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JAEA Reports

Study on molybdenum adsorption properties of alumina-based adsorbents and their application to $$^{99}$$Mo/$$^{rm 99m}$$Tc generators using the (n,$$gamma$$) method (Thesis)

Fujita, Yoshitaka

JAEA-Review 2023-010, 108 Pages, 2023/08

JAEA-Review-2023-010.pdf:6.62MB

$$^{rm 99m}$$Tc (technetium-99m) is the most widely used radioisotope in radiopharmaceutical and is decayed from the parent nuclide $$^{99}$$Mo (molybdenum-99). Most of $$^{99}$$Mo is generated as one of the fission products of uranium, but recently, from the viewpoint of nuclear security and nuclear nonproliferation, a uranium-free $$^{99}$$Mo production method is desired. One such method is the (n,$$gamma$$) method, in which $$^{98}$$Mo is irradiated by neutrons. However, since the specific activity of $$^{99}$$Mo produced by this method is extremely low, it is necessary to improve the Mo adsorption and $$^{rm 99m}$$Tc elution property of alumina (Al$$_{2}$$O$$_{3}$$), which is used as a Mo adsorbent, to apply this method to the $$^{99}$$Mo/$$^{rm 99m}$$Tc generator, a device for separation and concentration of $$^{rm 99m}$$Tc from $$^{99}$$Mo. Therefore, the objective of this thesis is to elucidate the parameters effective for improving the performance of alumina for the practical use of the $$^{99}$$Mo/$$^{rm 99m}$$Tc generator using the (n,$$gamma$$) method, and to contribute to the development of alumina columns that may be applicable to low specific activity $$^{99}$$Mo. In this study, alumina with different starting materials was prepared and its applicability as Mo adsorbent for $$^{99}$$Mo/$$^{rm 99m}$$Tc generator was evaluated. The effects of crystal structure and specific surface area of alumina on Mo adsorption properties were clarified, and the Mo adsorption mechanism was elucidated based on the results of surface analysis of alumina. In addition, $$^{rm 99m}$$Tc elution properties and $$^{rm 99m}$$Tc solution quality were evaluated using MoO$$_{3}$$ irradiated in the Kyoto University Research Reactor (KUR), and a new column shape with potential application to generators was proposed based on the experiment results of alumina columns designed for current generators.

Journal Articles

Production of diagnostic $$^{99}$$Mo/$$^{99m}$$Tc by PWR

Nasu, Takuya*; Fujita, Yoshitaka

Enerugi Rebyu, 42(10), p.15 - 18, 2022/09

no abstracts in English

Journal Articles

Integral experiments of technetium-99 using fast-neutron source reactor "YAYOI"

Nakamura, Shoji; Hatsukawa, Yuichi*; Kimura, Atsushi; Toh, Yosuke; Harada, Hideo

Journal of Nuclear Science and Technology, 58(12), p.1318 - 1329, 2021/12

https://doi.org/10.1080/00223131.2021.1942278
 Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

The present study performed fast-neutron capture cross-section measurement of $$^{99}$$Tc by an activation method using a fast-neutron source reactor "YAYOI" of the University of Tokyo. Technetium-99 samples were irradiated with reactor neutrons using a pneumatic system. Reaction rates of $$^{99}$$Tc were obtained by measuring decay gamma rays emitted from $$^{100}$$Tc. The neutron flux at an irradiation position was monitored with gold foils. The fast-neutron capture cross section of $$^{99}$$Tc at neutron energy of 85 keV was derived as 0.432$$pm$$0.023 barn by using the reaction rates of $$^{99}$$Tc, evaluated cross-section data and the fast-neutron flux spectrum of the YAYOI reactor. The present study agreed with the evaluated nuclear data library JENDL-4.0.

