fusion neutronics activity at jaeri from october 2000 to september 2001 peseted by takeo nishtani...
DESCRIPTION
Breeding Blanket Experiments OBJECTIVES One of our aim is to verify the nuclear performances of resent designed thermal blankets. IN THE PRESENT 2-dim F82H/ 6 Li-enriched Li 2 TiO3/Beryllium mock-up - Tritium production performance for 6Li-enriched (40~95%) breeder - Verification of activation of a ferric steel (F82H) for fusion neutron fields FUTURE WORKS 3-dim F82H/Water/Breeder/Beryllium mock-up Pebbly mock-upTRANSCRIPT
Fusion Neutronics Activity at JAERI from October 2000 to September 2001
Peseted by Takeo NISHTANI
IEA International Work Shop on Fusion Neutronics
The Kongreshous Baden-Baden, Germany
18th October, 2001 (During 10th ICFRM Conference)
Fusion Neutronic Activity Items at FNS/JAERI
Breeding Blanket Experiments Shielding benchmark experiments
Shutdown dose measurements Double bent duct streaming experiment Decay heat measurements
Activation Experiments for Sequential Charged Particle Reactions
Development of Neutron Measurement Technique Development of Artificial Diamond Detector Development of Micro Fission Chamber for ITER
Breeding Blanket Experiments
OBJECTIVES
One of our aim is to verify the nuclear performances of resent
designed thermal blankets.
IN THE PRESENT
2-dim F82H/6Li-enriched Li2TiO3/Beryllium mock-up
- Tritium production performance for 6Li-enriched (40~95%) breeder
- Verification of activation of a ferric steel (F82H) for fusion neutron fields
FUTURE WORKS
3-dim F82H/Water/Breeder/Beryllium mock-up
Pebbly mock-up
A schematic view of FNS blanket experiments
FNS 80deg. D-T target
A blanket assembly
Detectors (NE213)
Shielding (Li2CO3)
Present Blanket Assembly
Measurements
MeV-neutron 14-mm NE213
Reaction rates Fission Chamber(U-235 and U-238)
HPGe (Nb, Al, In, Au and F82H sheet)
Liquid Scintillation Counter (Aloka-5500)
Calculation
Code MCNP-4B
Nuclear data JENDLE-3.3 and JENDLE-FF
Measurement and Analysis Methods
Results of Measurements
Above spectra show the -ray spectrum emitted from the irradiated F82H(Fe: balance, Cr: 8% and W: 2%) and -ray spectrum emitted from the irradiated Li2TiO3 pellet. the reaction rates of the activities and tritium production can be obtained by the spectra.
The -ray spectrum emitted from the F82H The -ray spectrum emitted from the Li2TiO3
Preliminary Result
We have obtained the profile of reaction rates of the iron, chromium and tungsten in F82H and tritium production in 95-% Li2TiO3.
C/E of the 95-% Li2TiO3 tritium production is closed to 1 with the error of plus and minas 10%.
However, since experimental result of activities of Au foil in Be is significantly underestimated, The investigation of the cause is in progress.
