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Ichikawa, Shoichi; Haga, Hiroyuki; Katsuyama, Kozo; Uwaba, Tomoyuki; Maeda, Koji; Nishinoiri, Kenji
JAEA-Testing 2012-001, 36 Pages, 2012/07
JAEA-Testing-2012-001.pdf:11.48MB
The life of FBR (Fast Breeder Reactor) fuel assembly is restricted by BDI (Bundle-Duct Interaction). Therefore, it is very important to carry out the out pile bundle compressive tests which can imitate BDI, in order to evaluate BDI behavior. The target of the conventional BDI behavior was thin pins (
6.5 mm) for fuel pellets which were used with the assembly of Monju (the Monju prototype fast breeder reactor) etc. Furthermore by an upgraded Monju core and a demonstration core, adoption of thick pins for the holler annular pellets is planned. Therefore, it was necessary to carry out BDI evaluation of a thick pin. Then, the plans for out of pile bundle compressive test for large diameter pins were are reported this time.
Hirayama, Takashi; Kannari, Masaaki; Sato, Tomohiko
JAEA-Testing 2012-002, 29 Pages, 2012/06
JAEA-Testing-2012-002.pdf:2.98MB
In pursuance of "The Optimization Plan on the network of JAEA", which aims to ensure network reliability and information security and to improve convenience in using the network, we are engaged in the optimization of inter-institute/center network bandwidth. This is a record of an introduction of WAN accelerator into the network to Ningyo-toge Environmental Engineering Center which bandwidth is limited due to a geographically constraint.
Kinoshita, Junichi; Endo, Masayuki; Uesaka, Takahiro
JAEA-Testing 2012-003, 29 Pages, 2012/11
JAEA-Testing-2012-003.pdf:2.95MB
The comparatively high level liquid radioactive wastes generated from the nuclear facilities in the Nuclear Science Research Institute of JAEA have been treated by the bituminization system. In the future, bituminized products could be disposed of as homogeneously solidified products, if their qualities would meet with the technical standards of homogeneously solidified products which are stipulated in nuclear regulatory law. In this report, we summarized the measurement results of the density and radioactivity of solidified products in order to get basic data for future disposal.
Fujiwara, Takeshi
JAEA-Testing 2012-004, 13 Pages, 2012/11
JAEA-Testing-2012-004.pdf:2.7MB
In the 4-Group partitioning process developed in Japan Atomic Energy Research Institute (presently: Japan Atomic Energy Agency), a heat-generating nuclide group including Sr and Cs is separated by inorganic ion exchangers. Hydrous titanic acid and zeolite are used as the inorganic ion exchangers. The mechanical durability of the particles of hydrous titanic acid used for Sr recovery is not enough in case of mixing with zeolite used for Cs recovery. The method of drying the hydrous titanic acid was improved to provide sufficient mechanical durability to the product of hydrous titanic acid in case of mixing with zeolite. A procedure of producing hydrous titanic acid from the raw material, titanyl sulfate, was established and documented with cares to be taken at each step.
Shimojo, Yutaka; Ihata, Yoshiaki; Kaneko, Koji; Takeda, Masayasu
JAEA-Testing 2012-005, 63 Pages, 2013/02
JAEA-Testing-2012-005.pdf:11.94MB
Taking an advantage of high penetration capability of neutron, neutron scattering experiments can be performed under various sample environment, such as low (high) temperature, pressure, magnetic field and stress, and those complex conditions. To this aim, a number of sample environment accessories, refrigerators, furnaces, pressure cells, superconducting magnets are equipped in JRR-3 to be used for experiments. In this document, all available equipment in both JRR-3 reactor hall and guide hall are summarized. We hope this document would help neutron scattering users to perform effective, and excellent experiments.