Journal Articles

Thermal-neutron capture cross-section measurement of $$^{237}$$Np using graphite thermal column

Nakamura, Shoji; Endo, Shunsuke; Kimura, Atsushi; Shibahara, Yuji*

KURNS Progress Report 2020, P. 94, 2021/08

https://www.rri.kyoto-u.ac.jp/PUB/report/PR/ProgRep2020/ProgRep2020.html

The present study selected $$^{237}$$Np among radioactive nuclides and aimed to converge a contradiction between reported thermal-neutron capture cross sections. Neutron irradiation was carried out using the graphite thermal column equipped with the Kyoto University Research Reactor. A solution equivalent to 950 Bq order of radioactivity was pipetted out of a $$^{237}$$Np standard solution and dropped onto a fiber filter, which was then dried with an infrared lamp to prepare a $$^{237}$$Np sample. The $$^{237}$$Np sample was quantified using 312-keV gamma ray emitted from $$^{233}$$Pa in a radiation equilibrium with $$^{237}$$Np. To monitor a thermal-neutron flux component at an irradiation position, the $$^{237}$$Np sample was irradiated together with several stable nuclides as neutron flux monitors: $$^{45}$$Sc, $$^{59}$$Co, $$^{98}$$Mo, $$^{181}$$Ta and $$^{197}$$Au. The reaction rate of $$^{237}$$Np was obtained from gamma-ray yields given by $$^{238}$$Np and $$^{233}$$Pa, and then the thermal-neutron capture cross section of $$^{237}$$Np was derived.

Journal Articles

Development of $$^{99}$$Mo/$$^{99m}$$Tc generator for the $$^{99}$$Mo/$$^{99m}$$Tc domestic production

Fukumitsu, Nobuyoshi*; Tsuchiya, Kunihiko; Ariga, Katsuhiko*; Yamauchi, Yusuke*

Isotope News, (742), p.20 - 24, 2016/02

http://www.jrias.or.jp/books/pdf/201602_TRACER_FUKUMITSU_HOKA.pdf

no abstracts in English

JAEA Reports

Measurement and analysis of breeding index in the first mock-up core (XXII-1(65V)) for water-cooled breeder reactor at FCA (Contract research)

Fukushima, Masahiro; Okajima, Shigeaki; Ando, Masaki; Yamane, Tsuyoshi; Kataoka, Masaharu*

JAERI-Research 2005-008, 57 Pages, 2005/03

JAERI-Research-2005-008.pdf:3.49MB

no abstracts in English

Journal Articles

A High-sensitivity, non-destructive trace element analysis

Oshima, Masumi; Toh, Yosuke; Hayakawa, Takehito; Hatsukawa, Yuichi; Shinohara, Nobuo

JAERI-Conf 2001-002, p.532 - 534, 2001/03

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-2001-002-Part1.pdf

no abstracts in English

Journal Articles

Determination of metallic impurities in high-parity type IIa diamond grown by high-pressure and high-temperature synthesis using neutron activation analysis

Kaneko, Junichi; Yonezawa, Chushiro; Kasugai, Yoshimi; Sumiya, Hitoshi*; Nishitani, Takeo

Diamond and Related Materials, 9(12), p.2019 - 2023, 2000/12

https://doi.org/10.1016/S0925-9635(00)00357-5
 Times Cited Count：9 Percentile：47.89(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

A study on improvements in accuracy of nuclear data measurements using $$gamma$$-ray spectroscopic methods

Furutaka, 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 $$gamma$$-ray peak detection efficiencies, and (2) accuracies of $$gamma$$-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 $$gamma$$-ray standard sources using a $$gamma$$-$$gamma$$ coincidence method, for precise calibration of $$gamma$$-ray peak detection efficiency, and (2) development of a $$beta$$-$$gamma$$ coincidence measurement system using a plastic scintillation detector as a $$beta$$-ray detector, for the determination of $$gamma$$-ray emission probabilities of short-lived nuclides, and measurement of $$gamma$$-ray emission probabilities of $$^{100}$$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 $$gamma$$-ray response functions of the high-resolution high-energy spectrometer (HHS), to enable reliable analyses of the data obtained by the spectrometer.

Journal Articles

Simultaneous quantification of 49 trace elements with improved neutron activation analysis

Oshima, Masumi

Isotope News, (553), p.8 - 10, 2000/06

http://ci.nii.ac.jp/naid/10004563376

no abstracts in English

Journal Articles

Measurements of reaction rate ratios as indices of breeding performance in mock-up cores of FCA simulating metallic-fueled LMFBR and MOX-fueled LMFBR

Sakurai, Takeshi; *; *; *

Journal of the Physical Society of Japan, 36(8), p.661 - 670, 1999/08

no abstracts in English

JAEA Reports

Measurement and analysis of breeding indices of $$^{238}$$U capture to $$^{239}$$Pu fission rate ratios and $$^{238}$$U capture to $$^{235}$$U fission rate ratios at fast critical assembly

