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JAEA Reports

Performance test of Mo absorbents with irradiated high-density MoO$$_{3}$$ pellets (Joint research)

Kimura, Akihiro; Nishikata, Kaori; Nikolayevich, A.*; Vladimirovna, T.*; Chakrova, Y.*; Tsuchiya, Kunihiko

JAEA-Technology 2013-048, 30 Pages, 2014/03

JAEA-Technology-2013-048.pdf:3.0MB

In this study, the irradiation tests of the high-density MoO$$_{3}$$ pellets and PIEs were carried out with WWR-K for the realization of $$^{99}$$Mo/$$^{99m}$$Tc production procedure by the (n,$$gamma$$) method. High-density MoO$$_{3}$$ pellets were irradiated. After neutron irradiation, the irradiated pellets were carried out PIEs, and the pellets were sound from the results. The irradiated pellets were also dissolved with NaOH solution at 100$$^{circ}$$C. The solution speed of the pellets at 100$$^{circ}$$C was faster than that at 50$$^{circ}$$C and the it was clear that dissolved temperature of pellet was important factor for the solution speed. $$^{99}$$Mo adsorption/$$^{99m}$$Tc elution tests were carried out with PZC and PTC. It was obtained that the properties of $$^{99}$$Mo adsorption/$$^{99m}$$Tc elution of these Mo adsorbents was equivalent in previous results. As the these results, the prospects are bright for the realization of $$^{99}$$Mo production procedure by the (n,$$gamma$$) method.

JAEA Reports

Preliminary test for Mo recycling system in $$^{99}$$Mo manufacturing process, 1; Reusability evaluation of Mo absorbent (Joint research)

Kimura, Akihiro; Niizeki, Tomotake*; Kakei, Sadanori*; Chakrova, Y.*; Nishikata, Kaori; Hasegawa, Yoshio*; Yoshinaga, Hideo*; Chakrov, P.*; Tsuchiya, Kunihiko

JAEA-Technology 2013-025, 40 Pages, 2013/10

JAEA-Technology-2013-025.pdf:2.62MB

Neutron Irradiation and Testing Reactor Center has developed the production of a medical isotope of $$^{99}$$Mo, the parent nuclide of $$^{99m}$$Tc by the (n,$$gamma$$) method using JMTR. The (n,$$gamma$$) method has an advantage of easy manufacturing process and low radioactive wastes generation. However, the low radioactivity concentration of $$^{99m}$$Tc is remaining as an issue. Therefore, PZC and PTC have been developed as adsorbent of molybdenum. Meanwhile, it is necessary to recycle the absorbent and Mo for the reduction of the radioactive waste of used-adsorbent and the effective use of limited resources, respectively. This report summarizes results of the synthesis of Mo adsorbents such as PZC and PTC, and the performance tests.

JAEA Reports

Status of international cooperation in nuclear technology on testing/research reactors between JAEA and INP-NNC

Kawamura, Hiroshi; Chakrov, P.*; Tsuchiya, Kunihiko; Gizatulin, S.*; Takemoto, Noriyuki; Chakrova, Y.*; Kimura, Akihiro; Ludmila, C.*; Tanimoto, Masataka; Asset, S.*; et al.

JAEA-Review 2011-042, 46 Pages, 2012/02

JAEA-Review-2011-042.pdf:2.69MB

Based on the implementing agreement between National Nuclear Center of the Republic of Kazakhstan (NNC) and the Japan Atomic Energy Agency (JAEA) for the Nuclear Technology on Testing/Research Reactors in the cooperation in Nuclear Energy Research and Development in Nuclear Energy and Technology, four specific topics of cooperation (STC) have been carried out from June, 2009. Four STCs are as follows; (1) STC No.II-1: International Standard of Instrumentation, (2) STC No.II-2: Irradiation Technology of RI Production, (3) STC No.II-3: Lifetime Expansion of Beryllium Reflector, (4) STC No.II-4: Irradiation Technology for NTD-Si. The information exchange, personal exchange and cooperation experiments are carried out under these STCs. The status in the field of nuclear technology on testing/research reactors in the implementing arrangement is summarized, and future plans of these specific topics of cooperation are described in this report.

