edge imaging was also performed on a steel plate sample with distinct regions of BCC and FCC crystallinity, and the different crystal structures were successfully discriminated. In addition, an aluminum sample containing a friction stir spot welding region was also measured and the 200 and 111 Bragg-edges at the two joining areas were observed. However, it was hard to characterize the difference in texture between the two areas. The neutron counting rate for Bragg-edge imaging is expected to increase by approximately a factor 50 in the near future thanks to the planned improvements of the electron beam power and the detection efficiency of the neutron detector.

A new electron accelerator has been designed and is now under construction at AIST, Tsukuba, Japan. The accelerator will be used to produce a pulsed neutron beam for materials analysis. The design maximizes the yield of slow neutrons with high pulse temporal resolution as described in a previous publication [K. Kino et al., Nuclear Inst. and Methods in Physics Research, A 927 (2019) 407–418]. The accelerator is composed of a thermal cathode type electron gun with S-Band buncher/accelerator cavity followed by three, 2.9 m long S-Band acceleration cavities. High power RF is supplied by three klystron units, with klystron No.1 supplying both the electron gun and the 1st cavity, and klystrons No.2 and No.3 connected to the 2nd and 3rd cavities respectively. The design parameters of the accelerator are; pulse rate: 100 Hz, pulse length: 10 μs, electron current: 250 mA, electron energy: 40 MeV. Operating at these parameters a maximum beam power of around 10 kW will be delivered to the water-cooled Ta target for neutron production. In this report we will describe the design and construction of the electron accelerator.

We have designed and been constructing a compact accelerator-driven neutron facility for Bragg edge transmission imaging of structural materials to obtain position dependent crystallographic information. In order to combine a high neutron wavelength resolution, which is especially required for strain measurements, and an intense neutron beam flux at the sample position, which is required for obtaining high quality statistics within practical measurement times, the components of the neutron facility are optimized. To achieve a high wavelength resolution while maintaining an intense neutron beam flux at the sample position, a solid methane decoupled cold moderator at about 20 K coupled with neutron guide tubes is employed. The target–moderator system, especially the moderator thickness was optimized using the Monte-Carlo simulation code PHITS. Neutrons will be produced using a 35-MeV electron accelerator which is currently under construction. The accelerator has a design maximum beam power of 10 kW, a maximum repetition rate of 100 Hz and a maximum pulse width of 10 μ s . The combination of the flight path length of about 8 m and the repetition rate is suitable for efficient Bragg edge measurements. The pulse width of the electron beam is suitable to achieve a high wavelength resolution with the solid methane decoupled moderator. The estimated flux of the neutron beam at the sample position is 1.2 × 104 ∼ 4 . 5 × 104 /cm2/s depending on the usage of super mirror guide tubes. The wavelength resolution at the sample is 0.5 ∼ 0.7% in the wavelength region from 0.3 to 0.4 nm.

Fabry disease is a rare X-linked inherited multisystem disorder resulting from deficiency of the lysosomal enzyme alpha-galactosidase A. Currently, specific therapies, including enzyme replacement therapies, are available for Fabry disease, but clinical trials provide limited information on long-term safety and effectiveness. Agalsidase alfa was approved in Japan in 2006. The post-marketing surveillance study of all patients receiving agalsidase alfa to evaluate its long-term safety and effectiveness as a mandatory condition for its approval had been conducted for 8 years (from February 2007 to March 2015). A total of 493 patients were included in this analysis of safety and effectiveness. The overall mean follow-up period was 3.5 years (range, 0.0-7.9 years). The percentage of patients with adverse drug reactions was 24.5% (121/493) and 12.6% had infusion-related reactions (62/493). In the 256 patients without prior enzyme replacement therapy whose IgG antibody data were available, 17 were IgG antibody positive (6.6%). However, the chronological correlation between seroconversion and the incidence of infusion-related reactions was not clear. The mean brief pain inventory score of the worst pain decreased in patients with moderate and severe pain at baseline. Plasma Gb3 and urine sediment Gb3 in males with classical Fabry disease without prior enzyme replacement therapy significantly decreased. The mean yearly changes in eGFR (mL/min/1.73 m2) ranged from -2.88 to +1.00 in males with classical Fabry disease, from -2.04 to -0.95 in males with non-typical variant and from -2.64 to -1.02 in females. The lower eGFR or the more proteinuria at baseline, the faster the decrease in eGFR of the patients was observed. There was no substantial difference in cardiac parameters (left ventricular mass index, E/A wave ratio, ejection fraction, and QRS duration). In conclusion, agalsidase alfa, 0.2 mg/kg every other week, was well tolerated and controlled the progression of symptoms (especially renal and cardiac) of Fabry disease in adults. Enzyme replacement therapy should be started in Japanese patients before cardiac and/or renal symptoms of Fabry disease develop.

