overview of fusion neutronics activities at jaeri/fns in 2004
DESCRIPTION
Overview of Fusion Neutronics Activities at JAERI/FNS in 2004. Presented by T. NISHITANI Japan Atomic Energy Research Institute, Tokai-mura, 319-1195, Japan IEA Fusion Neutronics Subtask Workshop Sala del Consiglio, the Giorgio Cini Foundation, Venice 21th September 2004. - PowerPoint PPT PresentationTRANSCRIPT
Overview of Fusion Neutronics Activities at JAERI/FNS in 2004
Presented by T. NISHITANI
Japan Atomic Energy Research Institute, Tokai-mura, 319-1195, Japan
IEA Fusion Neutronics Subtask Workshop Sala del Consiglio, the Giorgio Cini Foundation, Venice
21th September 2004
Verification of Tritium Production through Integral Experiments on the Mock-up
REALITY SIMULATION
Reactor Spectrum
Two main components:
I. High Energy 1n0 from D-T Plasma
II. Low Energy Backward Scattering 1n0
Blanket Module Blanket Mock-up
Source Spectrum
• Point D-T Source;
• Point D-T Source with a Reflector;
Bulk Beryllium Assembly
One Breeder Layer Behind the Fist Wall
Two Breeder LayersSandwiched by Be
Experiment Strategy for Verification of Tritium Breeding
Type Mock-up /
Neutron Spectrum
Motivation
Clean Beryllium /
D-T source
C/E ?
Neutron Transport
Design-Oriented
One Breeder Layer Behind the Fist Wall
D-T source
C/E ?
for TPR-6
One Breeder Layer Behind the First Wall
D-T source & Reflector
Impact of Neutrons from a Reflector
W & One Breeder Layer Behind the First Wall
D-T source & Reflector
Impact of Armor Layer
Two Breeder Layers Sandwiched by Beryllium
D-T source
C/E ?
for TPR-6
Experiment on the Bulk Beryllium Assembly
6
28 m
m
355.6 mm
1.E-27
1.E-26
1.E-25
1.E-24
0 70 140 210 280 350
Distance, mmR
ea
cti
on
ra
te, 1
/nu
cl./
s.n
.
6Li(n, )3H
32S(n,p)32P, x 103
0.8
1.0
1.2
1.4
0 70 140 210 280 350Distance, mm
Ca
lc. /
Ex
p. 6Li(n, )3H
C/E ~ 1.04
0.8
1.0
1.2
1.4
0 70 140 210 280 350Distance, mm
Ca
lc. /
Ex
p. 32S(n,p)32P
C/E ~ 1.03
Source Reflector, SS316
Assembly Encloser, SS316
F82H (16) / Li2TiO3 (12) / Be (200)
Experiments on the One-Breeder Layer Blanket Mock-up -- TPR-6 data --
1.E-28
1.E-27
1.E-26
0 5 10 15Distance, mm
TP
R-6
, 1/6 L
i nu
cl./
s.n
.
D-T Source
D-T Source&
Reflector
0.8
1.0
1.2
1.4
0 4 8 12Distance, mm
Ca
lc. /
Ex
p. D-T Source & Reflector
C/E ~ 1.14
0.8
1.0
1.2
1.4
0 4 8 12Distance, mm
Ca
lc. /
Ex
p. D-T Source
C/E ~ 1.02
Source Reflector, SS316
Assembly Encloser, SS316
W (12.6) / F82H (16) / Li2TiO3 (12) / Be (200)
Experiments on the One-Breeder Layer Blanket Mock-up with W Armor
1.E-28
1.E-27
1.E-26
0 5 10 15Distance, mm
TP
R-6
, 1/6
Li n
ucl
./s.n
. Mock-upwithout
W armor
Mock-upwith
W (12.6 mm)
0.8
1.0
1.2
1.4
0 4 8 12Distance, mm
Cal
c. /
Exp
.
C/E ~ 1.18
0.8
1.0
1.2
0 4 8 12Distance, mm
RR
rat
io
W (12.6mm) Effect on TPR-6RR Ratio ~ 0.98
Li2TiO3 (12) / Be (100)
Experiment on the Mock-up with Two-Breeder Layers Sandwiched by Beryllium
TP
R-6
, 1/6 L
i nu
cl./s
.n.
