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JAEA Reports

Non-destructive assay equipment for quantitative determination of the nuclear material in plutonium fuel fabrication facility

; Akutsu, Hideo*; *; Miyahara, Kenji; *; *

PNC TN841 75-34, 23 Pages, 1975/09

Non-destructive assay equipment for quantitative determination of the neuclear material in plutonium fuel fabrication facility. In plutonium fuel Fabrication Facility (PFFF) of PNC, nuclear materials are received in the form of oxide powder both for plutonium and uranium as raw material, and are shipped to reactor site as the sub-assembly after passing through fabrication processes such as pellet preparation, fuel rod fabrication and assembling. This production line has some strategic points where the nondestructive assay is available for the safeguards techniques. In our facility, four strategic points for nondestructive assay were established as follows. (1) Receiving of nuclear material, (2) Shipping of subassembly, (3) Fuel rod, (4) Contaminated waste and scrap of the fuel power or pellets. This paper reports the result obtained from a callorimeter, scanner, neutron coincidence meter that was prepared for these strategic points.

JAEA Reports

Potentiality of an accounting system for nuclear materials in the PNC plutonium fuel facilities

*; ; *; Akutsu, Hideo*

PNC TN841 75-33, 13 Pages, 1975/09

PNC-TN841-75-33.pdf:1.41MB

The accounting system based on filing of data and inquiry processingby the use of an optical mark reader (OMR) has been developed and operated satisfactorily for criticality control and accountancy of nuclear materialsin plutonium facilities of PNC. The OMR system has merits, especially compared with an old chit and punch card system, such as low cost, abundance of the data included on a single sheet, universality of use for all kinds of material transfers, easiness of data correction, and large capacity todeal with. The OMR system is applied to the material transfer and also for the physical inventory taking. This system, together with the use of an accurate automatic balance equipped at each glove box, which is generally designated as an accounting unit for the criticality control, generated a MUF of 0.43% for a fuel fabrication campaign of 119 assemblies for a fast reactor, which can be decreased further. In correspondence to the recent safe guarding situation and also to fitting to an automatic fuel fab

JAEA Reports

Certificate and records of PNC fuel pins for RAPSODIE-5 irradiation program

Akutsu, Hideo*; Koizumi, Masumichi; Kashima, Sadamitsu; *

PNC TN841 75-15, 55 Pages, 1975/04

PNC-TN841-75-15.pdf:2.55MB

This document is completed according to the quality control and testing procedures described in "Preliminary Design of PNC-5 Subassembly for Rapsodie Irradiation" Coprecipilation methods was employed for preparing PuO $_{2}$ -UO $_{2}$ powder. Five lots of pellets are provided for fablication of forty fuel pins. Fablication process of PuO$_{2-UO$_{2 powder, pellets and fuel pins are shown in Fig.3-1, Fig.3-2, Fig.3-3 respectively.

JAEA Reports

Irradiation performance test of PuO $_{2}$ -UO $_{2}$ fuels by saxton reactor

Akutsu, Hideo*; *

PNC TN841 74-50, 58 Pages, 1974/12

PNC-TN841-74-50.pdf:6.93MB

Mixed oxide (PuO $_{2}$ -UO $_{2}$ ) fuel rods (four rods and oneassembly containing 68 rods) were irradiated to certificate irradiation performance of proto-typed fuel by saxton reactor to peak burnups of up to 8,050 MWd/mtm. linear power level was from 200 to 500 watts/cm. after irradiation, post-irradiation examinations were conducted in battelle's columbus laboratories (BCL). The post irradiation examinations were consisted of visual examination, profilometry, gamma scanning, fuel and clad metallography, burnup analysis, hydride analysis in claddings and clad strength tests. These examinations showed that the overall performance of the PuO $_{2}$ -UO $_{2}$ fuel was satisfactory.

JAEA Reports

Irradiation Performance Test of PuO $_{2}$ -UO $_{2}$ Fuels by Saxton Reactor

Akutsu, Hideo*; Koizumi, Masumichi

PNC TN841 74-49, 53 Pages, 1974/12

PNC-TN841-74-49.pdf:2.61MB

Mixed oxide(PuO $_{2}$ -UO $_{2}$ ) fuel rods (fourrods and one assembly containing 68 rods) were irradiated to certificate irradiationperformance of proto-typed fuel by SaxtonReactor to peak burnups of up to 80,500 MWD/MTM. Linear power level was from 200 to 500 watts/cm. After irradiation,post-irradiationexaminations were conducted in Battelle's Columbus Laboratories (BCL). The postirradiation examinations were consisted of visual examination, profilometry, gamma scanning, fuel and clad metallography, burnup analysis, hydride analysis in claddings and clad strength tests. These examinations showed that the overall performance of the PuO $_{2}$ -UO $_{2}$ fuel was satisfactory.

JAEA Reports

Uraniumu-Plutoniumu Mixed-Oxide Fuel Fabrcation for the Deuterium Critical Assembly "DCA" in JAPAN

Akutsu, Hideo*; *; *; Naruki, Kaoru

PNC TN843 74-13, 36 Pages, 1974/11

PNC-TN843-74-13.pdf:0.7MB

The construction of the prototype heavywater reactor "FUGEN" is currentlyprogressing on the schedule to be criticalin 1976. Prior to this reactor operation,the reactor physics examination are carringout with the Deuterium Critical Assembly "DCA" since 1973. A new facility, thePlutonium Fuel Fabrication Facility (PFFF)of PNC which is mainly devoted to mass-production, was constructed to meet theplutonium fuel fabrication requirement forPNC's FBR and ATR projects. At the "ATR line" of this PFFF, thefabrication of the plutomium fuel elementsfor DCA had been carried out since Mar. 1972, and 92 fuel assemblies with the totalmixed-oxide amounting to as much as 10tons were completed in Feb. 1973. It was the first experience in Japanthat,such a large amounts of mixed-oxidewas fabricated as the fuel assembliescomposed of three kinds of fuel rodsaccording to both the isotopic charactor and the plutonium enrichment, totaling about2600 fuel rods.

JAEA Reports