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Maki, Takashi*; Horiuchi, Nobutake*
JNC TJ9400 2004-004, 113 Pages, 2003/10
JNC-TJ9400-2004-004.pdf:7.52MB
The functions of the nuclear fuel cycle amount analysis code, developed in 2003 were extended. This code is a program that calculates the change in characteristics with time of mass balance (for example, the amount of natural uranium demand, plutonium mass balance, environmental load reduction, etc.) in a nuclear fuel cycle, to examine the state of future reactor types or recycling facilities. In 2003, as for this code, functions of changing FBR characteristics, calculation functions of automatic adjustment of FBR reprosseing facility capacity, recovery MA recycling, were added, and the I/O function was improved according to it. Moreover, benchmark calculation to the extended amount analysis code was performed, and it was confirmed that mass balance was calculated appropriately. Furthermore, the mass balance of a few typical FR cycle concepts was calculated in this analysis code, and the feature of each concept was clarified.
Maki, Takashi*; Horiuchi, Nobutake*
JNC TJ9400 2002-006, 79 Pages, 2002/01
JNC-TJ9400-2002-006.pdf:2.58MB
The function of the nuclear fuel cycle amount analysis code, developed in 2001 were extended. This code is a program that calculates the change in characteristics with time of mass balance (for example, the amount of natural uranium demand, plutonium mass balance, environmental load reduction, etc.) in a nuclear fuel cycle, to examine the state of future reactor types or recycling facilities. In 2002, as for this code, calculation functions of reprocessing facilities on plutonium-thermal spent fuels, recovery uranium recycling, and multiple FR concepts were added, and the I/O function was improved according to it. Moreover, benchmark calculation to the extended amount analysis code was performed using the other tool, and it was confirmed that mass balance was calculated appropriately. Furthermore, the mass balance of a few typical FR cycle concepts was calculated in this analysis code, and the feature of each concept was clarified.
Maki, Takashi*; Ichikawa, Hajime*; Asao, Takayuki*; Horiuchi, Nobutake*
JNC TJ9400 2002-004, 228 Pages, 2001/02
JNC-TJ9400-2002-004.PDF:9.97MB
We developed two computer codes to evaluate fuel cycle requirements of FR systems, which were selected in "the feasibility studies on commercialized FBR cycle systems". One code (CODE for material balance analysis) is to calculate the material balance data to evaluate the characteristics of each candidate. The other is to calculate the time-series data of material balance of fuel cycle as a whole, to evaluate an optimum scenario of FR systems introduction. The main characteristics of these codes are as follows: (1) Common function of both codes (a) They execute burn up calculation using characteristics values of reactor calculated with ORIGEN2 code. And they adjust Pu content using a concept of physical accounting method for adjusted fissile enrichment. (b) They simulate 18 type of FR systems, 10 reactor types and 6 reprocessing types. (2) Function of CODE for material balance analysis (a) It calculates nuclide inventory and thermal power, radioactivity, radio-toxicity in the waste and environmental release. (b) It evaluates safety of geological disposal of HLW and TRU waste (iodine waste) with simplified safety estimation method. (3) Function of CODE for time-series analysis (a) In addition to FR systems, it simulates 4 type of LWR systems and 5 type of Pu-Thermal LWR systems. (b)It calculates the Pu demand-and-supply situation. The precision of these codes was checked and verified by using other code result. Then we investigation characteristics of each FR system by evaluating material balance of fuel cycle. In addition we clarified differences between scenarios of introduction of FR systems.
Oyama, Koichi; Katsurai, Kiyomichi; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka; Nagata, Masanobu*; Horiuchi, Nobutake*; Chikazawa, Takahiro*; Kikuchi, Toshiaki*
no journal, ,
no abstracts in English