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Journal Articles

Nuclide partitioning and transmutation technology; Transmutation using fast reactor

Yanagisawa, Tsutomu*; Usami, Shin; Maeda, Seiichiro

Genshiryoku Nenkan 2018, p.90 - 95, 2017/10

no abstracts in English

JAEA Reports

Proceedings of the 5th NUCEF Seminar; February 27, 2001, JAERI, Tokai, Japan

5th NUCEF Seminar Working Group

JAERI-Conf 2001-015, 92 Pages, 2001/12

JAERI-Conf-2001-015.pdf:13.1MB

no abstracts in English

JAEA Reports

Evaluation of operatinal condition in LWTF; Tests using technical scale equipment

; Murata, Eiichi*; Sawahata, Yoshikazu*; Saito, Akira*

JNC TN8430 2001-002, 43 Pages, 2001/02

JNC-TN8430-2001-002.pdf:1.98MB

Japan Nuclear Cycle Development Institute (JNC) is designing the Low level radioactive Waste Treatment Facility (LWTF) in the Tokai Reprocessing Plant (TRP). The low level liquid waste generated the TRP is separated salt (NaNO$$_{3}$$, etc) and radionuclide in liquid treatment process of LWTF. The process can get higher volume reduction than previous bituminization. Based on the engineering tests equal to the liquid treatment process of LWTF, the validity of operational condition in LWTF is evaluated. As the results, it is confirmed that all operational condition in the processes which is Iodine immobilization, Pre-filter filtration, Pre-treatment, Coprecipitation and Ultrafiltration are available.

JAEA Reports

None

PNC TN8410 96-284, 245 Pages, 1996/03

PNC-TN8410-96-284.pdf:6.22MB

None

JAEA Reports

None

PNC TN8440 96-003, 22 Pages, 1996/02

PNC-TN8440-96-003.pdf:0.73MB

None

JAEA Reports

None

PNC TJ8409 95-005, 215 Pages, 1995/05

PNC-TJ8409-95-005.pdf:9.3MB

None

JAEA Reports

Literature survey on extractants for liquid-liquid extraction applied to nuclear fuel cycles

;

PNC TN8420 95-002, 140 Pages, 1995/01

PNC-TN8420-95-002.pdf:3.16MB

In the field of uranium ore refining and spent fuel reprocessing, a lot of extractants capable of recovering actinides have been innovated, and some of which have been developed in actual industrial scale processes. Extractability against trivalent actinides on each extractants were evaluated in this report. And as for the compounds which showed excellent extractability for Americium, their extraction characteristics for trivalent actinides, such as extraction behavior, mechanism, ligand structure and conformation of complexes, were evaluated, and filed as data-base. Based on these works, some of extractant were newly identified as candidate to apply Americium recovering. The most appropriate compounds for trivalent actinide separation can be generally found in the neutral bidentate organic compound groups: Especially, some derivatives belongs to Diphosphineoxide, Carbamoyl-methylphosphine oxide and Propandiamide were superior to give sufficiently excellent property even in higher nitric acid(1$$sim$$3M) solutions. Innovative research towards developping new extractants and extraction system seems to be directed to ; (1)investigate new types of extractant sustained by a different kind of complexing mechanism, (2)evaluate synergistic effect of adducts, diluents even including conventional extractants.

Journal Articles

A Nuclide-separation wire precipitator for measurement of noble-gas fission products

Katagiri, Masaki; Kishimoto, Maki; Ito, Hirokuni; ; Fukushima, Masao; Okawa, Hiroshi;

Nuclear Instruments and Methods in Physics Research A, 327, p.463 - 468, 1993/00

 Times Cited Count:3 Percentile:43.05(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

None

; ;

PNC TN8420 93-003, 35 Pages, 1992/12

PNC-TN8420-93-003.pdf:3.39MB

None

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