JAEA-Technology
2008-086
Irradiation Sample Fabrications for VHTR
-Research and Development for Advanced High Temperature
Gas-cooled Reactor Fuels and Graphite Components(Contract Research)
Yasuhiro MOZUMI, Shohei UETA, Jun AIHARAand Kazuhiro SAWA
High Temperature Fuel and Material Group
Nuclear Science and Engineering Directorate
February 2009
Japan Atomic Energy Agency
本レポートは独立行政法人日本原子力研究開発機構が不定期に発行する成果報告書です。
本レポートの入手並びに著作権利用に関するお問い合わせは、下記あてにお問い合わせ下さい。
なお、本レポートの全文は日本原子力研究開発機構ホームページ（http://www.jaea.go.jp）
より発信されています。
独立行政法人日本原子力研究開発機構
〒319-1195
研究技術情報部
研究技術情報課
茨城県那珂郡東海村白方白根 2 番地 4
電話 029-282-6387, Fax 029-282-5920, E-mail:[email protected]
This report is issued irregularly by Japan Atomic Energy Agency
Inquiries about availability and/or copyright of this report should be addressed to
Intellectual Resources Section, Intellectual Resources Department,
Japan Atomic Energy Agency
2-4 Shirakata Shirane, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 Japan
Tel +81-29-282-6387, Fax +81-29-282-5920, E-mail:[email protected]
© Japan Atomic Energy Agency, 2009
Irradiation Sample Fabrications for VHTR
- Research and Development for Advanced High Temperature Gas-cooled Reactor Fuels
and Graphite Components (Contract Research)
Yasuhiro MOZUMI̪1, Shohei UETA, Jun AIHARA and Kazuhiro SAWA
Nuclear Applied Heat Technology Division,
Nuclear Science and Engineering Directorate,
Japan Atomic Energy Agency
Oarai-machi, Higashiibaraki-gun, Ibaraki-ken
(Received December 10, 2008)
Fuel for the Very High Temperature Reactor (VHTR) is required to be used under
severer irradiation conditions and higher operational reactor temperatures than those of
present high temperature gas cooled reactors. Japan Atomic Energy Agency has developed
the advanced silicon carbide (SiC) -coated fuel particles having thicker layer thicknesses,
and zirconium carbide (ZrC)-coated particles that are expected to preserve their integrity
at higher temperatures and burnup conditions than current conventional coated fuel
particles. These particles have been fabricated successfully in order to perform irradiation
tests at experimental reactors. This paper is summarized fabrication data of irradiation
samples.
Keywords: Very High Temperature Reactor (VHTR), Advanced Silicon Carbide (SiC)
-coated Fuel Particles, Zirconium Carbide (ZrC)-coated Particles, Irradiation Sample
This work was performed by the Ministry of Education, Culture, Sports, Science and
Technology of Japan (MEXT) under contract with Japan Atomic Energy Agency.
̪1
Collaborating Engineer
⿥㜞᷷ࠟࠬἹߩߚ߼ߩᾖ኿ࠨࡦࡊ࡞⵾ㅧ 㕟ᣂ⊛㜞᷷ࠟࠬἹΆᢱ࡮㤥㋦ߦ㑐ߔࠆᛛⴚ㐿⊒
ฃ⸤⎇ⓥ
ᣣᧄේሶജ⎇ⓥ㐿⊒ᯏ᭴
ේሶജၮ␆Ꮏቇ⎇ⓥㇱ㐷
ᩭᾲᔕ↪Ꮏቇ࡙࠾࠶࠻
⨃૑ ᵏኡ̪‫ޔ‬ᬀ↰ ␽ᐔ‫⋧ޔ‬ේ ⚐‫ޔ‬ᴛ ๺ᒄ
ᐕ ᦬ ᣣ ฃℂ
⿥㜞᷷ࠟࠬἹ㧔㪭㪟㪫㪩㧕ߩΆᢱߪ‫⃻ޔ‬࿷ߩ㜞᷷ࠟࠬἹࠃࠅㆊ㉃ߥᾖ኿ⅣႺߢ߆ߟࠃࠅ㜞᷷ਅߢ
૶↪ߐࠇࠆ‫ޕ‬ේሶജᯏ᭴ߪ‫ⴕ⃻ޔ‬Άᢱࠃࠅఝࠇ㜞᷷߆ߟ㜞Ά὾ᐲߦ⠴߃߁ࠆߣᦼᓙߐࠇࠆ㜞ᕈ
⢻ߢෘ⡺ߥ὇ൻࠤࠗ⚛㧔㪪㫀㪚㧕ⵍⷒΆᢱ☸ሶ߿὇ൻࠫ࡞ࠦ࠾࠙ࡓ㩿㪱㫉㪚㪀ⵍⷒ☸ሶࠍ㐿⊒ߒߡ޿ࠆ‫ޕ‬
⹜㛎Ἱߢᾖ኿⹜㛎ࠍታᣉߔࠆߚ߼ߩ‫ࠄࠇߎޔ‬㜞ᕈ⢻ߥ὇ൻࠤࠗ⚛㧔㪪㫀㪚㧕ⵍⷒΆᢱ߿὇ൻࠫ࡞ࠦ
࠾࠙ࡓ㩿㪱㫉㪚㪀ⵍⷒ☸ሶߩ⵾ㅧߦᚑഞߒߚ‫ޕ‬㩷
ᧄႎߪ‫ޔ‬ᾖ኿⹜ᢱߩ⵾ㅧ࠺࡯࠲ࠍ߹ߣ߼ߚ߽ߩߢ޽ࠆ‫ޕ‬
ᧄႎ๔ᦠߪᢥㇱ⑼ቇ⋭߇ᣣᧄේሶജ⎇ⓥ㐿⊒ᯏ᭴ߣߩ
ᆔ⸤⎇ⓥᄾ⚂ߦࠃࠅታᣉߒߚ⎇ⓥ
ᬺോᚑ
ᨐߦ㑐ߔࠆ߽ߩߢ޽ࠆ‫ޕ‬
ᄢᵞ⎇ⓥ㐿⊒࠮ࡦ࠲࡯㧔㚢࿷㧕㧦‫⨙ ޥ‬ၔ⋵᧲⨙ၔ㇭ᄢᵞ↸ᚑ↰↸ ̪
ᛛⴚ㐿⊒දജຬ
Contents
1.
Introduction --------------------------------------------------------------------------------------------------- 1
2.