Sakurai, Takeshi;

JAERI-Research 95-054, 36 Pages, 1995/08

JAERI-Research-95-054.pdf:1.41MB

no abstracts in English

JAEA Reports

Experimental comparison of calibration methods for measurement of reaction rate by using fission foils

Sakurai, Takeshi; ; Obu, Makoto; ; Kobayashi, Keiji*; Unesaki, Hironobu*

JAERI-M 93-153, 50 Pages, 1993/08

JAERI-M-93-153.pdf:1.31MB

no abstracts in English

JAEA Reports

Introduction of Nuclear Instrumentations and Radiation Measurements in Experimental Fast Reactor 「JOYO」

Odo, Toshihiro;

PNC TN9420 92-005, 83 Pages, 1992/04

PNC-TN9420-92-005.pdf:2.17MB

This report introduces the nuclear instrumentation system and major R&D (research and development) activities using radiation measurement techniques in Experimental Fast Reactor "JOYO". In the introduction of the nuclear instrumentation system, following items are described; (1)system function (2)roles as a reactor plant equipment (3)specifications and charactelistics of neutron detectors, (4)construction and layout of the system. For reactor dosimetry at various irradiation tests and surveillance tests, multi-foil method employed in "JOYO", neutron fluence evaluation using activation foils and HAFM (Helium Accumulation Fluence Monitor) under development are described briefly. The failed fuel detection system and some experimental equipments using radiation measurement techniques are also introduced here with main results obtained by a series of fuel failure simulation experiments. In addition, following R&Ds are picked up as some examples based on radiation measurement technology; (1)burn-up measurement of spent fuel subassembly (2)measurement and evaluation of radiation source distributions (radioactive corrosion products)

Journal Articles

Neutronics experiment and analysis on a tungsten slab assembly bombarded with D-T neutrons

Ikeda, Yujiro; *; Konno, Chikara; Nakamura, Tomoo

Fusion Engineering and Design, 18, p.309 - 315, 1991/00

https://doi.org/10.1016/0920-3796(91)90144-F
 Times Cited Count：3 Percentile：40.8(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analyrical measurement using radioisotope sealed sources

Genshiryoku Kogyo, 25(11), p.63 - 66, 1979/00

http://ci.nii.ac.jp/naid/40001072154

no abstracts in English

Journal Articles

Fission Rate Measurement by Foil Activation Method

Nihon Genshiryoku Gakkai-Shi, 13(2), p.73 - 75, 1971/00

https://doi.org/10.3327/jaesj.13.73

no abstracts in English

Journal Articles

On the analysis and interpretation of foil data

Furuhashi, Akira

Nihon Genshiryoku Gakkai-Shi, 4(11), p.797 - 807, 1962/00

https://doi.org/10.3327/jaesj.4.797

no abstracts in English

Oral presentation

Status of $$^{99}$$Mo/$$^{99m}$$Tc production development by (n,$$gamma$$) reaction in JMTR

Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori

no journal, , 

Technetium-99m ($$^{99m}$$Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce $$^{99}$$Mo by (n,$$gamma$$) method, a parent nuclide of $$^{99m}$$Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of $$^{99}$$Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of $$^{99}$$Mo/$$^{99m}$$Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on $$^{99}$$Mo/$$^{99m}$$Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of $$^{99m}$$Tc solution will be equipped the hot cell in the JMTR Hot laboratory and the following R&D items will be carried out for the production improvement. (1) Fabrication of irradiation target such as the sintered MoO$$_{3}$$ pellets, (2) Separation and concentration of $$^{99m}$$Tc by the solvent extraction from Mo solution, (3) Examination of $$^{99m}$$Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this symposium, the status of the R&D and construction of the PIE devices under this project will be introduced for the production of $$^{99}$$Mo/$$^{99m}$$Tc production improvement.

Oral presentation

Accuracy improvement of thermal-neutron capture cross-section for Np-237

Nakamura, Shoji; Terada, Kazushi; Kimura, Atsushi; Nakao, Taro; Iwamoto, Osamu; Harada, Hideo; Uehara, Akihiro*; Fujii, Toshiyuki*

no journal, , 

As a part of the AIMAC Project, our group have measured the cross sections for Minor Actinides by an activation method with research reactors. In this presentation, we will clear up the cause of discrepancies among reported data for Np-237 in terms of the $$gamma$$-ray emission probability, experimental method and so on.

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