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JAEA Reports

Uncertainty quantification of Doppler coefficient for MONJU

Chiba, Go*; Hazama, Taira; Kinjo, Hidehito*; Nishi, Hiroshi; Suzuki, Takayuki

JAEA-Research 2011-034, 42 Pages, 2011/12

JAEA-Research-2011-034.pdf:1.88MB

Uncertainty of Doppler coefficient is quantified for a Monju core, reflecting present knowledge. Various uncertainty sources are evaluated: (1) Nuclear data and numerical method, (2) Fission product nuclear data, (3) Control rod position, (4) Approximated treatment of temperature dependence, (5) Averaged fuel temperature, (6) Approximated treatment of temperature spatial distribution, etc. Resulting uncertainty for Doppler coefficient is estimated at 11.7% for the 2 $$sigma$$ reliability.

Journal Articles

Feasibility study on an upgraded future Monju core concept with extended operation cycle length of one year and increased fuel burnup

Kinjo, Hidehito*; Kageyama, Takeshi*; Kitano, Akihiro; Usami, Shin

Nuclear Technology, 167(2), p.254 - 267, 2009/08

 Times Cited Count:1 Percentile:87.33(Nuclear Science & Technology)

A conceptual design study has been performed on upgrading the core performance of the Japanese FBR Monju. The main aim of this study is to investigate and demonstrate the feasibility of an upgraded core with an extended refueling interval of 365 EFPD and increased average fuel burnup of 150 GWd/t, which are expected in future commercial FBRs. Two design measures have been taken to accommodate the largely increased burnup reactivity for the longer cycle: (1) A modified fuel pin with increased pin diameter, pellet density and active core height has been introduced to improve the burnup reactivity, (2) The control rod specification has been modified to enhance the reactivity worth by increasing the $$^{10}$$B content to assure sufficient shutdown margin. The evaluation results show that even a medium sized core of about 2.5 m$$^{3}$$ could achieve the target, without causing significant drawbacks to the core characteristics. The feasibility is thus demonstrated.

JAEA Reports

None

*; Kinjo, Hidehito*; *; Ito, Kunihiro*; *

PNC-TJ1214 92-007, 105 Pages, 1992/07

PNC-TJ1214-92-007.pdf:2.82MB

None

JAEA Reports

None

Ito, Kunihiro*; Kinjo, Hidehito*; Aoi, Sadanori*; Kawahara, Kenichi*; Seino, Shun*

PNC-TJ2214 90-001, 118 Pages, 1990/08

PNC-TJ2214-90-001.pdf:3.5MB

no abstracts in English

JAEA Reports

Accident analysis for test pin failure during Power-to-Melt test

Morii, Tadashi*; Kinjo, Hidehito*

PNC-TJ9214 89-008, 74 Pages, 1989/11

PNC-TJ9214-89-008.pdf:1.48MB

Effects of pin failure during Power-to-Melt test performed in the experimental fast reactor "JOYO" have been analyzed in the present study in order to obtain a license for the test. The accident scenario of the present study is that after a clad failure of a test pin, melted fuel is released and forms blockage of fuel and stainless steel debris in a coolant flow area of a compartment in the test assembly. The follwing subjects have been investigated in the present study. (1)Blockage in the coolant flow area. (2)Contact of melted fuel with compartment. Conclusions are summarized as follows. (1)Under a hypothetical assumption in which all 4 test pins are melted and form a blockage, if the outer surface of the compartment is cooled by Na flow of an about 2200kg/(m$$^{2}$$$$cdot$$s), the integrity of the compartment is assured. (2)If melted fuel released from the test pin directly come in contact with the inner surface of the compartment, the calculated results show that the fuel can not melt through the compartment.

JAEA Reports

Design of fuel assembly for an efficiency test of FBR fuel

*; Morii, Tadashi*; *; *; *; *; Kinjo, Hidehito*

PNC-TJ9214 88-003, 394 Pages, 1988/06

PNC-TJ9214-88-003.pdf:7.31MB

In the experimental fast reactor JOYO, two new tests programs are scheduled in near future in order to verify high-power and high-burnup capability of LMFBR fuel pins : PTM(Power-to-Melt) test and RTCB(Run-to-Cladding Breach) test. A study is performed for the license of the tests. In this study, the fuel assemblies for the PTM and RTCB tests is designed, Safety assessment for the possible events occurred in the course of the tests, namely melt of sample fuel (PTM test) and cladding breach (RTCB test) is performed. Lastly, safety assessment for the accidents occurred in the course of the tests is also performed to obtain a license. As for the PTM test, the fuel assembly is designed considering thermal expansion of fuel pins and designed in order to prevent local blockage caused by released sample fuel and hold the released fuel within the assembly in preparations for the worst case of pin failure. The effect of reactivity insert by fuel slumping and pellet-cladding mechanical interaction caused by fuel melt within the test pin occurred during the PTM test is studied to show an integrity of the test pins. Analytical results show an integrity of test pins under the conditions with superposition of anticipated transient whose possibility of occurrence is relatively high. Lastly, even if the test pin is breached to release sample fuel, the calculated radiation dose to population is shown to be sufficiently lower than the limited values. As for the RTCB test, the devices are proposed to lower the released rate of FP gas and prevent an adjacent pin failure caused by the released gas in the cource of the test. Analytical results for the event of gas impingement on the adjacent spare pins show no additional breach of those pins. Calculated results with superposition of the representative anticipated transients and accidents also show an integrity of the adjacent spare pins. The released radio-activities calculated for the above events are sufficient smaller ...

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