Fabrication of advanced SiC-TRISO fuel ------------------------------------------------------------ 2
2.1 Fabrication processes of the VHTR fuel elements ---------------------------------------------- 2
2.2 UO2 kernels fabrication process ---------------------------------------------------------------------- 2
2.3 PyC and SiC coating processes ----------------------------------------------------------------------- 2
2.4 Manufacture process of fuel compacts-------------------------------------------------------------- 2
2.5 Specifications and fabrication of advanced fuels for an irradiation test----------------- 3
3.
Fabrication of ZrC coated particles -------------------------------------------------------------------- 4
3.1 ZrC coating by bromide process ---------------------------------------------------------------------- 4
3.2 Coating equipment --------------------------------------------------------------------------------------- 4
3.3 Fabrication of ZrC coated particles for irradiation tests ------------------------------------- 5
4.
Conclusion ----------------------------------------------------------------------------------------------------- 6
Acknowledgements ----------------------------------------------------------------------------------------------- 6
References ----------------------------------------------------------------------------------------------------------- 7
⋡
ᰴ
1.
ᐨ⺰ -------------------------------------------------------------------------------------------------------------- 1
2.
ᡷ⦟ SiC TRISO Άᢱߩ⵾ㅧ ------------------------------------------------------------------------------ 2
2.1 VHTR Άᢱⷐ⚛ߩ⵾ㅧᎿ⒟ ----------------------------------------------------------------------------- 2
2.2 Άᢱᩭ⵾ㅧᎿ⒟ -------------------------------------------------------------------------------------------- 2
2.3 PyC‫ޔ‬SiC ⤑⫳⌕Ꮏ⒟ ------------------------------------------------------------------------------------ 2
2.4 Άᢱࠦࡦࡄࠢ࠻⵾ㅧᎿ⒟ --------------------------------------------------------------------------------- 2
2.5 ᾖ኿⹜㛎↪ᡷ⦟Άᢱߩࠬࡍ࠶ࠢߣ⵾ㅧ -------------------------------------------------------------- 3
3.
ZrC ☸ሶߩ⵾ㅧ ----------------------------------------------------------------------------------------------- 4
3.1 ⥇⚛ᴺߦࠃࠆ ZrC ⫳⌕ ---------------------------------------------------------------------------------- 4
3.2 ⫳⌕ⵝ⟎ ----------------------------------------------------------------------------------------------------- 4
3.3 ᾖ኿⹜㛎↪ ZrC ⫳⌕☸ሶߩ⵾ㅧ ---------------------------------------------------------------------- 5
4.
⚿⺰ -------------------------------------------------------------------------------------------------------------- 6
⻢ㄉ -------------------------------------------------------------------------------------------------------------------- 6
ෳ⠨ᢥ₂ -------------------------------------------------------------------------------------------------------------- 7
1. Introduction
Current high-temperature gas-cooled reactor (HTGR) uses Triso-coated fuel
particles as shown in Fig. 1.
The Triso-coated fuel particle consists of a micro spherical
kernel of oxide or oxycarbide fuel and coating layers of porous pyrolytic carbon (buffer),
inner dense pyrolytic carbon (IPyC), silicon carbide (SiC) and outer dense pyrolytic carbon
(OPyC).
The principal function of these coating layers is to retain fission products within
the particle.
Particularly, the SiC coating layer acts as a barrier against the diffusive
release of metallic fission products which escape easily through the IPyC layer and
provides mechanical strength for the particle.
The Very-High-Temperature Reactor (VHTR) is one of the most promising
candidates for the Generation IV Nuclear Energy System [1].
The VHTR demands the gas
outlet temperature of approximately 1000°C for supplying electricity and process heat, e.g.,
for hydrogen production, as proposed in the Generation-IV International Forum [1].
The
VHTR fuel is required to have excellent safety performance up to burn-ups of about 15 to
20% fissions per initial metal atom (FIMA) and fluences of 6×1025 n/m2 (E>0.1 MeV) [1].
Although SiC has excellent properties, it gradually loses strength due to neutron
irradiation and mechanical integrity at very high temperatures, especially above 1700°C,
by thermal dissociation[2-4]. In the other side zirconium carbide (ZrC) is known as a
refractory and chemically stable compound, having a melting point of 3540 °C, and a
eutectic melting point with carbon of 2850°C.
JAEA has planed to irradiate the advanced silicon carbide (SiC) fuels having
thicker layer thicknesses at OSIRIS reactor in France near future. And also we have joined
the irradiation tests of ZrC-coated particles both High Flux Isotope Reactor (HFIR) in Oak
Ridge National Laboratory (ORNL) and High Flux Reactor (HFR) in The Nuclear Research
& consultancy Group (NRG).
The object of this paper is summarized fabrication data for advanced SiC fuel and
ZrC coated particles for VHTR developments.
2. Fabrication of advanced SiC-TRISO fuel
2.1 Fabrication processes of the VHTR fuel elements
The VHTR fuel fabrication process consists of three parts: (1) UO2 kernels
fabrication process, (2) PyC and SiC coating processes, (3) Manufacture process of Fuel
compacts. These processes are described below.
2.2 UO2 kernels fabrication process
The UO2 kernels are fabricated in a gel-precipitation process. The process is
shown in Fig. 2[5]. After formation of uranyl nitrate solution containing additives,
spherical droplets are generated at the vibrating nozzles and fall into ammonia water to be
aged to ammonium diuranate (ADU) particles. The reaction products of ammonium nitrate
etc. are washed off, then the particles are dried and calcinated to UO3 particles at 500͠ in
air. UO3 particles are reduced and sintered to UO2 particles with about 97%T.D. at 1600͠
under hydrogen atmosphere[5].
2.3 PyC and SiC coating processes
Figure 3 [5] shows the fabrication flow diagram of coated fuel particles. Coating
layers are deposited on the kernels in a chemical vapor deposition (CVD) process using a
fluidized bed type of coater.
The Tri-isotropic (TRISO) coating process is divided into four
coating processes for the porous PyC, IPyC, SiC and final OPyC layers. Mixing gases of
acetylene (C2H2) and argon (Ar) are used for the deposition of porous and low density PyC
for the first layer; propylene (C3H6) and Ar for the deposition of dense PyC for the second
and fourth layer; methyl-trichloro-silane (MTS) and hydrogen for the deposition of SiC for
the third layer [5].