We have constructed a compact accelerator-based neutron facility at the National Institute of Advanced Industrial Science and Technology (AIST) in Japan aiming at development of structural materials of transportation vehicles for weight reduction. The facility consists of electron linear accelerator, neutron source, and a neutron beamline with a measurement hutch. Currently we are commissioning the accelerator and expecting a first neutron beam in 2019.

A quantitative nondestructive Bragg-edge imaging technique for power-storage degradation was developed using commercial prismatic-shaped lithium-ion battery cells. The C or Li atoms/ions column density [cm−2] images for five phases of the negative electrode material (graphite, Li0.04C6, Li0.2C6, Li0.5C6, and Li1.0C6) with a 1 mm spatial resolution were obtained by considering the crystalline orientation for both fresh and fatigue cells. In the fresh cell, most of the graphite was uniformly converted to Li1.0C6 by charging, and in the fatigue cell, the graphite changed to various phases (especially, Li1.0C6 and Li0.5C6) by charging, and their spatial distributions were nonuniform.

Neutron imaging is a powerful tool for observing the internal structure of an object without destroying the object. Neutron imaging (neutron radiography) is a prominent application of neutrons but still requires significant improvements, for example, in sensitivity, resolution, radiation hardness, and handling of neutron imaging detectors. This paper presents the development and the first neutron imaging results of a neutron flat-panel detector (nFPD) based on an In-Ga-Zn-O (IGZO) thin-film transistor (TFT)/photodiode array coupled with a LiF/ZnS scintillator sheet. Direct photo-coupling to the scintillator increases the light collection efficiency. Moreover, unlike lens-coupled neutron cameras, the proposed detector is compact and easy to handle. Owing to the high off-state resistance of IGZO TFTs, their leakage current is lower than that of conventional TFTs, enabling the IGZO TFTs to hold an accumulated charge for a longer period of time and allowing longer exposure times for imaging. This would be a powerful feature for imaging at compact neutron sources with limited flux. This paper reports on the first neutron imaging results with an IGZO nFPD, its performance evaluation, and a demonstration of three-dimensional computed tomography with neutrons.

Given the increased demand for nondestructive inspections of the insides of bulk concrete structures, in this paper, we propose a new transmission imaging system that uses fast neutrons via an accelerator-driven compact neutron source. A key component that we have developed is a pixel-type fast neutron detector that consists of a 4 × 4 array of plastic scintillators with semiconductor photon sensors. Using neutron transmission images obtained with this detector, we have successfully identified a steel bar, a void hole, and water with 300-mm-thick concrete blocks via a RIKEN Accelerator-driven compact Neutron Source (RANS).

The frequency of neutron-induced soft errors is increasing as devices become more integrated and miniaturized. Therefore, it has become more important recently to check reliability of a recovery system from the soft errors in network systems. For accelerated test, first we have examined possibility of the acceleration tests at a compact accelerator-driven neutron source, which is easy to adjust for soft-error tests and which also has low experimental costs. We selected the electron accelerator-driven neutron source at Hokkaido University as the compact accelerator-driven neutron source. We prepared a new target-reflector assembly composed of heavy metals to provide the fast neutrons, and conducted neutron-induced soft-error experiments on network equipments. As a result, we found that an accelerated rate of soft errors was about $10^{{\mathbf {6}}}$ times compared with that of the natural environment. We also investigated network equipment soft-error tolerance, fault detection and backup switching processes. Performing such testing before network equipment is actually deployed is critical for development of future network systems. Hence, the compact accelerator-based neutron source is a very useful tool.

