Conceptual design of the handling and storage system of the spent target vessel for a MW-class neutron scattering facility

Adachi, Junichi*; Kaminaga, Masanori; Sasaki, Shinobu; Hino, Ryutaro

JAERI-Tech 2000-068, 86 Pages, 2000/11

JAERI-Tech-2000-068.pdf:4.39MB

no abstracts in English

None

; *; *; *; *

PNC TJ9365 95-001, 110 Pages, 1995/12

PNC-TJ9365-95-001.pdf:7.16MB

None

Measurement and evaluation of dose rates for upper guide tube of control rod drive mechanism in experimental fast reactor "JOYO"

Chatani, Keiji; ; ; Masui, Tomohiko*; Nagai, Akinori; ;

PNC TN9410 92-186, 63 Pages, 1992/06

PNC-TN9410-92-186.pdf:1.64MB

Dose rates around UGT (Upper Guide Tube) of CRDM (Control Rod Drive Mechanism) have been measured in Experimental Fast Reactor "JOYO" during the 9th periodical inspection in order to reflect the study on the shield thickness of UIS (Upper Internal Structure) cask, which has been planned to be used for a Large Fast Reactor. Absolute amount of radioactive corrosion products (CP) is evaluated by gamma spectra analysis for waste water from cleaned UGT. The results on this study are summarized as follows: (1)Measured dose rates distribution around UGT before and after clean-up show the same reduction. The affection of CP is not clearly observed for the dose rate distribution. (2)The relative values of dose rate, which are evaluated by considering the inside structure of UGT, show the attenuation of 10 from bottom to sodium level of UGT. The above relative distribution agrees well with that of measurement data using U-235 fission chamber, which was conducted at MK-I core start-up tests, except the stellite region. (3)As to the relative values of dose rate, calculation by "DOT3.5" and estimation by measured dose rate agree within factor 3 for the attenuation of 10. It is confirmed that the calculation can predict well the measurement. (4)Absolute amount of CP estimated by gamma spectra analysis and waste water analysis is 180 MBq. Co dominates 92 % of CP. This value agrees with the prediction by corrosion product behavior analysis code "PSYCHE" within factor 2.

Analysis of Shielding Benchmark Problem Using the Monte Carlo Code MORSE-CG

*; *; *; *; *; *; *; *;

JAERI-M 83-142, 52 Pages, 1983/09

JAERI-M-83-142.pdf:1.28MB

no abstracts in English

Design of transfer cask for mercury target vessel irradiated at J-PARC spallation neutron source

Harada, Masahide; Uchida, Toshitsugu; Sekijima, Mitsuaki; Haga, Katsuhiro; Kogawa, Hiroyuki; Kinoshita, Hidetaka; Takada, Hiroshi; Sato, Koichi; Masuyama, Koichi

no journal, , 

no abstracts in English