2.4 Manufacture process of fuel compacts
Figure 4 [5] shows the manufacture process of fuel compacts. First, natural
graphite powder, electro-graphite powder and a binder are mixed, and then the mixture
makes graphite matrix after fine grinding process. Coated fuel particles are over-coated
with the graphite matrix and warm-pressed to make annular cylinder of green compacts.
Green compacts are preliminarily heat treated for carbonization at 800͠ under nitrogen
atmosphere, then sintered at 1800͠ under vacuum to make fuel compacts[5].
2.5 Specifications and Fabrication of advanced fuels for an irradiation test
The Specifications of advanced UO2 Kernel, coated fuel particle (CFP) and compact are
described on Table 1 compared with first HTTR fuels. Advanced fuels are improved the
SiC thicker layer thickness against a high internal pressure of FP and CO gases with
higher burnup. Also the fuel kernel become smaller and a buffer become bigger against an
accumulated gas pressure. The advanced SiC-coated fuels have been fabricated
successfully at Nuclear Fuel Industries (NFI) based on the specifications and processes
described above sections. A typical appearance of a fuel compact is shown at Fig.5. These
fuels will be used the irradiation test at OSIRIS reactor near future for the VHTR
developments.
3. Fabrication of ZrC coated particles
3.1 ZrC coating by bromide process
In previous studies in JAEA, some coating techniques of ZrC have been examined
by the chemical vapor deposition (CVD) using zirconium halide vapors such as iodide,
chloride and bromide [6].
From the experimental results, it was concluded that the
bromide process was preferred to other halide processes experimentally, because it was
found to be easier to produce a stoichiometric composition of ZrC.
In the bromide process, the ZrC-coating layer is deposited with pyrolytic reaction
of ZrBr4, CH4 and H2 at about 1500°C in a fluidized bed.
Main reactions of the bromide
process can be described as follows [6]:
[CH4] = (C) + 2[H2]
(1)
[ZrBr4] + [H2] ń [ZrBr3], [ZrBr2] + [HBr]
(2)
[ZrBrx] + (C) = (ZrC) + x [Br], x=2, 3, or 4
(3)
[Br] + 0.5[H2] = [HBr]
(4)
0.25(C) + [HBr] = 0.25 [CH4] + [Br].
(5)
(In above equations, solid and gas phases are expressed in parentheses and square
brackets, respectively.)
3.2 Coating equipment
ZrC coater was constructed at Oarai Research and Development Center of JAEA as
shown in Figs. 6 and 7.
The ZrC coater was designed with the maximum batch size of 0.2
kg, which is about ten times larger than the previous device used.
The ZrC coater mainly consists of the gas supply equipment, the CVD coater, and
the off-gas combustion equipment.
In the gas supply system, liquid bromine is vaporized
with argon as carrier gas at a temperature of 0 oC, and the bromine gas is introduced into
the CVD coater from the bottom.
transferred into the coater.
A gas mixture of methane and hydrogen is also
The CVD coater is composed of the lower and the upper
heaters with in-line configuration to trigger ZrC reaction as described in Eqs. (1)- (4).
The
introduced bromine gas reacts with metallic zirconium sponge loaded in the lower heater,
and then produces ZrBrx gases at about 600oC.
The upper heater has a particle fluidizing
bed, and ZrC is coated on the surface of the particle at 1600oC in the maximum.
off-gas treatment equipment removes soot, hydrogen bromide, and residual hydrogen.
The
3.3 Fabrication of ZrC coated particles for irradiation tests
To investigate the fundamental irradiation properties of ZrC, PyC and SiC using
several irradiation temperatures under VHTR operating conditions, JAEA has joined the
irradiation tests both HFIR in ORNL and HFR in NRG with the total of 18 kinds of particle
samples. The fabricated irradiation samples are summarized at Table 2. These consist of
Type 1) 5 kinds of inner IPyC /ZrC coatings with ZrO2 kernels, Type 2) 4 kinds of IPyC/ZrC
coatings with Al2O3 kernels, Type 3) IPyC/SiC/OPyC coatings with SiC kernels and Type 4)
ZrO2 and Type 5) Al2O3 kernels without coating and Type 6) 4 kinds of IPyC /ZrC/OPyC
coatings with ZrO2 kernels.
oC
The irradiation conditions 800 and 900 oC, 1100 oC and 1200
over 2 x 1025 m-2 of fast neutron fluences are selected for JAEA samples in the tests.
For the Type 1) and 2), 6)as shown in Fig. 8 [7], ZrC-coating layer is known as the
most pronounced candidate for the advanced fuel particle used in VHTR.
In the viewpoint
of the coating material, it is essential for the ZrC coating layer to have the stoichiometric
composition (of which the carbon to zirconium atomic ratio, (C/Zr) is nearly 1.0), because it
shows higher performances with regards to a mechanical integrity, a thermal conductivity
and a fission product retention under irradiations than those of one with C/Zr>1.0.
The
ZrC with C/Zr>1.0 has so-called free carbons as shown in Fig. 9. In the irradiation test, ZrC
coatings with some different C/Zr ratio in the range of 1.0 to 1.3 are irradiated in order to
study the irradiation effect on ZrC coatings, mainly for mechanical properties such as the
hardness and strengths, for the microstructure of both ZrC and free carbons.
In addition
to the actual industrial viewpoint the coated fuel particle should be received a heat
treatment to form the fuel compact, the heated ZrC coated particles at 1,800 oC are also
irradiated to compare its behavior with non-heated ones.
The type 3) is SiC-TRISO particles with OPyC coating to compare PyC or SiC
properties under the irradiation (a microstructure, PyC dimensional change, PyC
anisotropy, etc.) with other samples.
Types 4) and 5) are two substrate kernels used for
JAEA samples in order to obtain the background data mainly for a dimensional change of
each particle under the irradiation.
For making PIEs easier, the some of these particles
used highly purified Al2O3 kernels to reduce radioactivities comparing with ZrO2 after the
irradiation.
4. Conclusion
The advanced SiC-coated fuel particles have been fabricated successfully in order
to perform irradiation tests at experimental reactors.
JAEA has developed the ZrC coating conditions under which uniform ZrC coating
layers can be obtained by using the new large-scale coater up to 0.2 kg batch.
ZrC coated
particles were successfully fabricated. These samples have been irradiated at experimental
reactors.
Acknowledgements
The present study is the result of “Research and development for advanced high
temperature gas cooled reactor fuels and graphite components” entrusted to the Japan
Atomic Energy Research Institute by the Ministry of Education, Culture, Sports, Science
and Technology of Japan (MEXT).
