JOPSS - Search Results

Journal Articles

Comparison of JSFR design with EDF requirements for future SFR

Uematsu, Mari Mariannu; Prle, G.*; Mariteau, P.*; Sauvage, J.-F.*; Hayafune, Hiroki; Chikazawa, Yoshitaka

Journal of Nuclear Science and Technology, 52(3), p.434 - 447, 2015/03

https://doi.org/10.1080/00223131.2014.953015

Times Cited Count：1 Percentile：9.71(Nuclear Science & Technology)

Electricite de France (EDF) and JAEA have signed a bilateral agreement for research and development cooperation and information exchange on future sodium-cooled fast reactors (SFR) since 2008. Within the bilateral framework, a comparison of Japan sodium-cooled fast reactor (JSFR) design with future French SFR concept has been done based on, firstly the requirement of the investor operator (EDF) of future French SFRs and secondly the French safety baseline that could be applicable to these reactors which is currently under preparation. This paper describes the comparison work results of JSFR and EDF requirements for future SFRs where the specific designs of JSFR were evaluated as interesting from EDF point of view. The comparison work pointed out the differences in safety baselines between two countries as well.

Journal Articles

Digital RF feedforward systems for beam loading compensation in JKJ synchrotrons

Tamura, Fumihiko; Yamamoto, Masanobu; Yoshii, Masahito*; Schnase, A.*; Omori, Chihiro*; Uesugi, Tomonori*

Proceedings of 8th European Particle Accelerator Conference (EPAC 2002), p.2106 - 2108, 2002/00

We present the concept and the design of the high-speed digital RF feedforward systems for beam loading compensation in the synchrotrons of JAERI-KEK Joint Project (JKJ). JKJ synchrotrons are high intensity proton synchrotrons at the energy of 3 and 50 GeV, in which beam loading compensation systems are necessary. Beam loading compensation is to be realized by full-digital RF feedforward systems. We describe the implementation details of the feedforward systems. The system consists of a down-converter, digital filters, and an up-converter. We present two possible implementations of the filters; one uses ASIC filter chips and the other uses FPGA.

JAEA Reports

Tests on decisive proof for the incinerating and melting facility using the in-can type high frequency induction heating

; ; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2000-002, 149 Pages, 1999/12

JNC-TN9410-2000-002.pdf:23.51MB

LEDF (Large Equipment Dismantling Facility) is the solid waste processing technology development facility that carries out high-volume reduction and low dosage processing. The high-volume reduction processing of the high dose -waste configured with combustible waste, pvc & rubber, spent ion exchange resin, and noncombustible waste have been planned the incinerating and melting facility using the in-can type high frequency induction heating in LEDF. This test is intended to clarify the design data. It was confirmed that the incinerating and melting performance, molten solid properties and exhaust gas processing performance with pilot testing equipment and bench scale equipment. The result of this test are as follows. (1)Processing speed is 6.7kg/h for the combustible waste, 13.0kg/h for the ion exchange resin, and 30.0kg/h for the noncombustible waste. For above optimum processing conditions are as follows. (a)Operating temperature is 1000 $^{circ}$ C for the combustible waste, 1300 $^{circ}$ C for the ion exchange resin, 1500 $^{circ}$ C for the noncombustible waste. (b)Air flow is 90Nm $^{3}$ /h. Air temperature is 300 $^{circ}$ C. Air velocity is 20m/s. (2)Incineration time per day is 5h. Warm-up time and incineration time from the stop of waste charging is 0.5h. Melting time per day is 5h inconsideration of heating hold time of incinerated ash and melting of quartz. Warm-up time is 0.5h. (3)The system decontamination factor in Co, Cs and Ce with pilot testing equipment is 10 $^{5}$ or more. (4)Design data of the iron doped silica gel judged to be have a applicability as RuO $_{4}$ gas absorber is as follows. (a)Its diameter distribute in the range of 0.8-1.7mm. (b)To have a decontamination factor of 10 $^{3}$ can achieve for retention time of 3 seconds and its life time is about 1 year. (5)In terms of the distribution of the nuclear species in molten solid is evenly distributed. It was also confirmed that the distribution of main elements in ceramic layer is ...

JAEA Reports

Parameter analysis calculation on characteristics of portable FAST reactor

PNC TN9410 98-059, 53 Pages, 1998/06

PNC-TN9410-98-059.pdf:1.23MB

The analysis program code STEDFAST; Space, TErrestrial and Deep sea FAST reactor ・gas turbine system; had been developed in PNC to get the best values of system parameters on fast reactor ・gas turbine power generation systems used as power sources for deep sea, space and terrestrial cogeneration. In this report, we performed a parameter survey analysis by using the code to study characteristics of the systems. Concerning the deep sea fast reactor ・gas turbine system, calculations with many variable parameters were performed on the base case of a NaK cooled reactor of 40kWe. We aimed at total equipment weight and surface area necessary to remove heat from the system as important values of the characteristics of the system Electric generation power and the material of a pressure hull were specially influential for the weight. The electric generation power, reactor outlet/inlet temperatures, a natural convection heat transfer coefficient of sea water were specially influential for the area. Concerning the space reactor ・gas turbine system, the calculations with the variable parameters of compressor inlet temperature, reactor outlet/inlet temperatures and turbine inlet pressure were perfomed on the base case of a Na cooled reactor of 40kWe. The first and the second variable parameters were influential for the total equipment weight of the important characteristic of the system. Concening the terrestrial fast reactor ・gas tubine system, the calculations with the variable parameters of heat transferred pipe number in a heat exchanger to produce hot water of 100 $^{circ}$ C for cogeneration, compressor stage number and the kind of primary coolant material were performed on the base case of a Pb cooled reactor of 100MWt. In the comparison of calculational results for Pb and Na of primary coolant material, The primary coolant weight flow rate was naturally large for the fomer case compared with for the latter case because density is very different between them. ...

JAEA Reports

Stationary analysis program code STEDFAST for space, terrestrial and deep sea fast reactor gas turbine power generation system (User's manual)

; Sekiguchi, Nobutada

PNC TN9520 95-002, 66 Pages, 1995/02

PNC-TN9520-95-002.pdf:2.55MB

This analysis program code STEDFAST; Space, TErrestrial and Deep sea FAST reactor gas tubine system; is used to get the adequate values of system parameters on fast reactor gas turbine power generation systems used as power sources for deep sea, space and terrestrial cogeneration. Characteristics of the code are as follows. Objective systems of the code are a deep sea, a space and a terrestrial reactors. Primary coolants of the systems are NaK, Na, Pb and Li. Secondary coolant is the mixture gas of He and Xe. The ratio of He and Xe is arbitrary. Modeling of components in the systems was performed so that detailed modeling might be capable in future and that a transient analytical code could be easily made by using the code. A progra㎜ing language is MAC-FORTRAN. The code can be easily used in a personal computer. The code made possible instant calculation of various state values in a Brayton cycle, understanding the effects of many parameters on thermal efficiency and finding the most adequate values of the parameters. From now on, detailed modeling of the components will be performed. After that, the transient program code will be made.

JAEA Reports