A compact accelerator-driven neutron source has some advantages over a large accelerator facility in terms of accessibility and usability. Recently, the project to develop a non-destructive testing system for nuclear fuels by neutron imaging using a compact accelerator-driven neutron source has launched in Japan. In this project, the traditional neutron radiography and temperature imaging by neutron resonance absorption spectroscopy (N-RAS) have been studied. From the viewpoint of L/D, a high-brightness moderator is desirable for the neutron imaging. In this study, we investigated the dependence of moderator size on the source brightness and the pulse characteristics of the neutron by simulation calculations to design the moderator for imaging using thermal and epithermal neutrons. As a result, the optimal size of the moderator for the neutron imaging was 6∼7 cm in the energy region from 5 meV to 100 eV.

Transmission measurement of a commercial Li-ion battery was performed using the pulsed neutron beam provided by the Japan Spallation Neutron Source. A high position resolution two-dimensional neutron detector recorded the neutrons that went through the battery sample. The transmission spectra for each partitioned area on the battery sample were fitted by a function taking into account the coherent elastic scattering of neutrons on the electrode materials. Using the fitting results, we succeeded in obtaining the charge/discharge images through the quantitative crystal surface densities.

It should be possible to non-destructively estimate nuclide density by analyzing the transmission dips due to the resonance absorption in neutron transmission spectra. In this study performed at the NOBORU instrument in J-PARC/MLF, we evaluated the quality of the neutron resonance transmission measurements and their potential use in the estimation of nuclide density. First, we calculated the emission time distributions of epithermal neutrons by simulation and then fitted the pulse shapes using several kinds of functions to make a response function suitable for the NOBORU instrument. We found that the Cole-Windsor function well reproduced the pulse shape at arbitrary energy. Then, we applied this function to the resonance analysis code REFIT, and found that it was possible to reproduce the resonance shapes. Finally, we performed the transmission measurements at NOBORU and analyzed the resonance dips for Ta, Ag and Cu by the revised REFIT code.

We obtain the transmission image of a commercial lithium ion (Li-ion) battery using a pulsed neutron beam at the beamline 09 of the Materials and Life Science Experimental Facility at the Japan Proton Accelerator Research Complex. The purpose of this study is to improve the performance of the Li-ion battery by nondestructive observation of its charging and discharging. The transmission images for three charge states (3.2 V, 3.7 V, and 4.2 V) reveal differences between these three states, which we attribute to electrolyte migration. The transmission spectra show Bragg edges originating from the electrodes, current collectors, and battery vessel. Although the battery as a whole has the expected relation between the charge accumulation and the quantity of lithium amounts in the positive and negative electrodes, a portion of the battery deviates from this relation, which may imply a position dependent charging in the battery.

The neutron capture cross-section for platinum was measured at J-PARC/MLF/ANNRI. The intense pulsed neutron beam was impinging on a natural platinum foil sample and the emitted prompt γ-rays were detected by a Ge spectrometer. The peak energies of the low energy resonances for natural platinum are consistent with those of the JEFF-3.1.2, RUSFOND2010 and next-JENDL data libraries except for the 20-eV resonance. The resonance cross-sections of the next-JENDL library do not contradict the present measurements within the uncertainty of the absolute value of the present work. We analysed the prompt γ-ray spectrum and found a clear 7921.93 keV peak that originates from the transition from the 196 Pt compound state to its ground state. The neutron capture cross-section for 195 Pt was obtained by choosing events of this peak. The peak energies of most of the low energy resonances are almost consistent with those of the RUSFOND2010 and next-JENDL libraries. However, there was a disagreement for the 20-eV resonance.

The neutron capture cross section of 99 Tc was measured using NaI(Tl) detectors of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) at the Japan Proton Accelerator Research Complex (J-PARC) in the energy range from thermal to the keV energy region. Preliminary results were presented and compared with previous measurements and evaluations.

A fast data acquisition method based on pulse-width analysis was developed for measuring neutron capture cross-sections using an NaI(Tl) detector. The new method was tested by detecting γ-rays from standard γ-ray sources and neutron-induced reactions. Non-linear relation between the γ-ray energy and the pulse width of the detector output signal was studied. The neutron beam experiments were performed using a pulsed neutron beam from a spallation neutron source at the Japan Proton Accelerator Research Complex. Detector-deposited energy spectra were reconstructed from the pulse-width spectra using the parameterized relation between the pulse width and the γ-ray energy. Time response properties of the pulse-width analysis method were compared with the traditional pulse-height analysis method. Detailed analysis of the experimental results demonstrated that the present method was more resistive to intense γ-ray bursts from the spallation neutron source.

