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Oral presentation

Evaluation of differential pressure fluctuation between subchannels in a tight-lattice rod bundle

Zhang, W.; Yoshida, Hiroyuki; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Coupled hydro-transport analysis study on geochemical environmental change caused by tunnel excavation using geological data obtained from the Horonobe URL project

Suzuki, Hideaki; Fujita, Tomo; Fujisaki, Kiyoshi*

no journal, , 

The development of excavation disturbed zone (EDZ) around the disposal tunnel affects such as the corrosive environment of the over-pack and environmental condition of the nuclear species migration on the geological disposal for the high-level radioactive waste (HLW). It is necessary to consider affect of EDZ in the realistic numerical simulation of the long-term behavior of near-filed HLW repository after emplacement of engineered barrier system. This study presents the results on the analysis assessment on geochemical reaction with the evolution of the unsaturated zone around the tunnel with consideration of Horonobe area geological environment, using the developed coupled Thermo-Hydro-Mechanical and Chemical (THMC) processes analysis model. As a result, this model is applied a change of the solution composition by degasification of the carbon dioxide gas to the pore water and the change of the oxidation-reduction potential due to unsaturated zone around the tunnel.

Oral presentation

Role of expert authority in work management; Analysis of JCO criticality accident

Tanabe, Fumiya

no journal, , 

The behavior of changing a procedure of UNH homogenization without permission by the manager of the the production group was greatly influenced by lack of expert autority in the manager and its cogition by himself and the foreman of the special crew. The selfcognition by the manager resulted aslo in his behavior of neglecting the walk-around check of the work in the conversion test building.

Oral presentation

Evaluation of nuclear data of deuterium for neutron- and proton-induced reactions up to 250 MeV

Chiba, Satoshi; Hiratsuka, Yasuhisa*; Gojuki, Shuichi*; Oryu, Shinsho*

no journal, , 

Nuclear data of deuterium are evaluated for neutron- and proton-induced reactions up to 250 MeV. The neutron total cross section was evaluated based on least-squares method GMA taking account of available experimental data. The elastic scattering cross section, its angular distribution and break-up reaction cross section were calculated in terms of Faddeev theory. The calculated results reproduced the experimental data well.

Oral presentation

Economic effect of radiological application; Year 2006

Yanagisawa, Kazuaki; Kume, Tamikazu; Makuuchi, Keizo*; Inoue, Tomio*; Komoda, Fumio*; Maeda, Mitsuru*

no journal, , 

Products produced by using radiological application (electron and $$gamma$$ ray etc.) at industrial and agricultural fields as well as reimbursement of medical and dental cares in Japanese market was studied at fiscal year 2006. This is to certify the quantitative role of radiological application, which will benefit the welfare of the people of our nation. The shipment of semiconductor has the largest share in our industrial market, having economic scale approximately of 4,800 billion yen. The net value taking into consideration of attributed ratio of radiation as much as 23% will be 1,082 billion yen. The shipment of rice born by mutation has the largest share in our agricultural market (90% of the total), having economic scale approximately of 260 billion yen. Application of radiation is done at medical and dentistry fields, an economic scale based on reimbursement is 1,620 billion yen.

Oral presentation

The Development for the separation measurement method of Pu-239 and U-235 by using 14 MeV neutron direct interrogation method

Takamine, Jun; Haruyama, Mitsuo; Takase, Misao; Yamaguchi, Satoshi

no journal, , 

We have not yet known the nondestructive detection method to determine each quantity of the object which Uranium and Plutonium is mixed in, such as the waste contaminated by MOX fuel. Then we paid attention to the component of delayed and prompt neutron obtained by 14 MeV neutron direct interrogation method. And from those correlations, we developed the new method to determine the abundance of Uranium and Plutonium. Actually, we made the theory formula of the correlation and perform the experiment where a ratio of Pu-239 and U-235 is the independent variables. As a result, we confirmed that a theory value accorded with experimental value in precision. Furthermore, as a method to drastically reduce a background on measurement of prompt neutron, it has been suggested that graphite reflector was changed in stainless steel. And then, fixed-quantity precision on this technique was also improved greatly by this renovation.

Oral presentation

Evaluation method of pH elevation caused by reaction between cement hydrates and saline water

Masuda, Kenta; Honda, Akira; Fujita, Hideki*; Negishi, Kumi*

no journal, , 

It is important for evaluating the migration behavior of radionuclides and the influence of high pH plume on the barrier components to understand the chemistry of cement pore water. In order to understand the pH elevation of the cement pore water, OPC pastes were immersed in NaCl solution. The experimental results were analyzed using geochemical model. The pH elevation can be interpreted using the initial OPC hydrates composition which takes Al included in C-S-H gel into account.