3.E-27
5.E-27
7.E-27
9.E-27
1.E-26
1.E-26
0 4 8 12
Distance, mm
First Layer
1.E-27
3.E-27
5.E-27
7.E-27
9.E-27
1.E-26
0 4 8 12
Distance, mm
Second Layer
0.8
1.0
1.2
1.4
0 4 8 12Distance, mm
Ca
lc. /
Ex
p. First Layer
C/E ~ 1.02
0.8
1.0
1.2
1.4
0 4 8 12Distance, mm
Ca
lc. /
Ex
p. Second Layer
C/E ~ 1.05
The JAERRI/FNS activity for tritium benchmark measurement
We obtained the complete result of tritium benchmark by means of HTO sample.
690.0± 3%
69.0± 3%
13.8± 3%
330.0 ± 3%
1.505± 0.76%
18.44± 0.75%
91.4± 0.73%
1.505± 0.76%
18.52± 0.75%
91.3± 0.73
347.3± 3%
36.97± 3%
3.84± 3%
13.26± 3%
Theoretical value
Bq/g
1.01
1.01
1.01
-----
1.06
1.04
0.97
-----
-----
-----
1.00
1.00
1.00
1.00
Ratio
0.98
0.99
1.00
0.99
-----
-----
-----
1.00
1.01
1.01
1.01
1.01
1.03
1.02
Ratio
1.02
1.02
1.04
0.95
1.00
1.00
1.00
1.00
1.00
1.00
0.98
0.97
0.98
0.97
Ratio
678.0 (2.4%)
68.4 (4.3%)
13.9 (5.7%)
328.0 (3.0%)
---------
---------
---------
1.5 (3.8%)
18.7 (3.5%)
92.0 (3.4%)
352.0 (2.4%)
37.2 (4.6%)
4.0 (5.7%)
13.5 (5.2%)
TUD measurement Bq/g
(Total uncertainty %)
702.0 (1.0%)
70.4 (1.2%)
14.3 (1.4%)
315.0 (1.0%)
1.5 (9.2%)
18.6 (1.4%)
91.4 (1.2%)
1.5 (9.2%)
18.6 (1.4%)
91.4 (1.2%)
342.0 (1.5%)
35.7 (1.3%)
3.8 (4.4%)
12.8 (2.1%)
ENEA measurement Bq/g
(Total uncertainty %)
694.0 (3.3%)
70.0 (3.4%)
13.9 (3.5%)
----------
1.6 (4..3%)
19.2 (2.7%)
94.0 (2.3%)
---------
---------
---------
347.8 (3.4%)
36.84 (3.4%)
3.84 (3.4%)
13.26 (3.4%)
JAERI measurement Bq/g
(Total uncertainty %)
VKTA-A
VKTA-B
VKTA-C
VKTA-D (Blind)
TUD
ENEA02
ENEA12 (Blind)
ENEA22
ENEA04
ENEA14
ENEA24 (Blind)
ENEA
HTO-01
HTO-02
HTO-03
HTO-04 (Blind)
JAERI
HTO waterPrepared
690.0± 3%
69.0± 3%
13.8± 3%
330.0 ± 3%
1.505± 0.76%
18.44± 0.75%
91.4± 0.73%
1.505± 0.76%
18.52± 0.75%
91.3± 0.73
347.3± 3%
36.97± 3%
3.84± 3%
13.26± 3%
Theoretical value
Bq/g
1.01
1.01
1.01
-----
1.06
1.04
0.97
-----
-----
-----
1.00
1.00
1.00
1.00
Ratio
0.98
0.99
1.00
0.99
-----
-----
-----
1.00
1.01
1.01
1.01
1.01
1.03
1.02
Ratio
1.02
1.02
1.04
0.95
1.00
1.00
1.00
1.00
1.00
1.00
0.98
0.97
0.98
0.97
Ratio
678.0 (2.4%)
68.4 (4.3%)
13.9 (5.7%)
328.0 (3.0%)
---------
---------
---------
1.5 (3.8%)
18.7 (3.5%)
92.0 (3.4%)
352.0 (2.4%)
37.2 (4.6%)
4.0 (5.7%)
13.5 (5.2%)
TUD measurement Bq/g
(Total uncertainty %)
702.0 (1.0%)
70.4 (1.2%)
14.3 (1.4%)
315.0 (1.0%)
1.5 (9.2%)
18.6 (1.4%)
91.4 (1.2%)
1.5 (9.2%)
18.6 (1.4%)
91.4 (1.2%)
342.0 (1.5%)
35.7 (1.3%)
3.8 (4.4%)
12.8 (2.1%)
ENEA measurement Bq/g
(Total uncertainty %)
694.0 (3.3%)
70.0 (3.4%)
13.9 (3.5%)
----------
1.6 (4..3%)
19.2 (2.7%)
94.0 (2.3%)
---------
---------
---------
347.8 (3.4%)
36.84 (3.4%)
3.84 (3.4%)
13.26 (3.4%)
JAERI measurement Bq/g
(Total uncertainty %)
VKTA-A
VKTA-B
VKTA-C
VKTA-D (Blind)
TUD
ENEA02
ENEA12 (Blind)
ENEA22
ENEA04
ENEA14
ENEA24 (Blind)
ENEA
HTO-01
HTO-02
HTO-03
HTO-04 (Blind)
JAERI
HTO waterPrepared
Results of tritium -ray counting (Bq/g) in used HTO samples
The JAERRI/FNS activity for tritium benchmark measurement
As the next step, JAERI/FNS carried out the D-T neutrons irradiation by means of the 6Li and 7Li enriched pellets.
