Criticality Evaluation for the Monju Restart Core

Hazama, Taira; Kitano, Akihiro; Kishimoto, Y.

doi:10.13182/nt12-a14097

Cited by 14 publications

(2 citation statements)

References 11 publications

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“…However, if fuel loading and/or operation of reactor would be significantly delayed, the fuel should be refabricated and reloaded because of the change on reactivity worth due to the decay of 241 Pu, whose half-life is 14.4 years, to 241 Am. In Monju, where sodium leakage accident occurred on December 1995 and start-up test is performed on May 2010, the depletion of criticality was observed [31] in the test. After the test, fuel reloading was performed on August 2010 to compensate the reactivity worth.…”

Section: Energy Security Of Plutonium Utilizationmentioning

confidence: 98%

Safety and Economics of Uranium Utilization for Nuclear Power Generation

Fukaya¹

2018

Uranium - Safety, Resources, Separation and Thermodynamic Calculation

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Safety and economics of uranium utilization for nuclear power generation were investigated and discussed. In order to sustain energy supply with nuclear power generation, uranium resources should be abundant. From the viewpoint of depletion of the resources, fast breeder reactor (FBR), which is breeder reactor of plutonium, has been developed. In this context, the uranium utilization and plutonium utilization with breeding by FBR are compared and discussed from the viewpoint of safety, sustainability, and energy security. In addition, the significance of partitioning and transmutation (P&T), which is one of the advantages of FBR, was also discussed from the viewpoint of environmental burden from radioactive waste.

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Section: Energy Security Of Plutonium Utilizationmentioning

confidence: 98%

Safety and Economics of Uranium Utilization for Nuclear Power Generation

Fukaya¹

2018

Uranium - Safety, Resources, Separation and Thermodynamic Calculation

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“…The Japanese prototype fast breeder reactor, Monju, resumed the SST in May 2010 after an interruption of 14 years. The major reactor physics parameters, such as criticality [1], control rod worth [2], isothermal temperature coefficient, [3] and feedback reactivity, were measured. This paper describes the evaluation of the feedback reactivity experiment in which the self-stability characteristics of the Monju core were confirmed [4].…”

Section: Introductionmentioning

confidence: 99%

Measurement and analysis of feedback reactivity in the Monju restart core

Kitano

Takegoshi

Hazama

2015

Journal of Nuclear Science and Technology

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The purpose of this study is to develop a feedback reactivity measurement technique in the Japanese prototype fast breeder reactor Monju and to validate calculation methodology to forecast the nuclear feedback phenomena. A feedback reactivity measurement technique has been developed based on a reactivity model featuring components that depend on the reactivity coefficients, denoted as reactor power (K R ) and reactor vessel inlet temperature (K in ). This technique can precisely measure the two reactivity components simultaneously and was applied to the feedback reactivity experiment conducted in the Monju system start-up test in May 2010. A thorough evaluation considering all possible biases and uncertainties demonstrated that the reactivity coefficients can be evaluated with a measurement uncertainty smaller than 3%. The evaluated reactivity coefficients were simulated considering the temperature distribution in the core. The calculated and measured values of K R agreed within 1%, and the value of K in was consistent with that reported in a previous isothermal temperature coefficient experiment. The measured and calculated fuel subassembly outlet temperatures also agreed well within 0.2 • C, which supports the validity of the temperature calculation.

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