Oral presentation

Uncertainty analysis for groundwater migration scenario of geological disposal of TRU waste

Nishimura, Yuki; Takeda, Seiji; Kimura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Development of nondestructive measurement techniques for uranium-contaminated waste; Examination of evaluating nuclide composition

Oki, Koichi; Ishibashi, Yuzo; Muto, Katsumi; Komatsuzaki, Takashi*; Suzuki, Satoshi*; Sukegawa, Yasuhiro*

no journal, , 

no abstracts in English

Oral presentation

Nuclear data for nuclear criticality safety

Suyama, Kenya

no journal, , 

Improvement of the accuracy of the nuclear data is an important factor for reliable nuclear criticality safety evaluation. Under the situation where the nuclear data of main isotopes have been improved considerably, we would like to take this opportunity to review the required nuclear data for future safety evaluation of nuclear fuel cycle facilities.

Oral presentation

Effect of overpack corrosion on redox potential of bentonite pore water, 3; Corrosion test of carbon steel in compacted bentonite

Iida, Yoshihisa; Yamaguchi, Tetsuji; Inada, Daisuke; Tanaka, Tadao; Otsuka, Ichiro*

no journal, , 

no abstracts in English

Oral presentation

Development of common and fundamental technologies on nuclear fuel behavior for realizing MA recycling, 2; Calculation and formulation of helium production in fast reactor fuel

Akie, Hiroshi; Suzuki, Motoe; Serizawa, Hiroyuki; Arai, Yasuo

no journal, , 

Helium production in fast reactor fuel is estimated by using burnup calculation code system SWAT by taking into consideration $$alpha$$ decay, oxygen (n,$$alpha$$) reaction and ternary fission. A formula is formulated in order for the simple estimation of helium production in fast reactor fuel, and the results are compared with the detailed calculation results by SWAT. As a result, the difference between the SWAT calculation and the simplified formula in the estimated helium production amount is about 10% or less.

Oral presentation

CREPT-MCNP; Code system for efficiency calibration of $$gamma$$-ray spectrometer based on the representative point method

Saegusa, Jun; Ogose, Hitoshi; Takamura, Atsushi*; Sugita, Takeshi*

no journal, , 

The representative point method is an efficiency calibration method for a $$gamma$$-ray spectrometer. A calculation code system, CREPT-MCNP, for implementing the method has been newly developed. CREPT-MCNP can be operated under the Windows PC environment as a GUI based application. The code system estimates the position of the representative point which is intrinsic to each shape of volume sample, and also gives the self-absorption factors to make correction on the efficiencies measured at the representative point with a standard point source. It can deal with photons between 20 keV and 2 MeV with p- or n-type germanium semiconductor detectors.

Oral presentation

Long time power profile until re-criticality and recovery of power in criticality accident

Yamane, Yuichi

no journal, , 

After criticality accident occurred at nuclear fuel solution, the fission power increases to its maximum then decreases monotonically. An equation was derived for the time interval between re-criticality and recovery of the power. The evaluated results show good agreement to experimental data.

Oral presentation

Experimental determination of hydraulic conductivity of bentonite under various exchangeable cation compositions and ionic strengths

Kadowaki, Mitsushi; Yamaguchi, Tetsuji; Mukai, Masayuki; Iida, Yoshihisa; Tanaka, Tadao

no journal, , 

no abstracts in English

Oral presentation

Development of dynamic neutron computer tomography for the thermal-hydrauric evaluation of liquid metal, 2; Velocity measurement

Kureta, Masatoshi; Kumada, Hiroaki; Kume, Etsuo; Someya, Satoshi*; Okamoto, Koji*

no journal, , 

Development of the Dynamic Neutron Computer Tomography (DNCT) technique is conducted as the new 4D thermal-hydraulic measurement technique in order to provide the detailed database for thermal-hydraulic evaluation methods on liquid metal cooled FBR core. We studied the data analysis method to be realized a velocity measurement by the DNCT, and developed the velocity and locus measurement techniques by expanding the spring model particle trace velocimetry. In this presentation, velocity measurement technique installed in the DNCT analysis system and test results taken at the JRR-4 are reported.

Oral presentation

Experimental study on mineralogical changes with interaction between cement and bentonite

Hoshino, Seiichi; Yamada, Fumika*; Mukai, Masayuki; Yamaguchi, Tetsuji; Tanaka, Tadao

no journal, , 

no abstracts in English

Oral presentation

Source term evaluation in containment vessel during late phase of severe accident, 9.2; Experiments on iodine chemistry under irradiation

Moriyama, Kiyofumi; Tashiro, Shinsuke; Hirayama, Fumio*; Maruyama, Yu; Nakamura, Hideo; Watanabe, Atsushi*

no journal, , 

no abstracts in English

Oral presentation

Calculations of temperature reactivity coefficients for homogeneous MOX fuel system

Sato, Shohei; Okuno, Hiroshi

no journal, , 

From a viewpoint of nuclear criticality safety evaluation, it is important to comprehend temperature reactivity coefficient. In this paper, we calculate temperature reactivity coefficient of MOX fuel by fitting a quadric curve in the changing temperature system. As a result, it is indicated that temperature reactivity coefficient of MOX fuel is negative, and decreases with H/(U+Pu). Temperature reactivity coefficient does not depend on MOX density.

370 (Records 1-20 displayed on this page)