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Okumura, Keisuke; Okamoto, Tsutomu
no journal, ,
In order to evaluate nuclide inventories in LWR spent fuels with sufficient accuracy, the local power history normalization function was newly implemented in the burn-up calculation code MVP-BURN. The function was validated by comparison between calculated and measured values for nuclide inventories in the post irradiation examination analyses.
Ebine, Masumi; Katagiri, Masaki*; Birumachi, Atsushi; Nakamura, Tatsuya; Hosoya, Takaaki*
no journal, ,
no abstracts in English
He position sensitive proportional counter systemBirumachi, Atsushi; Katagiri, Masaki*; Ebine, Masumi; Nakamura, Tatsuya; Arai, Yoichi*; Ochiai, Kunihito*
no journal, ,
no abstracts in English
Suyama, Kenya; Totsuka, Masayoshi; Uchiyama, Gunzo; Takada, Tomoyuki*
no journal, ,
Decommission of the Fukushima Daiichi NPP is under discussion. It is not possible for us to assure the fuel assemblies keep the original geometry, and the nuclide composition of the material of the damaged fuel and their positions in the reactor are also unknown now. So that, in this stage, it is difficult for us to judge whether the parameters adopted in the criticality safety evaluation is reasonable or on the contrary over conservative. Based on this view, for the further study on the criticality safety evaluation of the damaged nuclear fuel, we have stared evaluating the basic criticality parameters of such fuel materials.
Nakanishi, Yoshiki; Nakagawa, Akinori; Sone, Tomoyuki; Sasaki, Toshiki; Nakazawa, Osamu; Tashiro, Kiyoshi
no journal, ,
no abstracts in English
Sone, Tomoyuki; Sasaki, Yu; Nakanishi, Yoshiki; Nakazawa, Osamu; Tashiro, Kiyoshi
no journal, ,
no abstracts in English
Ichikawa, Shoichi; Katsuyama, Kozo; Maeda, Koji; Nishinoiri, Kenji; Uwaba, Tomoyuki; Koyama, Shinichi
no journal, ,
Out of pile bundle compressive test plan for a thick pin is carried out in order to evaluate BDI behavior of "Monju" advanced reactor and demonstration reactor.
Zaima, Naoki; Nakashima, Shinichi; Nakatsuka, Yoshiaki; Kado, Kazumi
no journal, ,
We developed uranium mass assay systems for 200-litter wastes drums applied neutron and 
measurements by NDA method. The systems are composed of the 16 pieces of Helium-3 proportional counters for neutron detection with 100 mm thickeness polyethylene and a Ge-SSD for ray detection. The neutron measurement methodology is consist of 
U (
,n) reaction and measurement is applied by Ge-SSD. The extensive testing trials using the known amount of uranium with different enrichment and some kinds of matrices in drums were performed. By using this system we tried to determine uranium mass in drums for the purpose of reduction MUF in URCP.
Tamai, Hidesada; Akimoto, Hajime; Takase, Kazuyuki
no journal, ,
no abstracts in English
Yamano, Hidemasa; Tanaka, Masaaki; Kaneko, Tetsuya; Sakai, Takaaki; Sago, Hiromi*; Hirota, Kazuo*; Xu, Y.*
no journal, ,
Experimental and analytical evaluation have been carried out to understand flow-induced-vibration characteristics of large-diameter elbow pipings and to develop its assessment methodology for ensuring the feasibility of sodium fast reactor design with two-loop cooling system for the increase of reactor power output. Proposed guideline of flow-induced vibration evaluation for hot-leg piping has been developed compling their research results.
Yamaguchi, Masatake; Udagawa, Yutaka; Abe, Hiroaki*; Sekimura, Naoto*
no journal, ,
From first-principles calculations, we investigate solute segregation energy and defect formation energy in hcp Zirconium. We found that segregation energies of some solute elements (Fe, Cr, etc.) are large enough to segregate at Zr grain boundary.
Matsuoka, Leo; Ichihara, Akira; Yokoyama, Keiichi
no journal, ,
no abstracts in English
Sawamura, Masaru; Nagai, Ryoji; Nishimori, Nobuyuki; Hajima, Ryoichi
no journal, ,
We are proposing non-destructive assay system of nuclear materials with laser Compton scattering combined with an energy-recovery linac and a laser. We are designing a spoke cavity with electro-magnetic simulation code and fabricated a model cavity. RF properties was measured and compared with calculation. The results will be presented.
Yoshida, Hiroyuki; Nagatake, Taku; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*
no journal, ,
no abstracts in English
Onodera, Naoyuki; Yoshida, Hiroyuki; Takase, Kazuyuki
no journal, ,
no abstracts in English
Watakabe, Tomoyoshi; Kitamura, Seiji; Tsukimori, Kazuyuki; Morishita, Masaki
no journal, ,
no abstracts in English
Miyabe, Masabumi; Oba, Masaki; Akaoka, Katsuaki; Iimura, Hideki; Tampo, Motonobu; Oba, Hironori; Maruyama, Yoichiro; Wakaida, Ikuo
no journal, ,
We measured number density distribution of ablation plume of uranium and its temporal variation. From this measurement, we determined several experimental conditions suitable for isotope analysis of uranium, i.e. observation timing, observation height from sample surface and gas pressure etc. It was found that the limit of detection of this method was several 100 ppm using the obtained optimum conditions.
Kojima, Kensuke; Okumura, Keisuke; Okamoto, Tsutomu
no journal, ,
For the accurate inventory estimation of gadolinium isotopes in LWR fuel assemblies with burnable poisoned rods (Gd
O
-UO), burn-up analyses were carried out for PWR and BWR fuel assemblies by using MVP-BURN and JENDL-4.0. As a result, isotope generation and depletion of gadolinium in each fuel assembly were quantitatively clarified.
Nishihara, Kenji; Sugawara, Takanori; Iwamoto, Hiroki; Tsujimoto, Kazufumi; Pyeon, C. H.*; Yagi, Takahiro*
no journal, ,
Analysis method for the pulsed neutron method is newly developed to obtain neutron lifetime with subcriticality based on the maximum likelihoods method. The method was validated by experiments in the KUCA with several subcriticalities injected by a DT neutron source with several repetitions.
Isozaki, Toshihiko; Shirato, Yoji; Tsutagi, Koichi; Yoshino, Yasuyuki; Uchida, Toyomi; Nakamura, Yoshinobu
no journal, ,
no abstracts in English