The profiles of reaction rates at the assembly
Shielding benchmark experiments for ITER (R&D Task T-426)
Shutdown dose measurements to evaluate accuracy of the new one step method
Double bent duct streaming experiment
Decay heat measurements for copper and type 316 stainless steel (presented at ICFRM-10)
Shutdown dose measurements
Cross sectional view of the assembly Comparison of shutdown dose rates
Shutdown dose rates can be evaluated by the new one step method within experimental error (~10%)
D-T source Test region
Shield(SS316/H20)
Source Reflector(SS316)
1200
φ300
20080
0φ
356#A#B #C
#a #b #c
Reflector(SS316)
0.0
1.0
2.0
3.0
4.0
5.0
6.0
7.0
8.0
9.0
1.0E+05 3.0E+05 5.0E+05 7.0E+05 9.0E+05 1.1E+06 1.3E+06 1.5E+060.5
1.0
1.5
2.0
2.5
3.0
3.5
1.0
Cooling time (x 105sec)
Shut
dow
n do
se ra
te(
Sv
/hr)
9.0
8.0
7.0
6.0
5.0
4.0
3.0
2.0
1.0
0.0
3.5
3.0
2.5
2.0
1.5
1.0
0.53.0 7.0 9.0 11.0 13.0 15.05.0
FENDL/2AFENDL/2
#A
#a
Double bent duct streaming experiment
Typical streaming effects can be reproduced by MCNP & FENDL/2 (~30%)
Cross sectional view of the assembly Comparison of neutron spectrum
Iron Rack
Auxiliary Shield
Streaming Assembly
Auxiliary Shield
1800200
800
1000 900 Duct Opening
(300 x 300)
DT Source
1700
1200
550750
765
335
565150
#1 #2 #3
#4 #5
#6
1.0E-12
1.0E-11
1.0E-10
1.0E-09
1.0E-08
1.0E-07
1.0E-06
1.0E-05
1.0E-04
1.0E+00 1.0E+01 1.0E+02
Energy (MeV)
Neu
tron
flux
(n/c
m2 /s
ourc
e/le
thar
gy)
Calculation
Experiment #3
#4
#5
#6
Activation Experiments for Sequential Charged Particle Reactions (SCPR)
For the safety design of future D-T reactors it becomes important to consider activations via SCPR.
Many protons are generated in coolant water, so sequential reactions will be enhanced around the surface of coolant pipes.
→ Fusion material foils (Cu, V, Ti, Fe, W, Pb) attached on a polyethylene board were irradiated by 14-MeV neutrons at FNS/JAERI and the sequential reaction rates were obtained for 5 positions.
n p A(p,n)C
A(n,x)Brecoi led
Coolant
Coolant(H2O)
14-MeVneutrons
Pipes Polyethylene(3mmt)
14-MeVneutrons
Niobium Foi l
Fusion Material Foi l s (100Å 2̀50É mt)
Experiment
1 2 3 4 5
Preliminary Results The sequential reaction rate of 51V(p,n)51Cr for the foil-1 close
to a polyethylene board is about 20 times larger than that for the foil-5 far from foil-1.
Measured gamma-ray spectrum from V sample
Reaction-rate distribution of 51V(p,n)51Cr
Development of Artificial Diamond Detector Recently, we tried to use a chemical vapor deposition (CVD) dia
mond with single crystal.
The detector has an energy resolution of 0.4 % for 5.486 MeV particles, which gives us a good prospect to the 14 MeV neutron spectrometer using a single crystalline CVD diamond.
1.0 mm(a) 1.0 mm(b)
0
100
200
300
400
500
750 775 800 825 850Channel number
5.486 MeV particles
0.4 %
CVD diamond
Single crystallinePolycrystalline
Development of Micro-fission Chamber for ITER
■ Micro-fission chamber was developed to be installed in ITER vacuum vessel for power monitor.
■ Basic performances for radiation measurement under in-vessel condition were tested and confirmed to be excellent.
Fabricated micro-fission chamber
Main result of performance test
■ Linearity between neutron source and detector response was confirmed.■ Response sensitivity for the neutron shielding turned out excellent.■ Gamma-ray background was estimated less than 0.1% the neutron flux.
0 1 2 3 4 5Co
unts
/sec
/Sou
rce
or
n/c
m2 /
sec/
Sour
ce
Total Neutron Flux Calc.
>10MeV Neutron Flux Calc.
Reaction Rates Calc.
Count Rates Meas.
10-9
10-7
10-5
10-3
Chamber Location
Comparison between Count Rates & Neutron Flux
Arrangement of Shielding Experiment
21 43
Future Plan in Fusion Neutronic at FNS/JAERI
Extend of Breeding Blanket Experiments Breeder and Beryllium pebbles
Activation Experiments for Sequential Charged Particle Reactions
Development of Neutron Measurement Technique Development of Neutron Detector using Optical
Fiber Development of Artificial Diamond Detector