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Yamamoto, Masahiko; Kono, Soma; Saegusa, Yu; Kuno, Takehiko; Sekine, Megumi; Inoue, Naoko; Noro, Naoko; Rodriguez, D.; Yamaguchi, Tomoki; Stinett, J.*
Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 10 Pages, 2023/05
The gamma-ray measurement part of the Non-Destructive Assay (NDA) course of safeguards and nuclear material accountancy was developed to focus on gamma-ray measurement allotting two days out of five days. The lectures on the basic characteristics and detection methods and mechanism of gamma-ray detectors were provided as e-learnings which were developed. The part for hands-on exercises were implemented in JAEA facility. Participants have set up each gamma-ray detector, and performed measurements of uranium and the other gamma-ray emitting nuclides. Also, uranium-235 enrichment measurements have been performed. In addition, the participants trained with a handheld gamma-ray spectrometer, HM-5, that is popular for IAEA safeguards as the preparation in the measurement exercise of fresh fuel assemblies in JRR-3, a research reactor facility of JAEA. This paper reports on the development, implementation, and feedback from participants on gamma-ray measurement part of the NDA course.
Yokoyama, Kaoru; Ohashi, Yusuke
Annals of Nuclear Energy, 175, p.109240_1 - 109240_7, 2022/09
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Decommissioning is planned at nuclear facilities that have been discontinued. We examined the evaluation method of uranium radioactivity for concrete waste generated by the decommissioning of nuclear facilities. Since the peaks of Ac-228, Tl-208, and K- 40 are derived from concrete waste, it is difficult to distinguish the 1001 keV peak emitted from the uranium source. We have derived a formula to correct gamma rays from concrete and the environment, and the amount of uranium was quantified. When the weight of concrete waste is about 300 kg, if the weight of uranium is 3 g or more, it can be quantified within a relative error of about 30%. Measurement tests were performed using homogeneous simulated concrete waste. Since uranium contamination is on the concrete surface at the uranium processing facility and small chunks generated by scraping the concrete surface will be stored in a drum and measured, it seems that the test of homogeneous concrete reflects the actual waste.
Wada, Yuki*; Bowers, G. S.*; Enoto, Teruaki*; Kamogawa, Masashi*; Nakamura, Yoshitaka*; Morimoto, Takeshi*; Smith, D.*; Furuta, Yoshihiro*; Nakazawa, Kazuhiro*; Yuasa, Takayuki*; et al.
Geophysical Research Letters, 45(11), p.5700 - 5707, 2018/06
Times Cited Count：30 Percentile：81.84(Geosciences, Multidisciplinary)Tsuchiya, Harufumi; Harada, Hideo; Koizumi, Mitsuo; Kitatani, Fumito; Kureta, Masatoshi; Becker, B.*; Kopecky, S.*; Heyse, J.*; Paradela, C.*; Mondelaers, W.*; et al.
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/12
Neutron Resonance Densitometry (NRD) was developed as a non-destructive assay to quantify U and Pu isotopes in particle-like debris. NRD is composed of neutron resonance transmission analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA) or Prompt Gamma-ray Analysis (PGA). NRCA/PGA in NRD plays a role of identifying impurities in debris under the high-radiation field primarily caused by 
Cs. For this purpose, a novel LaBr
-ray detector employing specific shields has been newly developed. With the developed -ray detector, a demonstration NRCA experiment was performed at a neutron time of flight facility GELINA (Belgium). As a result, samples (Hf, Gd, Ni) placed in a black box that is completely sealed by third party were successfully identified by the experiment. This presentation explains the design concept of the ray detector including its detection principle and details of the demonstration NRCA experiment.
-ray spectra including the Doppler-broadened peak for boron determinationMagara, Masaaki; Yonezawa, Chushiro
Nuclear Instruments and Methods in Physics Research A, 411(1), p.130 - 136, 1998/00
Times Cited Count：24 Percentile：85.15(Instruments & Instrumentation)no abstracts in English
IEEE Transactions on Nuclear Science, NS-31(1), p.316 - 319, 1984/00
no abstracts in English
*; *; *; *; *
JAERI-M 8196, 64 Pages, 1979/05
no abstracts in English
; ;
JAERI-M 6523, 18 Pages, 1976/05
no abstracts in English
Sato, Shunsuke*; Nauchi, Yasushi*; Hayakawa, Takehito; Kimura, Yasuhiko; Suyama, Kenya
no journal, ,
The ray spectrum measurement was conducted for a sample taken from a PWR lead used assembly and photon spectrum data for higher energy region than usual case was obtained. Burnup calculation adopting MVP-BURN code was carried out for the sample and the agreement between experimental data and the calculation results was confirmed.
-ray emitters including 
Cs, 2; Study of the coincidence summing effect taking into account for the thickness of the cylindrical shaped volume sampleYamada, Takashi*; Abe, Takaaki*; Asai, Masato; Yonezawa, Chushiro*; Kakita, Kazutoshi*; Hirai, Shoji*
no journal, ,
The true coincidence summing corrections for cascade rays are usually carried out by using -ray detection efficiencies averaged over whole sample volume. This is not an exact method, but is recognized to be practically useful. However, a recent international comparison experiment suggested that this method provides slightly small correction factors. To solve this problem, we developed a method to calculate the true coincidence summing corrections for cylindrical shaped volume samples by dividing the volume sample into a number of plane samples, calculating the efficiencies for each plane sample with summing corrections, and integrating them over whole sample volume. This method improved the problem of small correction factors.
