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Cs activity in spent nuclear fuel with calculated detector response functionSato, Shunsuke*; Nauchi, Yasushi*; Hayakawa, Takehito*; Kimura, Yasuhiko; Kashima, Takao*; Futakami, Kazuhiro*; Suyama, Kenya
Journal of Nuclear Science and Technology, 60(6), p.615 - 623, 2022/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)A new non-destructive method for evaluating Cs activity in spent nuclear fuels was proposed and experimentally demonstrated for physical measurements in burnup credit implementation. Cs activities were quantified using gamma ray measurements and numerical detector response simulations without reference fuels, in which Cs activities are well known. Fuel samples were obtained from a lead use assembly (LUA) irradiated in a commercial pressurized water reactor (PWR) up to 53 GWd/t. Gamma rays emitted from the samples were measured using a bismuth germinate (BGO) scintillation detector through a collimator attached to a hot cell. The detection efficiency of gamma rays with the detector was calculated using the PHITS particle transport calculation code considering the measurement geometry. The relative activities of 
Cs, Cs, and 
Eu in the sample were measured with a high-purity germanium (HPGe) detector for more accurate simulations of the detector response for the samples. The absolute efficiency of the detector was calibrated by measuring a standard gamma ray source in another geometry. Cs activity in the fuel samples was quantified using the measured count rate and detection efficiency. The quantified Cs activities agreed well with those estimated using the MVP-BURN depletion calculation code.
Satoh, Daiki; Sato, Tatsuhiko; Endo, Akira; Matsufuji, Naruhiro*; Sato, Shinji*; Takada, Masashi*; Ishibashi, Kenji*
Nuclear Science Symposium Conference Record, 2005 IEEE, Vol.3, p.1288 - 1290, 2005/10
The response functions of a BC501A liquid organic scintillator have been measured for incidence of various charged particles to investigate the relationship between the kinetic energy of the charged particles and the light output of BC501A. The experiment was performed at Heavy-Ion Medical Accelerator in Chiba (HIMAC) utilizing spallation reactions by heavy ion bombardment on a graphite target. Charged particles incidental on BC501A were identified with the two-dimensional scatter plot of the time-of-flight and the light output. The light output of the BC501A scintillator was deduced as a function of the kinetic energy of the charged particles, and was compared with the semi-empirical formula. While the experimental data showed a good agreement with the formula for proton and deuteron, the data gave slightly larger values compared with the systematic trend for alpha particle.
Kobayashi, Tetsuya; Chishiro, Etsuji; Suzuki, Hiroyuki*; Anami, Shozo*; Yamaguchi, Seiya*; Michizono, Shinichiro*; Kawamura, Masato*; Fukui, Yuji*; Fang, Z.*
Proceedings of 2nd Annual Meeting of Particle Accelerator Society of Japan and 30th Linear Accelerator Meeting in Japan, p.320 - 322, 2005/07
Total System of 324MHz-Low Level RF Control for J-PARC Linac was produced and its performance study was done. In this system, in order to stabilize the Klystron output and to compensate the linearity of that, an analog feedback control system is adopted. The response function including phase characteristic (vector locus) of this feedback system was obtained by means of measurement. From this result the prospect for the transient analysis is discussed.
Satoh, Daiki; Sato, Tatsuhiko; Endo, Akira; Yamaguchi, Yasuhiro; Takada, Masashi*; Ishibashi, Kenji*
AIP Conference Proceedings 769, p.1680 - 1683, 2005/05
Response function of liquid organic scintillators is essential to derive the accurate neutron spectrum. Experimental data above 100 MeV, however, are very scarce. The existing Monte Carlo codes, SCINFUL and CECIL, are often used for estimation of the response function instead of the experimental data. These codes are known to reproduce well the response function for incidences below 100 MeV. Unfortunately, the codes are not applicable to the calculation in the higher energy region. In order to determine the response functions above 100 MeV, a new Monte Carlo code, designated as SCINFUL-QMD, has been developed. In the comparison with the experimental data up to 800 MeV, the validation of SCINFUL-QMD was confirmed. The results of SCINFUL-QMD agreed with the experimental data better than those of other calculation codes.
Satoh, Daiki; Sato, Tatsuhiko; Endo, Akira; Yamaguchi, Yasuhiro; Takada, Masashi*
NIRS-M-180, p.263 - 264, 2005/05
Response functions of NE213 liquid organic scintillator have been measured to develop a dose assessment method for high-energy neutrons. Spallation reactions by 800 MeV/u Si ions and 400 MeV/u C ions incident into thick carbon targets were utilized for the production of high-energy neutrons. Kinetic energies of neutrons were determined by the time-of-flight (TOF) method. 
-ray and charged particle events were eliminated from experimental data in off-line analysis. The measured response functions were used for validation of the simulation by the SCINFUL-QMD code, which is utilized for calculation of the G-function that converts the scintillator response to neutron dose. It was found from the results that SCINFUL-QMD has a good ability to reproduce the response functions.