Measurements of the neutron capture cross sections of 107Pd were carried out at the Materials and Life Science Experimental Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC). Gamma-rays were detected with an NaI(Tl) spectrometer of the Accurate Neutron–Nucleus Reaction Measurement Instrument (ANNRI). The neutron capture cross sections were determined by the time-of-flight method in the neutron energy region from the thermal to keV energies.

The measurements of the neutron-capture cross sections were performed for the radioactive 107 Pd and stable 105 , 108 Pd nuclei by the time-of flight method using an apparatus called “Accurate Neutron–Nucleus Reaction measurement Instrument (ANNRI)” installed at the neutron Beam Line No.4 of the Materials and Life science experimental Facility (MLF) in the J-PARC. The neutron-capture cross sections of 107 Pd and 105 , 108 Pd have been measured in the low energy region from the thermal to a few hundreds eV. From the measurements, new information was obtained for some resonances of these Pd nuclei.

The cross section of the 237 Np(n, γ ) reaction has been measured at the Japan Proton Accelerator Research Complex (J-PARC). The NaI(Tl) spectrometer installed in the accurate neutron-nucleus reaction measurement instrument (ANNRI) was used for the measurement. The relative cross section was obtained using the neutron spectrum measured by the 10 B(n, α 1 ) reaction. The absolute value of the cross section was deduced by normalizing the relative cross section to the evaluated value in JENDL-4.0 at the first resonance.

The neutron-capture cross sections of 112 Sn and 118 Sn were measured by the time-of-flight method in the energy range from 10 meV to 2 keV with an array of germanium detectors in ANNRI at J-PARC. The preliminary results of the neutron-capture cross sections for 112 Sn and 118 Sn were obtained by normalizing the relative cross sections to the thermal cross section measured by Krane and to the evaluated value of JENDL-4.0 at the 47.05-eV resonance, respectively. Twelve new resonances for 112 Sn were observed, whereas the 21.02-, 40.38- and 166-eV resonances for 112 Sn and the 289-eV resonance for 118 Sn which are listed on JENDL-4.0 and/or ENDF/B VII.1 were not observed. The prompt γ -ray distributions gated at the 112 Sn and 118 Sn resonances were obtained. Twenty-three new prompt γ -ray emissions were observed in the 112 Sn (n, γ ) reactions.

We can non-destructively obtain an image of nuclide/isotope distribution or temperature in a substance by analyzing the dips due to the resonance absorption in a neutron transmission spectrum. The observed transmission spectra are expressed by convolution of intrinsic resonance cross section and neutron pulse shape, namely the emission time distribution of neutrons emitted from a moderator. Therefore, the pulse shape should be reproduced at arbitrary energy by a synthetic function for performing the quantitative resonance analysis. We have found that the Cole-Windsor function reproduced well the pulse shape of the instrument at J-PARC (Japan Proton Accelerator Research Complex) neutron source and succeeded in evaluating nuclide density of some samples quantitatively by analyzing transmission resonance spectra. On the other hand, the function expressing the pulse shape of a thermal neutron source at Hokkaido University has not been found. Therefore, we have calculated the pulse shape of epithermal neutrons by Monte-Carlo simulation and fitted the pulse shape using several kinds of function. We found that the Cole-Windsor function also was the best function for reproducing the pulse shape of the source. Moreover, we implemented it to the resonance analysis code and calculated the resonance transmission spectra of some nuclide to evaluate the capability for resonance analysis at Hokkaido University source.

The cross-section of the 237Np reaction has been measured in the energy range from 10 meV to 1 keV using the ANNRI-NaI(Tl) spectrometer at the Japan Proton Accelerator Research Complex (J-PARC). The cross-section was obtained relative to that of the 10B reaction. The absolute value of the cross-section was deduced by normalizing the relative cross-section to the evaluated value of JENDL-4.0 at the first resonance. The thermal cross-section was obtained to be ( ) b. The Maxwellian-averaged cross-section for meV was derived as ( ) b by referring the cross-section below 10 meV from JENDL-4.0. These results lead to the Westcott's g-factor of .