The authors are indebted to Dr. T. Ogawa, Dr. K.
Minato and Dr. M. Ogawa from JAEA for their valuable advices, Mr. A. Yasuda of JAEA, Mr.
T. Sekita and Mr. T. Ebisawa from Nuclear Fuel Industries, Ltd., Mr. T. Nemoto from
Kaken Laboratory, Co. and Mr. T. Tobita from Nuclear Engineering, Co. for obtaining the
experimental data, and Mr. T. Iyoku from JAEA for helpful comments in preparing this
paper.
References
[1] U.S.DOE Nuclear Energy Research Advisory Committee and the Generation IV
International Forum, 03-GA500034-08(2004).
[2] Y. Kurata, K. Ikawa, K. Iwamoto, J. Nucl. Mater. 92 (1980) 351.
[3] H. Nabielek, W. Schenk, W. Heit, et al., Nucl. Technol., 84 (1989) 62.
[4] D. T. Goodin, J. Am. Ceram. Soc., 65 (1982) 238.
[5]S.KATO et al., Fabrication of HTTR first loading fuel, IAEA-TECDOC-1210, April 2001.
[6] T. Ogawa, K. Ikawa, K. Iwamoto, J. Nucl. Mater. 97 (1981) 104.
[7] Ueta, S. et al., Development on fabrication and inspection techniques for the ZrC-coated
fuel particle as an advanced high temperature gas cooled reactor fuel, Hyomen(Surface),
vol. 46 ,no. 4, 2008, p.222-232. (In Japanese)
Table 1 The specification of the Advanced fuel for irradiation tests planed at OSIRIS
Item
Advanced fuel
1st HTTR Fuel for
Sampling rate
reference
Fuel kernel
235
U enrichment (%)
Diameter (Pm)
9.9
3.4-9.9
500
600
1 sample/enrichment
1 sample (50 particles)
/fuel kernel lot
Sphericity
95% <1.2
95% <1.2
3 samples
(100particles/sample)
Density
(g/cm3)
10.63
10.63
3 samples/fuel kernel
lot
O/ U ratio
2.00
2.00
1 sample/fuel kernel
lot
CFP
Layer thickness
Buffer (Pm)
95
60
1 sample (50 particles)
/CFP lot
I-PyC (Pm)
40
30
1 sample (50 particles)
/CFP lot
SiC (Pm)
35
25
1 sample (50 particles)
/CFP lot
O-PyC (Pm)
40
45
1 sample (50 particles)
/CFP lot
Fuel compact
Packing fraction (%)
25
30
3 samples/ fuel
compact lot
Dimensions
Outer Diameter (mm)
10
26
All fuel compacts
Inner Diameter (mm)
2
10
All fuel compacts
Length
12
39
All fuel compacts
(mm)
Table 2
No.
Type of particles
Coated particles for irradiation tests at HFR and HFIR Particle
Material
D(Pm)
ZrO2
1
843
2
3
Same as No.1 sample
ZrO2+PyC+ZrC
(ZrO2 kernel with
4.82% Y2O3)
841
4*
7
8
858
ZrO2
PyC
720(diameter)
35
6.07
1.9
ZrC
21
6.01
759(diameter)
12
38
45
Around1.9
932
ZrO2with
4.82%Y2O3
724
ZrO2
724(diameter)
6.07
Al2O3
PyC
ZrC
755(diameter)
42
24
3.89
1.9
6.5
1.84
3.2
1.85
Same as No.9sample
Al2O3+PyC+ZrC
(99.99% Al2O3
kernel )
744
Al2O3
PyC
ZrC
642(diameter)
33
9
3.89
1.9
6.5
Same as No.11sample
12
13
6.07
1.9
6.5
SiC
PyC
SiC
PyC
902
11
720(diameter)
35
28
PyC+SiC
(SiC kernel)
9
10
ZrO2
PyC
ZrC
Same as No.3 sample
5*
6
PyC
ZrC
Size or
Density
thickness
(g/cm3)
(Pm)
720(diameter)
6.07
35
1.9
22
6.45
Al2O399.99%
642
Al2O3
642(diameter)
3.89
895
ZrO2
IPyC
ZrC
OPyC
720(diameter)
35
21
24
6.07
1.9
6.52
1.9
14
15*
16*
17*
Same as No.15 sample
ZrO2+IPyC
+ZrC+OPyC
(ZrO2 kernel with
4.82% Y2O3)
902
18*
ZrO2
IPyC
ZrC
OPyC
720(diameter)
35
27
25
6.07
1.9
6.52
1.92
Same as No.17 sample
Remarks
lot
C/Zr=1.11
as fabricated
ZrC-06-2022
C/Zr=1.11
heat treatment at
about 1800 oC
ZrC-06-2022HT
C/Zr=1.03
as fabricated
ZrC-06-2048
C/Zr=1.03
heat treatment at
about 1800 oC
ZrC-06-2048HT
C/Zr=1.35
heat treatment at
about 1800 oC
ZrC-06-2003HT
as fabricated
91SiCCP
heat treatment at
about 1800 oC
ZCP-06-M01HT
as received
ZCP-06-M01
C/Zr=1.1
as fabricated
ZrC-Al-2003
C/Zr=1.1
heat treatment at
about 1800 oC
ZrC-Al-2003HT
C/Zr=1.1
as fabricated
ZrC-Al-2001
C/Zr=1.1
heat treatment at
about 1800 oC
ZrC-Al-2001HT
heat treatment at
about 1800 oC
7001(600-710)HT
as received
7001(600-710)
C/Zr=1.03
as fabricated
ZrC-07-3002
C/Zr=1.03
heat treatment at
about 1800 oC
ZrC-07-3002HT
C/Zr=1.03
as fabricated
ZrC-07-3010
C/Zr=1.03
heat treatment at
about 1800 oC
ZrC-07-3010HT
㧖Irradiation samples both HFR and HFIR
UO2 kernel
IPyC layer
Buffer layer
SiC layer
OPyC layer
Fig. 1 Triso-coated particle fuel
Additives
Uranyl nitrate
Additives
Uranyl nitrate
UO2 (NO3 )2
Mixing
Mixing
Vessel
P
Dropping
Storage
Vessel
Aging
Flow rate
controller
oscillator
Washing
vibrataing
nozzle
P
Drying
stroboscope
NH3 gas
ADU particle
Fluidized
column
Calcinating
P
UO3 particle
steam
exhaust
Sintering
UO2 kernel
Collecting Vessel
Fig. 2 UO2 kernels fabrication process [5]
Fig. 3 Fabrication process of UO2 kernels
7 1 MGTPGNU
(KTUVNC[GTEQCVKPI
. QY density
FGPUKV[pyrocarbon)
R[TQECTDQP
(Low
% * # T
Window
Gas outlet
Graphite heater
Heat
insulator
Reactor tube
Pyrometer
cupples
Thermo
5GEQPFNC[GTEQCVKPI
(High
density
pyrocarbon)
JKIJFGPUK
V[R[T
QECTDQP
% * # T
Particles
Fluidized
and Coating
gases
6JKTFNC[GTEQCVKPI
5KNKEQPECTDKFG
SiCl
+H2)
%(CH
* 35K
% N3*
Cooling
water
Gas
inlet nozzle
Particle dischargecan
% QCVGT
Fourth layer coating
(high density pyrocarbon)
C3H6+Ar
TRISO type coated fuel particles
Polished
cross section of coated fuel particle
Fig. 4 Fabrication
process
of processes
coated fuel
Fig. 3 PyC and
SiC coating
[5] particle
Coated fuel particle
Graphite powder
Binder
Mixing
Overcoating
Drying
preheating
Overcaoted
Over
coated particle
particle
Charge
Weighing
Weighting
Pressing
Green compact
Carobonization
Carbonization
Degassing
Numbering
A1234
Green
compact
Fuel compact
Automatical pressing system
ofoffuel
Fig. 5 Fig.