Endo, Akira; Kim, E.; Yamaguchi, Yasuhiro
JAERI-Data/Code 2001-027, 62 Pages, 2001/10
JAERI-Data-Code-2001-027.pdf:2.05MB
SCINFUL has been used to calculate response functions of organic scintillators for high-energy neutron spectroscopy. However, the applicability of SCINFUL is limited to the calculations for cylindrical NE213 and NE110 scintillators. In the present study, SCINFUL-CG was developed by introducing a geometry specifying function and high-energy neutron cross-section data into SCINFUL. The geometry package MARS-CG, the extended version of the CG (Combinatorial Geometry), was programmed into SCINFUL-CG to express various geometries of detectors. Neutron spectra in the regions specified by the CG can be evaluated by the track length estimator. The cross section data of silicon, oxygen and aluminum for neutron transport calculation were incorporated up to 100MeV using the data of LA150. Validity of SCINFUL-CG was examined by comparing calculated results with those by SCINFUL and MCNP and experimental data. SCINFUL-CG can be used for the designs of high-energy neutron spectrometers and neutron monitors using the organic scintillators. The present report is a user's manual of SCINFUL-CG.
Kinase, Sakae; Noguchi, Hiroshi
Radiation Protection Dosimetry, 93(4), p.341 - 345, 2001/00
Times Cited Count：0 Percentile：0.01(Environmental Sciences)no abstracts in English
Kinase, Sakae; Yoshizawa, Michio; Kuwabara, Jun; Noguchi, Hiroshi
KEK Proceedings 2000-20, p.31 - 40, 2000/12
no abstracts in English
-ray spectroscopic methodsFurutaka, Kazuyoshi
JNC TN8400 2000-028, 70 Pages, 2000/10
JNC-TN8400-2000-028.pdf:1.71MB
This report describes the study done by the author as a postdoctoral research associate at Japan Nuclear Cycle Development Institute. This report is divided into two parts: improvements in accuracy in determination of thermal neutron capture cross sections, and improvements in accuracy of photo-nuclear absorption cross section measurements using the HHS. (1)In the measurements of thermal neutron capture cross sections using an activation method, accuracies of the final results attained are limited by (1) accuracy of -ray peak detection efficiencies, and (2) accuracies of -ray emission probabilities. In this study; to determine thermal neutron capture cross sections more accurately, the following researches have been done using a newly developed three-dimensional coincidence measurement system: (1)accurate determination of -ray standard sources using a - coincidence method, for precise calibration of -ray peak detection efficiency, and (2) development of a 
- coincidence measurement system using a plastic scintillation detector as a -ray detector, for the determination of -ray emission probabilities of short-lived nuclides, and measurement of -ray emission probabilities of 
Tc nuclide using the coincidence system. (2)To transform radioactive nuclides with small thermal neutron capture cross sections, use of photonuclear absorption reaction has been suggested. In order to transform these nuclides efficiently using the reaction, one has to know detailed behavior of the photo-absorption cross sections. In this study, a Monte-Carlo simulation code has been used to create a standard set of -ray response functions of the high-resolution high-energy spectrometer (HHS), to enable reliable analyses of the data obtained by the spectrometer.
Kinase, Sakae
Journal of Nuclear Science and Technology, 37(4), p.413 - 414, 2000/04
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Kinase, Sakae
Nihon Genshiryoku Gakkai-Shi, 42(3), 1 Pages, 2000/03
no abstracts in English
Kinase, Sakae
Journal of Nuclear Science and Technology, 36(10), p.952 - 956, 1999/10
Times Cited Count：3 Percentile：28.69(Nuclear Science & Technology)no abstracts in English
Kaneko, Junichi; Ikeda, Yujiro; Nishitani, Takeo; Katagiri, Masaki
Review of Scientific Instruments, 70(1), p.1100 - 1103, 1999/01
Times Cited Count：22 Percentile：77.39(Instruments & Instrumentation)no abstracts in English
Kinase, Sakae
KEK Proceedings 99-15, p.76 - 81, 1999/00
no abstracts in English
Kinase, Sakae
Journal of Nuclear Science and Technology, 35(12), p.958 - 962, 1998/12
Times Cited Count：5 Percentile：44.27(Nuclear Science & Technology)no abstracts in English
Hayashi, Koji
JAERI-M 93-041, 152 Pages, 1993/03
no abstracts in English
Hayashi, Koji; Shinohara, Yoshikuni; *
Keisoku Jido Seigyo Gakkai Rombunshu, 28(10), p.1216 - 1223, 1992/00
no abstracts in English
;
Progress of Theoretical Physics, 62(6), p.1533 - 1549, 1979/00
Times Cited Count：13no abstracts in English