We measured two-dimensional transmission spectra of pulsed neutron beams for a Japanese sword sample. Atom density, crystalline size, and preferred orientation of crystals were obtained using the RITS code. The position dependence of the atomic density is consistent with the shape of the sample. The crystalline size is very small and shows position dependence, which is understood by the unique structure of Japanese swords. The preferred orientation has strong position dependence. Our study shows the usefulness of the pulsed neutron transmission method for cultural metal artifacts.

Pulsed neutron imaging methods provide information on crystallographic structure, magnetic field, elemental composition, hydrogen bound state and other material features. Such methods have been expected to be a powerful complement to the traditional imaging method. Data analysis codes, detectors and new applications are being developed in Japan, and a new imaging beam line is being constructed at J-PARC. Here, recent progress in Japanese research on pulsed neutron imaging is presented, and a design for construction of the new imaging beam line is reported.

The functioning of an arteriovenous fistula (AVF) used for vascular access during hemodialysis has been assessed mainly by dilution methods. Although these techniques indicate the immediate recirculation rate, the results obtained may not correlate with Kt/V. In contrast, the clearance gap (CL-Gap) method provides the total recirculation rate per dialysis session and correlates well with Kt/V. We assessed the correlation between Kt/V and CL-Gap as well as the change in radial artery (RA) blood flow speed in the fistula before percutaneous transluminal angioplasty (PTA) in 45 patients undergoing continuous hemodialysis. The dialysis dose during the determination of CL-Gap was 1.2 to 1.4 Kt/V. Patients with a 10% elevation or more than a 10% relative increase in CL-Gap underwent PTA (n = 45), and the values obtained for Kt/V and CL-Gap before PTA were compared with those obtained immediately afterward. The mean RA blood flow speed improved significantly (from 52.9 to 97.5cm/sec) after PTA, as did Kt/V (1.07 to 1.30) and CL-Gap (14.1% to -0.2%). A significant correlation between these differences was apparent (r = -0.436 and p = 0.003). These findings suggest that calculating CL-Gap may be useful for determining when PTA is required and for assessing the effectiveness of PTA, toward obtaining better dialysis.

Using pulsed neutron imaging, the distributions of absolute values of nuclide densities and temperatures of the sample can be estimated. However, the images obtained by the pulsed neutron imaging have a low spatial resolution because of the performance limitations of the detector. On the other hand, X-ray radiograms have higher spatial resolution compared with the neutron images. To obtain higher-resolution neutron images, we developed the resolution enhancement method for neutron images by cooperating with the X-ray radiography. The resolution enhancement method consists of the image alignment and the mapping methods. As a first step, we tried mapping neutron transmission image into the X-ray image.

The neutron neutron-capture cross cross-sections of 244Cm and 246Cm were measured by the time-of-flight method in the energy range of 1–300 300 eV with an array of large germanium detectors in the Accurate Neutron-Nucleus Reaction measurement InstrumentANNRI at Material and Life Science Experimental Facility (MLF) of the Japan Proton Accelerator Research ComplexJ-PARC/MLF. The 244Cm resonances at around 7.7 and 16.8 8 eV and the 246Cm resonances at around 4.3 and 15.3 3 eV were observed in the capture reactions for the first time. The uncertainties of the obtained cross cross-sections are 5.8% at the top of the first resonance of 244Cm and 6.6% at that of 246Cm. The rResonance analyses were performed for low-energy ones using the code SAMMY. The prompt γ-ray spectra of 244Cm and 246Cm were also obtained. Eight and five new prompt γ-ray emissions were observed in the 244Cm(n, γ) and 246Cm(n, γ) reactions, respectively.

A pixel-type position-sensitive Li-glass neutron detector has been developed in the Hokkaido University and applied to neutron transmission measurements for obtaining wavelength-dependent neutron images due to its high counting rate. This detector will be applied to monitor the time spectrum of the pulsed neutron beam for the neutron capture cross-section measurements at the Japan Spallation Neutron Source (JSNS). It turned out that the gamma-rays which were accompanied by neutron transmission measurements may be also detected by this detector and may affect wavelength-dependent neutron intensity. We have therefore studied experimentally and numerically the detector efficiency for gamma-rays as a function of photon energy. We have also investigated some practical methods to reduce the effects of gamma-rays on the position-sensitive Li-glass neutron detector by using the Hokkaido University 45MeV LINAC neutron source.