Fabrication
process
4 Manufacture
process
Fuelcompact
Compacts [5]
Pressing
Discharge
Fig. 5 Appearance of a fuel compact Upper heater for
ZrC deposition
Lower heater for
ZrBrx production
Fig. 6 Appearance of the CVD coater.
Off gas combustion equipment
Exhaust gas
Upper heater
with a particle
H2 combustor
fluidizing bed
Soot filter HBr absorber
Lower heater
loaded metallic
zirconium
Br2 + Ar
CH4 + H2
CVD coater
Bromine vaporizer
Gas supply equipment
Fig. 7 Process flow diagram of ZrC coater.
(b)
(a)
(c)
1000Pm
10Pm
Fig. 8 (a) Appearance and (b) (c) cross sections of ZrC coated particles. [7]
Growth direction
Near the surface of the
ZrC coated particle
Free carbon
1Pm
Fig. 9 STEM dark field (HAADF) image of ZrC coating layer with free carbon having high
carbon peak by EDX
‫ޓ‬࿖㓙න૏♽㧔5+㧕
⴫㧝㧚SI ၮᧄන૏
SI ၮᧄන૏
ၮᧄ㊂
ฬ⒓
⸥ภ
㐳
ߐࡔ ࡯࠻࡞ m
⾰
㊂ ࠠࡠࠣ࡜ࡓ kg
ᤨ
㑆
⑽
s
㔚
ᵹࠕ ࡦࡍࠕ A
ᾲജቇ᷷ᐲ ࠤ ࡞ ࡆ ࡦ K
‛ ⾰㊂ࡕ
࡞ mol
శ
ᐲ ࠞ ࡦ ࠺ ࡜ cd
㕙
૕
ㅦ
ട
ᵄ
ኒ
㕙
Ყ
㔚
⏛
㊂
⾰
ノ
ዮ
Ყ
⴫㧞㧚ၮᧄන૏ࠍ↪޿ߡ⴫ߐࠇࠆSI⚵┙න૏ߩ଀
SI ၮᧄන૏
⚵┙㊂
ฬ⒓
⸥ภ
Ⓧ ᐔᣇࡔ࡯࠻࡞
m2
Ⓧ ┙ᴺࡔ࡯࠻࡞
m3
ߐ 㧘 ㅦ ᐲ ࡔ࡯࠻࡞Ფ⑽
m/s
ㅦ
ᐲ ࡔ࡯࠻࡞Ფ⑽Ფ⑽
m/s2
ᢙ Ფࡔ࡯࠻࡞
m-1
ᐲ 㧘⾰㊂ ኒ ᐲ ࠠࡠࠣ࡜ࡓᲤ┙ᣇࡔ࡯࠻࡞
kg/m3
Ⓧ
ኒ
ᐲ ࠠࡠࠣ࡜ࡓᲤᐔᣇࡔ࡯࠻࡞
kg/m2
૕
Ⓧ ┙ᣇࡔ࡯࠻࡞Ფࠠࡠࠣ࡜ࡓ
m3/kg
ᵹ
ኒ
ᐲ ࠕࡦࡍࠕᲤᐔᣇࡔ࡯࠻࡞
A/m2
⇇ ߩ ᒝ ߐ ࠕࡦࡍࠕᲤࡔ࡯࠻࡞
A/m
Ớ ᐲ (a) 㧘 Ớ ᐲ ࡕ࡞Ფ┙ᣇࡔ࡯࠻࡞
mol/m3
㊂
Ớ
ᐲ ࠠࡠࠣ࡜ࡓᲤ┙ᴺࡔ࡯࠻࡞
kg/m3
ᐲ ࠞࡦ࠺࡜Ფᐔᣇࡔ࡯࠻࡞
cd/m2
1
᛬
₸ (b) 㧔ᢙሼߩ㧕‫ޓ‬㧝
(b)
㧔ᢙሼߩ㧕‫ޓ‬㧝
1
ㅘ ⏛ ₸
ਸ਼ᢙ‫ޓ‬
1024
1021
1018
1015
1012
109
106
103
102
101
㉄
⚛
ᵴ
ᕈ ࠞ࠲࡯࡞
kat
⸥ภ
d
࠯
࠲
ࠛ ࠢ ࠨ
㨆
㧱
10-2
࠮ ࡦ ࠴
ࡒ
࡝
c
m
ࡍ
࠹
࠲
࡜
㧼
㨀
μ
n
ࠡ
ࡔ
ࠟ