Li2CO3 pellet( 13mm x 2mm, Li-6 : 99.7 atom%)
DT neutron1.5 x 10 11 n/sec
TiT target
FNS 80deg. Beam line
Beryllium assembly60 x 35 cm3
200 mm 102 mm
Li2CO3 pellet( 13mm x 2mm, Li-6 : 99.7 atom%)
DT neutron1.5 x 10 11 n/sec
TiT target
FNS 80deg. Beam line
Beryllium assembly60 x 35 cm3
200 mm 102 mm
5 r.p.m.
DT neutron1.5 x 10 11 n/sec
TiT targetLi2CO3 pellet
( 13mm x 2mm, Li-7:99.9 atom%)
Aluminum disk
Motor
Si detector for neutron counting
FNS 80deg. Beam line350 keV, 1mA Deuteron
Water line for cooling
5 r.p.m.
DT neutron1.5 x 10 11 n/sec
TiT targetLi2CO3 pellet
( 13mm x 2mm, Li-7:99.9 atom%)
Aluminum disk
Motor
Si detector for neutron counting
FNS 80deg. Beam line350 keV, 1mA Deuteron
Water line for cooling
We obtained preliminary results of the tritium activities (Bq/cc) in the irradiated pellets. We will discuss the results in depth within this conference term.
Schematic drawing of Li-7 enrichedLi2CO3 irradiation experiments with JAERI/FNS
Schematic drawing of Li-6 enrichedLi2CO3 irradiation experiments with JAERI/FNS
FNS Rotatingtritium target(TiT target 37TBq)
D+ beam350 keV, ~20mA
Pre-collimator
Shield wall
2nd Target room
Accelarator Room
F.C.Th-232
Shield wall
Collimator assembly
1st Target room at JAERI/FNS
F.C.U-238
Experimental chamber
Step-backshielding door
Experimental movable deck
1.8 m 2.0 m
Neutron beam
Experimental chamber
Schematic view of JAERI/FNS D-T neutron beam assembly and the experimental chamber.
Differential cross section measurement of (n,CP) reactioncollaborating with Osaka University
Differential cross section measurement of (n,CP) reaction
We obtained the DDXs and ADXs of 9Be(n,x) and 9Be(n,t) reactions
The measured ADX of the 9Be(n,t) and and the evaluated value (ENDF-B/VI).
0
1
2
3
4
0 0.2 0.4 0.6 0.8 1
9Be(n,t)
[cosine unit]
Evaluated value
lab= 70 deg
45 deg
30 deg
15 deg
The measured ADX of the 9Be(n,x) and the evaluated nuclear data (JENDL-3.3 and ENDF-B/VI).