JAEA Reports

Retesting of $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution characteristics of molybdenum adsorbents for (n,$$gamma$$) method; Joint experiment report on irradiation technology of RI production (STC No.2$$-$$II) (Joint research)

Kimura, Akihiro; Izumo, Hironobu; Tsuchiya, Kunihiko; Hori, Naohiko; Ishihara, Masahiro; Bannykh, V.*; Gluschenko, N.*; Chakrova, Y.*; Chakrov, P.*

JAEA-Testing 2010-002, 20 Pages, 2010/08

JAEA-Testing-2010-002.pdf:2.92MB

JMTR has a plan to produce $$^{99}$$Mo, which is the parent nuclide of radiopharmaceutical $$^{rm rm 99m}$$Tc, by (n,$$gamma$$) method. The cooperation experiments for $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution with the Poly-Zirconium Compound (PZC) and the Molybdate Zirconium Gel (Zr-gel) methods were carried out at Kazakhstan National Nuclear Energy Center (NNC) in October, 2009. The $$^{99}$$Mo adsorption capability was the same level as reference data, however the $$^{rm 99m}$$Tc elution capability with PZC was lower than reference data in this test. Therefore, re-experiments of $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution with both methods were carried out at NNC. As a result, the $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution capabilities were obtained as the same levels as reference data. Additionally, $$^{rm 99m}$$Tc solution was high purity by the elution method connected with alumina column.

JAEA Reports

$$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution characteristics of molybdenum adsorbents for (n,$$gamma$$); Method-joint experiment report on irradiation technology of RI production (STC No. 2-II) (Joint research)

Kimura, Akihiro; Izumo, Hironobu; Tsuchiya, Kunihiko; Hori, Naohiko; Ishihara, Masahiro; Bannykh, V.*; Gluschenko, N.*; Chakrova, Y.*; Chakrov, P.*

JAEA-Technology 2009-075, 23 Pages, 2010/02

JAEA-Technology-2009-075.pdf:7.41MB

Japan Materials Testing Reactor (JMTR) of the Japan Atomic Energy Agency (JAEA) has a plan to produce $$^{99}$$Mo, which is the parent nuclide of radiopharmaceutical $$^{rm 99m}$$Tc, by (n,$$gamma$$) method. The $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution characteristics of molybdenum adsorbents should be evaluated since the specific activity of $$^{99}$$Mo obtained by (n,$$gamma$$) method is low. Therefore, $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution tests with molybdenum adsorbents for the (n,$$gamma$$) method such as poly-zirconium compound (PZC) and molybdate zirconium gel were carried out under cooperation with the Kazakhstan National Nuclear Energy Center (NNC). As a result, the $$^{99}$$Mo adsorption performance of the adsorbents was the same level as conventional data, whereas the $$^{rm 99m}$$Tc elution performance of the adsorbents was lower than conventional data. The $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution performance will be investigated again in future.

Oral presentation

Joint experiments for Mo-99 production by (n,$$gamma$$) method

Kimura, Akihiro; Tanimoto, Masataka; Gluschenko, N.*; Morozova, T.*; Moisseikina, N.*; Gurin, A.*; Tsuchiya, Kunihiko; Chakrova, Y.*

no journal, , 

(n,$$gamma$$) method has an advantage of easy manufacturing process and low radioactive wastes generation. However, the low radioactivity concentration of $$^{99m}$$Tc is remaining as an issue. Therefore, the Poly zirconium compound (PZC) and the $$^{99}$$Mo-Zr gel were developed as Mo absorbent in Japan and Kazakhstan. Then, comparison tests and information exchange were carried out for obtaining specific comparison data of PZC and $$^{99}$$Mo-Zr gel. We were able to obtain specific comparison data of PZC and $$^{99}$$Mo-Zr gel from these experiments.

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