ࠟ
㧳
㧹
ࡑࠗࠢࡠ
ࡁ
10-9 ࠽
ࠦ
10-12 ࡇ
10-15 ࡈࠚࡓ࠻
ࠠ
ࡠ
ࡋ ࠢ ࠻
࠺
ࠞ
㨗
㨔
࠻
10-18 ࠕ
10-21 ࠯ ࡊ ࠻
10-24 ࡛ ࠢ ࠻
a
z
y
ᣣ
ᐲ
ಽ
da
d
°
’
⑽
ࡋࠢ࠲࡯࡞
࡝࠶࠻࡞
SIၮᧄන૏ߦࠃࠆ
⴫ߒᣇ
m/m
2/ 2
m m
s-1
m kg s-2
m-1 kg s-2
m2 kg s-2
m2 kg s-3
sA
m2 kg s-3 A-1
m-2 kg-1 s4 A2
m2 kg s-3 A-2
m-2 kg-1 s3 A2
m2 kg s-2 A-1
kg s-2 A-1
m2 kg s-2 A-2
K
cd
m-2 cd
s-1
10-3
10-6
p
f
1 d=24 h=86 400 s
1°=(Ǒ/180) rad
1’=(1/60)°=(Ǒ/10800) rad
”
1”=(1/60)’=(Ǒ/648000) rad
ha 1ha=1hm2=104m2
L㧘l 1L=11=1dm3=103cm3=10-3m3
t
1t=103 kg
࠻ࡦ
⴫㧣㧚SIߦዻߐߥ޿߇‫ޔ‬SIߣ૬↪ߐࠇࠆන૏ߢ‫ޔ‬SIන૏ߢ
⴫ߐࠇࠆᢙ୯߇ታ㛎⊛ߦᓧࠄࠇࠆ߽ߩ
ฬ⒓
⸥ภ
SI න૏ߢ⴫ߐࠇࠆᢙ୯
1eV=1.602 176 53(14)×10-19J
㔚 ሶ ࡏ ࡞ ࠻
࠳ ࡞ ࠻ ࡦ
⛔৻ේሶ⾰㊂න૏
eV
Da
u
1Da=1.660 538 86(28)×10-27kg
1u=1 Da
ᄤ
ua
1ua=1.495 978 706 91(6)×1011m
ᢥ
න
૏
⴫㧤㧚SIߦዻߐߥ޿߇‫ޔ‬SIߣ૬↪ߐࠇࠆߘߩઁߩන૏
ฬ⒓
⸥ภ
SI න૏ߢ⴫ߐࠇࠆᢙ୯
ࡃ
࡯
࡞ bar 㧝bar=0.1MPa=100kPa=105Pa
᳓㌁ᩇࡒ࡝ࡔ࡯࠻࡞ mmHg 1mmHg=133.322Pa
m2 s-2
m2 s-2
s-1 mol
(a)SIធ㗡⺆ߪ࿕᦭ߩฬ⒓ߣ⸥ภࠍᜬߟ⚵┙න૏ߣ⚵ߺวࠊߖߡ߽૶↪ߢ߈ࠆ‫ߒ߆ߒޕ‬ធ㗡⺆ࠍઃߒߚන૏ߪ߽ߪ߿
‫ޕ޿ߥߪߢ࠻ࡦ࡟࡯ࡅࠦޓ‬
(b)࡜ࠫࠕࡦߣࠬ࠹࡜ࠫࠕࡦߪᢙሼߩ㧝ߦኻߔࠆන૏ߩ․೎ߥฬ⒓ߢ‫ޔ‬㊂ߦߟ޿ߡߩᖱႎࠍߟߚ߃ࠆߚ߼ߦ૶ࠊࠇࠆ‫ޕ‬
‫ޓ‬ታ㓙ߦߪ‫⸥ߪߦᤨࠆߔ↪૶ޔ‬ภrad෸߮sr߇↪޿ࠄࠇࠆ߇‫ޔ‬⠌ᘠߣߒߡ⚵┙න૏ߣߒߡߩ⸥ภߢ޽ࠆᢙሼߩ㧝ߪ᣿
‫ޕ޿ߥࠇߐ␜ޓ‬
(c)᷹శቇߢߪࠬ࠹࡜ࠫࠕࡦߣ޿߁ฬ⒓ߣ⸥ภsrࠍන૏ߩ⴫ߒᣇߩਛߦ‫⛽߹߹ߩߘޔ‬ᜬߒߡ޿ࠆ‫ޕ‬
(d)ࡋ࡞࠷ߪ๟ᦼ⃻⽎ߦߟ޿ߡߩߺ‫ߪ࡞࡟ࠢࡌޔ‬᡼኿ᕈᩭ⒳ߩ⛔⸘⊛ㆊ⒟ߦߟ޿ߡߩߺ૶↪ߐࠇࠆ‫ޕ‬
(e)࠮࡞ࠪ࠙ࠬᐲߪࠤ࡞ࡆࡦߩ․೎ߥฬ⒓ߢ‫ࠬ࠙ࠪ࡞࠮ޔ‬᷷ᐲࠍ⴫ߔߚ߼ߦ૶↪ߐࠇࠆ‫ࠬ࠙ࠪ࡞࠮ޕ‬ᐲߣࠤ࡞ࡆࡦߩ
‫ ޓ‬න૏ߩᄢ߈ߐߪห৻ߢ޽ࠆ‫ޔߡߞ߇ߚߒޕ‬᷷ᐲᏅ߿᷷ᐲ㑆㓒ࠍ⴫ߔᢙ୯ߪߤߜࠄߩන૏ߢ⴫ߒߡ߽หߓߢ޽ࠆ‫ޕ‬
(f)᡼኿ᕈᩭ⒳ߩ᡼኿⢻㧔activity referred to a radionuclide㧕ߪ‫”ߢ⺆↪ߚߞ⺋߫ߒ߫ߒޔ‬radioactivity”ߣ⸥ߐࠇࠆ‫ޕ‬
(g)න૏ࠪ࡯ࡌ࡞࠻㧔PV,2002,70,205㧕ߦߟ޿ߡߪCIPM൘๔2㧔CI-2002㧕ࠍෳᾖ‫ޕ‬
⴫㧠㧚න૏ߩਛߦ࿕᦭ߩฬ⒓ߣ⸥ภࠍ฽߻SI⚵┙න૏ߩ଀
SI ⚵┙න૏
⚵┙㊂
