Analysis of energy deposition and evaluation of maximum load of irradiation capsule for NSRR experiment with uranium-zirconium hydride fuel

Fuketa, Toyoshi; Ishijima, Kiyomi; Tanzawa, Sadamitsu; Nakamura, Takehiko; Sasajima, Hideo; Kashima, Yoichi; ;

JAERI-Research 95-005, 53 Pages, 1995/01

JAERI-Research-95-005.pdf:1.96MB

no abstracts in English

None

; Kashima, Sadamitsu;

Donen Giho, (83), p.67 - 69, 1992/06

https://jopss.jaea.go.jp/pdfdata/PNC-TN1340-92-003.pdf

HBWR Irradiation experiment for plutonium bearing "LWR-Type" Fuel Rod (2nd); (II) Fuel rod fabrication of IFA-529 fuel assembly

Honda, Yutaka*; *; *; *; Seki, Masayuki; *; *; Kashima, Sadamitsu

PNC TN843 83-01, 108 Pages, 1983/04

PNC-TN843-83-01.pdf:10.96MB

None

None

Honda, Yutaka*; Kashima, Sadamitsu; *; *

PNC TN841 82-05, 26 Pages, 1982/01

PNC-TN841-82-05.pdf:2.46MB

no abstracts in English

None

Honda, Yutaka*; Kashima, Sadamitsu; *

PNC TN841 81-13, 116 Pages, 1981/03

PNC-TN841-81-13.pdf:12.87MB

no abstracts in English

Certificate and Records of HALDEN IFA-529 Test Fuel Rods in PNC Irradiation Program

Kashima, Sadamitsu; *; *; Koizumi, Masumichi; Tateishi, Yoshinori*; Honda, Yutaka*

PNC TN841 80-21, 51 Pages, 1980/03

PNC-TN841-80-21.pdf:1.56MB

The Halden IFA-529 irradiation test is planned to examine the fuel dehavior of BWR Type fuel under reactor operation. Twelve fuel rods for this irradiation testwere fabricated in Research & Development Section of Plutonium Fuel Div. in PNC. These fuel rods have instrumentations for the measurement of fuel column elongation, claddingelongation, plenum pressure and fuel center temperature. The fuel pellets were made from type of raw materials. One was obtained by precipitation-calcination prosess, and another was direct denitration process. The fuel composition is 8.3% PuO2-U02(natural), and the pellet nominal dimension is 10.56mm dia. and 10mm height.

Fabrication tests of low density nuclear fuel pellets

Honda, Yutaka*; Kashima, Sadamitsu; ; Koizumi, Masumichi*

American Ceramic Society Bulletin, 60(12), p.1296 - 1299, 1980/00

Ceritificate and records of PNC fuel pins for RAPSODIE-6,7 irradiation program

Honda, Yutaka*; Kashima, Sadamitsu

PNC TN841 79-30, 47 Pages, 1979/02

PNC-TN841-79-30.pdf:2.43MB

Rap - 6,7 irradiation tests planned as the pre-irradiation of Monju type fuel pins to be used for transient tests in GETR. The 24 fuel pins (12 of upper and lower pins each) fabricated from two sintering lots of pellet. The fuel composition is 30% PuO-60% EUO, and nominal pllet density is 85% TD. The fuel pins contains fuel pellets, insulator pellets, spring, tagging gas container, plenum sleeve and sic container.

Certificate and records of PNC fuel pellets and pin components for power-to-melt experiment (HEDL P-EO1) in EBR-II

Kashima, Sadamitsu; Motohashi, Koichi

PNC TN841 78-70, 35 Pages, 1978/11

PNC-TN841-78-70.pdf:1.14MB

Uranium-Plutonium mixed oxide pellets and the other components for fuel pins have been fabricated by PNC. These materials are expected to be assembled to three fuel pins by HEDL (Han-ford Engineering Development Labo tory) for in adiation test P-E01 in EBR-11. The components includes claddings, endplugs, plenum spacers and springs.

None

Koizumi, Masumichi; Kashima, Sadamitsu; *; *; *; *; *; *

PNC TN841 78-16, 44 Pages, 1978/02

PNC-TN841-78-16.pdf:2.75MB

no abstracts in English