JENDL3.3
ENDF/B-VI
1
10
100
1000
-1 -0.5 0 0.5 1
Experiment
ADX
[mb/
sr]
Scattering angle [cos unit]
In 2004, 51V(d,x) 49Cr, natFe(d,x) 55,56Co , natNi(d,x) 55Co , 60,61Cu , and 181Ta(d,x)178,180Ta cross sections have been measured.
natFe(d,x)56Co natNi(d,x)61Cu
1.0E+01
1.0E+02
1.0E+03
0 10 20 30 40 50Deuteron Energy [MeV]
Cro
ss S
ect
ion
[m
b] Present
Takacs('01)
1.0E+00
1.0E+01
1.0E+02
0 10 20 30 40 50Deuteron Energy [MeV]
Cro
ss S
ect
ion
[m
b] Present
Takacs('01)
Measurements of (d,x) reaction cross sections for IFMIF
Heat Load Analysis of NBI Duct
Evaluation of nuclear heating and surface heat load due to bremsstrahlung by MCNP as ITER ITA task
D-NBI duct
NBI duct
Duct wall with facing surface
Blanket
NBI duct
Blanket
Vacuum vessel
TF coil
PF coil
Cryostat
Biological shield
NBI duct
Vacuum vessel
Duct wall with hidden surface
Heat Load Analysis of NBI Duct
1
10
0 50 100 150 200
Facing SurfaceHidden Surface
Distance from the FW surface (cm)
1
10
0 50 100 150 200
Hidden SurfaceFacing Surface
Distance from the FW surface (cm)
Hydrogen Isotope Analysis of the TFTR Tile
Nuclear Reaction Analysis with below 350-keV deuteronDepth profiles of Tritium, Deuterium and Lithium
Rutherford Backscattering Spectroscopy with 350-keV deuteron Carbon density of the matrix and some high Z impurities (W etc.)
Imaging Plate methodsTritium intensity and spatial distributions in the matrix
Activation Analysis with FNS D-T neutron sourceMedium Z metals (Fe, Ni, Co etc.)
Gas flow methodThe number of tritium and carbon-14
Our main objectives is to measure the tritium retention on the TFTR-PFM
In 1993, the TFTR had the series of the D-T discharge experiments.The absolute measurement of tritium depth profile in the order of m on the surface of the plasma facing material (4D-CFC) has been left.
Tritium Depth Profile on the Surface of the TFTR tile
T-Retention7.2 x 1015 T/cm2 (up to 1.2m)
NE213
JAERI/FNS80deg. LineD+， 1A150~380 keV
SSD
We mainly observed charged particles induced with T-d, D-d, 6Li-d and 7Li-d reactions by means of nuclear reaction analysis.
Schematic view of the FNS-NRA system
1.0E+00
1.0E+01
1.0E+02
1.0E+03
1.0E+04
1.0E+05
0 3 6 9 12
Energy MeV
Cou
nts
/Ch
ann
el/m
C
6Li(d,2)
D(d,p)TT(d,n)
7Li(d,2n)
3.0E+19
6.0E+19
9.0E+19
1.2E+20
-0.2 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4
Depth (m)
Tri
tium
den
sity
(c
m-3
)
Tritium profile on the surface, Activity=12.9 MBq/cm2. Density peak 1 x 1020cm-3 at near 0.5 m depth.
Tritium Depth Profile on the Surface of the TFTR tile
3.0E+19
6.0E+19
9.0E+19
1.2E+20
-0.2 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4
Depth (m)
Tri
tium
den
sity
(c
m-3
)
T-Retention7.2 x 1015 T/cm2 (up to 1.2m)
Tritium profile on the surface, Activity=12.9 MBq/cm2. Density peak 1 x 1020cm-3 at near 0.5 m depth.
We mainly observed charged particles induced with T-d, D-d, 6Li-d and 7Li-d reactions by means of nuclear reaction analysis.
NE213
JAERI/FNS80deg. LineD+， 1A150~380 keV
SSD
Schematic view of the FNS-NRA system
A piece at the corner of block in KC-16 was sampled
Plan in 2004-2005
Integral Study on Structural/Blanket Materials Benchmark experiment for the blanket assembly with pebbles Benchmark experiment for the blanket assembly with the coolant panel.
Low Activation Materials Induced Radioactivity Experiments Charged particle production cross section measurement for 6Li and 7Li. Activation cross section measurement of (d,X) reactions for IFMIF ma
terials,Ta, Fe, Ni and V, in the energy range of 20-35 MeV. Others
ITER-ITA task : Nuclear heat analyses for NB and DNB ports. Neutron Elastic Scattering Analysis of D and T in TFTR and JT-60 car
bon tiles.