SI ၮᧄන૏ߦࠃࠆ
ฬ⒓
⸥ภ
⴫ߒᣇ
-1
☼
ᐲ ࡄࠬࠞ࡞⑽
Pa s
m kg s-1
2
-2
ജ ߩ ࡕ ࡯ ࡔ ࡦ ࠻ ࠾ࡘ࡯࠻ࡦࡔ࡯࠻࡞
Nm
m kg s
⴫
㕙
ᒛ
ജ ࠾ࡘ࡯࠻ࡦᲤࡔ࡯࠻࡞
N/m
kg s-2
ⷺ
ㅦ
ᐲ ࡜ࠫࠕࡦᲤ⑽
rad/s
m m-1 s-1=s-1
ⷺ
ട
ㅦ
ᐲ ࡜ࠫࠕࡦᲤ⑽Ფ⑽
rad/s2
m m-1 s-2=s-2
ᾲ ᵹ ኒ ᐲ , ᡼ ኿ ᾖ ᐲ ࡢ࠶࠻Ფᐔᣇࡔ࡯࠻࡞
kg s-3
W/m2
ᾲ ኈ ㊂ , ࠛ ࡦ ࠻ ࡠ ࡇ ࡯ ࠫࡘ࡯࡞Ფࠤ࡞ࡆࡦ
J/K
m2 kg s-2 K-1
Ყ ᾲ ኈ ㊂㧘 Ყ ࠛ ࡦ ࠻ ࡠ ࡇ ࡯ ࠫࡘ࡯࡞Ფࠠࡠࠣ࡜ࡓᲤࠤ࡞ࡆࡦ J/(kg K)
m2 s-2 K-1
Ყ ࠛ ࡀ ࡞
ࠡ ࡯ ࠫࡘ࡯࡞Ფࠠࡠࠣ࡜ࡓ
J/kg
m2 s-2
ᾲ
વ
ዉ
₸ ࡢ࠶࠻Ფࡔ࡯࠻࡞Ფࠤ࡞ࡆࡦ W/(m K) m kg s-3 K-1
૕ Ⓧ ࠛ ࡀ ࡞ ࠡ ࡯ ࠫࡘ࡯࡞Ფ┙ᣇࡔ࡯࠻࡞ J/m3
m-1 kg s-2
㔚
⇇
ߩ
ᒝ
ߐ ࡏ࡞࠻Ფࡔ࡯࠻࡞
V/m
m kg s-3 A-1
㔚
⩄
ኒ
ᐲ ࠢ࡯ࡠࡦᲤ┙ᣇࡔ࡯࠻࡞ C/m3
m-3 sA
⴫
㕙
㔚
⩄ ࠢ࡯ࡠࡦᲤᐔᣇࡔ࡯࠻࡞ C/m2
m-2 sA
㔚 ᧤ ኒ ᐲ 㧘㔚 ᳇ ᄌ ૏ ࠢ࡯ࡠࡦᲤᐔᣇࡔ࡯࠻࡞ C/m2
m-2 sA
⺃
㔚
₸ ࡈࠔ࡜࠼Ფࡔ࡯࠻࡞
F/m
m-3 kg-1 s4 A2
ㅘ
⏛
₸ ࡋࡦ࡝࡯Ფࡔ࡯࠻࡞
H/m
m kg s-2 A-2
ࡕ ࡞ ࠛ ࡀ ࡞ ࠡ ࡯ ࠫࡘ࡯࡞Ფࡕ࡞
J/mol
m2 kg s-2 mol-1
ࡕ࡞ࠛࡦ࠻ࡠࡇ࡯, ࡕ࡞ᾲኈ㊂ ࠫࡘ࡯࡞Ფࡕ࡞Ფࠤ࡞ࡆࡦ J/(mol K) m2 kg s-2 K-1 mol-1
ᾖ ኿ ✢ ㊂㧔㨄 ✢ ෸ ߮ ǫ ✢ 㧕 ࠢ࡯ࡠࡦᲤࠠࡠࠣ࡜ࡓ
C/kg
kg-1 sA
ๆ
෼
✢
㊂
₸ ࠣ࡟ࠗᲤ⑽
Gy/s
m2 s-3
᡼
኿
ᒝ
ᐲ ࡢ࠶࠻Ფࠬ࠹࡜ࠫࠕࡦ
W/sr
m4 m-2 kg s-3=m2 kg s-3
᡼
኿
ノ
ᐲ ࡢ࠶࠻Ფᐔᣇࡔ࡯࠻࡞Ფࠬ࠹࡜ࠫࠕࡦ W/(m2 sr) m2 m-2 kg s-3=kg s-3
㉂ ⚛ ᵴ ᕈ
Ớ ᐲ ࠞ࠲࡯࡞Ფ┙ᣇࡔ࡯࠻࡞ kat/m3
m-3 s-1 mol
⴫㧡㧚SI ធ㗡⺆
⸥ภ ਸ਼ᢙ‫ ޓ‬ធ㗡⺆
㨅
ࠪ
10-1 ࠺
⴫㧢㧚SIߦዻߐߥ޿߇‫ޔ‬SIߣ૬↪ߐࠇࠆන૏
ฬ⒓
⸥ภ
SI න૏ߦࠃࠆ୯
ಽ
min 1 min=60s
ᤨ
h
1h =60 min=3600 s
㧔a㧕㊂Ớᐲ㧔amount concentration㧕ߪ⥃ᐥൻቇߩಽ㊁ߢߪ‛⾰Ớᐲ
‫ޓޓ‬㧔substance concentration㧕ߣ߽ࠃ߫ࠇࠆ‫ޕ‬
㧔D㧕ߎࠇࠄߪήᰴర㊂޽ࠆ޿ߪᰴర㧝ࠍ߽ߟ㊂ߢ޽ࠆ߇‫ߣߎߩߘޔ‬
‫ߔ⴫ࠍޓޓ‬න૏⸥ภߢ޽ࠆᢙሼߩ㧝ߪㅢᏱߪ⴫⸥ߒߥ޿‫ޕ‬
⴫㧟㧚࿕᦭ߩฬ⒓ߣ⸥ภߢ⴫ߐࠇࠆSI⚵┙න૏
SI ⚵┙න૏
⚵┙㊂
ઁߩSIන૏ߦࠃࠆ
ฬ⒓
⸥ภ
⴫ߒᣇ
㧔㨎㧕
ᐔ
㕙
ⷺ ࡜ࠫࠕࡦ(㨎)
rad
1
㧔㨎㧕
(㨎)
(c)
┙
૕
ⷺ ࠬ࠹࡜ࠫࠕࡦ
sr
1
๟
ᵄ
ᢙ ࡋ࡞࠷㧔㨐㧕
Hz
ജ
࠾ࡘ࡯࠻ࡦ
N
࿶
ജ
ᔕ
ജ ࡄࠬࠞ࡞
,
Pa
N/m2
ࠛ ࡀ ࡞ ࠡ ࡯ , ઀ ੐ , ᾲ ㊂ ࠫࡘ࡯࡞
