Determination of Plutonium in High Active Liquid Waste by Spectrophotometry using Neodymium as an Internal Standard for Safeguards Analysis

Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kitao, Takahiko; Hina, Tetsuro; Toshiaki, Hiyama,

Dai-25-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, p.120 - 127, 2004/00

For the determination of Pu in the high active liquid waste (HALW), isotope dilution mass spectrometry (IDMS) has been applied to verification analysis at Tokai Reprocessing Plant. IDMS has been considered as the most reliable analytical technique for accountability measurement of Pu in spent fuel reprocessing plant. However, it takes quite long time for inspector to obtain an analytical result because inspection sample has to be transported to safeguards analytical laboratory for off-site analysis. In order to overcome this disadvantage, a rapid verification analysis of Pu in HALW by conventional spectrophotometer using Nd as an internal standard was proposed to achieve on-site verification measurements. In this method, Nd standard is intended to be provided by International Atomic Energy Agency (IAEA) so that an inspector can independently control it not only as an internal standard but also as an authentication purpose. The validation analysis was carried out by comparing with IDMS. It was found that the values of Pu concentration obtained by proposed method were in good agreement with those obtained by IDMS. Therefore the proposed method can be expected for the application to the verification analysis.

Determination of Plutonium in High Active Liquid Waste of Reprocessing Plant by Spectrophotometry using Neodymium as an Internal Standard

Surugaya, Naoki; Taguchi, Shigeo; Sato, Soichi; Hina, Tetsuro; Toshiaki, Hiyama,; Kitao, Takahiko

Proceedings of 45th INMM Annual Meeting, CD-ROM, 8p., 8 Pages, 2004/00

A rapid verification technique with conventional spectrophotometer has been developed to achieve on-site safeguards measurements in which neodymium as an internal standard was chosen to determine the plutonium concentration in high radioactive liquid waste.This method will provide the on-site analytical capabilities as it allows rapid and simple analyses at Tokai Reprocessing Plant.

None

Surugaya, Naoki; Sato, Soichi; ;

Saikuru Kiko Giho, (18), p.83 - 90, 2003/03

https://rdreview.jaea.go.jp/gihou/pdf2/n18-09.pdf

None

Degradation of Tribytylphosphate in Plutonium Nitrate Solutions

Kuno, Yusuke; ; Masui, Jinichi

Journal of Nuclear Science and Technology, 29(8), p.762 - 767, 1992/00

https://doi.org/10.3327/jnst.29.762

Examination of determination to Pu amount in LASW from TRP

Makino, Risa; Kabuki, Toshihide*; Tomikawa, Hirofumi; Hina, Tetsuro; Ozone, Takashi; Kurosu, Kazutoshi; Fukuhara, Junichi; Kobayashi, Kentaro

no journal, , 

Tokai Reprocessing Center has developed method of determination of Pu contained in low activity solid wastes (LASWs), to make better accountancy control. Our final goal is to estimate of Pu amounts in wastes generated in Tokai Reprocessing Plant (TRP). Some of small size wastes (carton-boxes) and drums from TRP was measured by some kind of non-destructive assay system. It was found that high dose wastes have slight amounts of Pu. However, because some of wastes from TRP have FPs, the wastes could not be measured exactly. Near future, JAEA will try upgrading or development of NDA system, and determination of Pu amount of wastes from TRP.

Operator's experience on random inspection for reprocessing plant at JNC-1 site

Ishiyama, Koichi; Miura, Yasushi; Kimura, Takashi; Hina, Tetsuro; Kodani, Yoshiki; Fukuhara, Junichi; Yamaguchi, Katsuhiro*; Ikeda, Atsushi*; Kabuki, Toshihide*

no journal, , 

Regarding the Integrated Safeguards (IS) for JNC-1 site where includes six facilities of the Reprocessing Center and MOX fuel fabrication facilities and so on, its discussion for application started in June 2004 between the government of Japan and IAEA, its concept was agreed in November 2006, and it has been introduced in August 2008. With IS for JNC-1, for the purpose of improvement of deterrence of the nuclear material diversion, the traditional interim inventory verification (IIV) that had been implemented as scheduled previously has changed to random interim inspection with short notice (RII.)The Tokai Reprocessing Center consists of 2 facilities; TRP and PCDF, and has nuclear materials from the spent fuel to the MOX powder. The IIV needed about 5 person-days for TRP and about 7 person-days for PCDF. It was discussed to make RII procedure that makes it possible to perform such short notice inspection and reduce the person-days by about 2 per a RII. Although it was discussed that what and how frequently information was provided to inspectors in order them to make a plan to implement RIIs. After the introduction of RII, the person-days are decreased even though the operators' work loads for information provision are increased. This paper reports development of the method, experience and expected effectiveness regarding RII to the Tokai Reprocessing Center in the viewpoint of its operator.