We performed simulation calculations of neutron transmission spectra for minor actinide and long-lived fission product samples with pulsed neutron beams produced by the two neutron sources: the Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI) at the Japan Spallation Neutron Source (JSNS) that provides the world's most intense pulsed neutron beam, and a compact accelerator-driven neutron source. For the both cases, we assumed to put a neutron detector at downstream of the sample and took into account the detector efficiency of neutrons to estimate statistics. ANNRI gives high statistical neutron transmission spectra. Therefore, it is useful for obtaining the total cross-section data through the transmission spectra for the small amount sample or the small cross-section regions between the resonances not only for monitoring the beam condition during the neutron capture-reaction measurements at ANNRI. On the other hand, a compact neutron source shows transmission spectra at resonances with less deformation by its single bunch beam. This implies that the compact neutron source is useful for assigning the resonances and the resonance analysis.

Primary gamma rays from the neutron capture resonances for 99Tc were measured at the J-PARC/ANNRI. The transition pattern from the first resonance is similar to that from the capture reaction of thermal neutrons. On the other hand, transition patterns from the higher energy resonances are completely different, and there is no clear dependence on the spin-parities of the resonances.

A fast data acquisition method based on pulse width analysis was developed for γ -ray spectroscopy with an NaI(Tl) detector. The new method was tested in experiments with standard γ -ray sources and pulsed neutron beam from a spallation neutron source. Pulse height spectra were successfully reconstructed from pulse width distribution by use of an energy calibration curve. The 197 Au(n, γ ) 198 Au cross section was measured by this method to test the viability. The obtained experimental cross section showed a good agreement with a calculation using the resonance parameters of JENDL-4.0.

Measurement of Neutron Capture Cross Section Ratios of Cm Resonances Using NNRI Shinji GOKO a , Atsushi KIMURA a , Hideo HARADA a , Masumi OSHIMA a , Masayuki OHTA a , Kazuyoshi FURUTAKA a , Tadahiro KIN a , Fumito KITATANI a , Mitsuo KOIZUMI a , Shoji NAKAMURA a , Yosuke TOH a , Masayuki IGASHIRA b , Tatsuya KATABUCHI b , Motoharu MIZUMOTO c , Yoshiaki KIYANAGI c , Koichi KINO c , Michihiro FURUSAKA c , Fujio HIRAGA c , Takashi KAMIYAMA d , Jun-ichi HORI d , Toshiyuki FUJJI d , Satoshi FUKUTANI d & Koichi TAKAMIYA a a Nuclear Science and Engineering Directorate , Japan Atomic Energy Agency , Tokaimura, Naka-gun, Ibaraki , 319-1195 , Japan b Research Laboratory for Nuclear Reactors , Tokyo Institute of Technology , O-okayama, Meguro-ku, Tokyo , 152-8550 , Japan c Faculty of Engineering , Hokkaido University , Kita 13, Nishi 8, Kita-ku, Sapporo, Hokkaido , 060-8628 , Japan d Research Reactor Institute , Kyoto University , Asashiro Nishi, Kumatori-cho, Sennangun, Osaka , 590-0494 , Japan Published online: 05 Jan 2012.

We measured the energy spectra and spatial distributions of the neutron beam of Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) at the Japan Proton Accelerator Research Complex/Materials and Life Science Experimental Facility (J-PARC/MLF). Our research team designed and built ANNRI to measure nuclear data with high precision. The measurements of the neutron beam were performed on three types of beams provided by ANNRI in the neutron energy range from 1.5 meV to 10 keV. The energy spectra show a typical feature of para-hydrogen moderator, and the absolute intensities almost agree with predictions based on both a simulation calculation of the Japan Spallation Neutron Source (JSNS) and a neutron transmission calculation of the beamline. The available neutron intensities at 21.5 m are 7.5×10 5 , 1.6×10 4 , and 1.1×10 5 n/cm 2 /s in the energy ranges 1.5–25 meV, 0.9–1.1 eV, and 0.9–1.1 keV, respectively, under the 17.5 kW JSNS operation. The measured spatial distributions of the beams formed by three different collimators are consistent with those expected from the collimator-system design of the beamline. The beam sizes in FWHM are about 29, 14, and 11 mm for the three different beam collimators. The edges of the spatial distributions are relatively sharp, enabling us to measure the nuclear data successfully.