J
Nm
઀ ੐ ₸ 㧘 Ꮏ ₸ 㧘 ᡼ ኿ ᧤ ࡢ࠶࠻
W
J/s
㔚
⩄
㔚
᳇
㊂ ࠢ࡯ࡠࡦ
,
C
㔚 ૏ Ꮕ 㧔㔚 ࿶ 㧕 , ⿠ 㔚 ജ ࡏ࡞࠻
V
W/A
㕒
㔚
ኈ
㊂ ࡈࠔ࡜࠼
F
C/V
㔚
᳇
ᛶ
᛫ ࠝ࡯ࡓ
ƺ
V/A
ࠦ ࡦ ࠳ ࠢ ࠲ ࡦ ࠬ ࠫ࡯ࡔࡦࠬ
S
A/V
⏛
᧤ ࠙ࠛ࡯ࡃ
Wb
Vs
⏛
᧤
ኒ
ᐲ ࠹ࠬ࡜
T
Wb/m2
ࠗ ࡦ ࠳ ࠢ ࠲ ࡦ ࠬ ࡋࡦ࡝࡯
H
Wb/A
࠮ ࡞ ࠪ ࠙ ࠬ ᷷ ᐲ ࠮࡞ࠪ࠙ࠬᐲ(㨑)
͠
శ
᧤ ࡞࡯ࡔࡦ
lm
cd sr(c)
ᾖ
ᐲ ࡞ࠢࠬ
lx
lm/m2
Bq
᡼ ኿ ᕈ ᩭ ⒳ ߩ ᡼ ኿ ⢻ 㧔㨒㧕 ࡌࠢ࡟࡞㧔㨐㧕
ๆ෼✢㊂, Ყࠛࡀ࡞ࠡ࡯ಽਈ,
ࠣ࡟ࠗ
Gy
J/kg
ࠞ࡯ࡑ
✢㊂ᒰ㊂, ๟ㄝ✢㊂ᒰ㊂, ᣇะ
Sv
J/kg
ࠪ࡯ࡌ࡞࠻㧔㨓㧕
ᕈ✢㊂ᒰ㊂, ୘ੱ✢㊂ᒰ㊂
ធ㗡⺆
࡛
࠲
ࠝࡦࠣࠬ࠻ࡠ࡯ࡓ
ᶏ
㉿
ࡃ
࡯
ࡦ
Έ
㧹
㧝Έ=0.1nm=100pm=10-10m
㧝M=1852m
b
ࡁ
ࡀ
ࡌ
࠻
ࡄ
࡞
kn
Np
㧮
㧝b=100fm2=(10-12cm)2=10-28m2
㧝kn=(1852/3600)m/s
࡞
dB
࠶
࡯
࠺
ࠫ
ࡌ
5+න૏ߣߩᢙ୯⊛ߥ㑐ଥߪ‫ޔ‬
‫ޓޓޓޓ‬ኻᢙ㊂ߩቯ⟵ߦଐሽ‫ޕ‬
⴫㧥㧚࿕᦭ߩฬ⒓ࠍ߽ߟCGS⚵┙න૏
ฬ⒓
⸥ภ
SI න૏ߢ⴫ߐࠇࠆᢙ୯
࡞
ࠣ erg 1 erg=10-7 J
ࠛ
࠳
ࡐ
ࠗ
ࠕ
ࠬ
ࠬ
࠻ ࡯ ࠢ
࠴
࡞
ࡈ
ࠟ
ࠜ
ࡦ dyn 1
࠭ P 1
ࠬ St 1
ࡉ sb 1
࠻ ph 1
࡞ Gal 1
ࡑ ࠢ ࠬ ࠙ 㨴 ࡞
ࠟ
࠙
ࠬ
ࠛ࡞ࠬ࠹࠶࠼㧔㨏㧕
Mx
G
Oe
dyn=10-5N
P=1 dyn s cm-2=0.1Pa s
St =1cm2 s-1=10-4m2 s-1
sb =1cd cm-2=104cd m-2
ph=1cd sr cm-2 104lx
Gal =1cm s-2=10-2ms-2
1 Mx = 1G cm2=10-8Wb
1 G =1Mx cm-2 =10-4T
1 Oe䇭 (103/4Ǒ)A m-1
㧔E㧕㧟ర♽ߩCGSන૏♽ߣSIߢߪ⋥ធᲧセߢ߈ߥ޿ߚ߼‫╬ޔ‬ภ‫ޠ ޓޓޟ‬
‫ߪ ޓޓ‬ኻᔕ㑐ଥࠍ␜ߔ߽ߩߢ޽ࠆ‫ޕ‬
ࠠ
࡟
࡜
ฬ⒓
ࡘ
࡝
ࡦ
࡟
ࠟ
࠻
⴫10㧚SIߦዻߐߥ޿ߘߩઁߩන૏ߩ଀
⸥ภ
SI න૏ߢ⴫ߐࠇࠆᢙ୯
࡯ Ci 1 Ci=3.7×1010Bq
ࠥ
ࡦ
ࡦ R
࠼ rad
ࡓ rem
ࡑ ǫ
ࡈ
ࠚ
࡞
ࡒ
ࡔ࡯࠻࡞♽ࠞ࡜࠶࠻
࠻
ᮡ
Ḱ
ᄢ
᳇
1 R = 2.58×10-4C/kg
1 rad=1cGy=10-2Gy
1 rem=1 cSv=10-2Sv
1ǫ=1 nT=10-9T
1ࡈࠚ࡞ࡒ=1 fm=10-15m
1ࡔ࡯࠻࡞♽ࠞ࡜࠶࠻ = 200 mg = 2×10-4kg
࡞ Torr 1 Torr = (101 325/760) Pa
࿶ atm 1 atm = 101 325 Pa
ࠞ
ࡠ
࡝
࡯
cal
ࡒ
ࠢ
ࡠ
ࡦ
μ
1cal=4.1858J㧔㨬15͠㨭ࠞࡠ࡝࡯㧕㧘4.1868J
㧔㨬IT㨭ࠞࡠ࡝࡯㧕4.184J㧔㨬ᾲൻቇ㨭ࠞࡠ࡝࡯㧕
1 μ =1μm=10-6m
㧔╙ 㧘ᐕᡷ⸓㧕
この印刷物は再生紙を使用しています