ML20055C947
| ML20055C947 | |
| Person / Time | |
|---|---|
| Issue date: | 06/20/1990 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Haughney C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9007020172 | |
| Download: ML20055C947 (14) | |
Text
..
i S 8 0 %is MEMORANDUM FOR:
Charles J. Haughney, Chief fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety FROM:
John P. Roberts, Section leader Irradiated fuel Section Fuel Cycle Safety Pranch 1
SUBJECT:
MEETINGWITHNUCLEARASSURANCECORPORATION(NAC)
DATE/ TIME:
June 19, 1990; 9:30 a.m.
1'
' LOCATION:
Room 48-11, One White Flint North Duilding, Rockville, MD ATTENDEES:
See enclosure 1 PURPOSE:
To discuss NAC development of a burnup meter.
Discussion:
NAC has 6 contract with Power Reactor and Nuclear Fuel Development F
'y (PHC) to develop a burnup meter for spent nuclear fuel.
PNC will tc- $ data and facilities at Tokai Mura for benchmarking NAC's Burnup Meter ano del Assembly Analysis System (see enclosure 2).
NAC discussed its burnup meter development (see enclosure 2).
NAC and NRC staff discussed the need for subsequent radiochemical analysis of spent fuel to be used in tests at Tokai Mura of the burnup meter. Such tests are important to assure proper benchmarking of the NAC system.
/S/
John P. Roberts, Section Leader 1rradiated fuel Section i
Fuel Cycle Safety Branch
Enclosures:
- 1) Attendance List
- 2) Burnup Meter Presentation DISTRIBUTION MU File Center IMNS Central File
/_
IMIF R/F w
[ lypf 'JP, NHSS R/F
'r IMSB R/F Ijg(3
$Edf XM7 U$7" %MI" RM0 d %/
hg
[JR/ M0TOCHAUGHNEY)
$4,
,OF0 :IMIE
~
- I l
l....:.44 lNAME :J ssr n jc :f wn
.---.:.........-:J
.--..--:-...--------:..... g
-g g g ::-----------
DATE 16 90
- 6
/90 0FFICIAL RECORD COPY Suhim b e
i I
I p.
NAC-Burnup Meeting l
I on ' June 19, 1990
)
o I
NAME ORGANIZATION I
I 2
Carl Withee NRC/SGTB Earl Easton NRC/SGTB l
Nancy Osgood NRC/SGTB
-l Ross Chappell NRC/SGTB j
F lMarissa Garcia NRC/SGTB George Gardes NRC/SGTB Chucc Nilsen
-NRC/RES-l i
John Roberts.
NRC/IMNS C. E. MacDonald NRC/SGTB L. E. Fischer LLNL F
Steve Ruffin NRC/IMNS i
Paul Schutt NAC b
Alan H. Wells NAC F
L-1 l
s
+
l t
?
5 f
i m
1 BURNUP METER AND FUEL ASSEMBLY ANALYSIS SYSTEM l
t P
April 1990 t
i l
Nuclear Assurance Corporation 6251 Crooked Creek Road Norcross, Georgia 30092 Telephone: (404) 447 1144 Telex: 6827020, 6827114 l
Facsimile: (404)447 1797 l
-li
l II BURNUP METER COMPONENTS Neutron Detector: Reads Burnup Directly from Curium neutrons Gross Gamma Detector:
Reads Burnup Directly from Fission Gammas Enrichment Independent Burnup Gamma Line Detector: Determines Cool Time from Cs-134/Cs-137 Ratio Axial Burnup Profile System Qualification: Radiochemistry Benchmark PNC Tokai Reprocessing Plant I
5
, i BURNUP METER APPLICATIONS Transport:
Approved by USNRC for Transport NLI-6502 (CofC 9103)
Measure before shipment L
i Useful for High Burnup Fuel and High Capacity Baskets Storage: Required for BWR facilities (No Boron in Pool)
Validation of PWR pool Administrative Control PWR Plants with Single Region Racks Also Unborated PWR pools (West Valley, etc.)
Reactor Pools:
Alternative to Administrative Control or Boron Credit l
Reprocessing Plant: Verify Process Safety
\\,
BURNUP METER PROGRAM Develop Concept (Complete) 1 Develop Contract.with PNC (Complete)
Radiochemistry Procedures (Complete) l Measure U, Pu, Cs, Cm'Isotopics L
Fabrication of Equipment Pre-Operational Testing (Ga Tech, VPCo)
PNC Measurements (Tokai Reprocessing Plant) i USNRC Review / Approval of Topical Report
y, i-s hl i
L BENCHMARKING METHODOLOGY i
I Tokai Reprocessing Plant (TRP):
l l
20 PWR, One at a time L
20 BWR, Two at a time Radiochemistry:
Better than 5 percent Isotopic Accuracy l
l.
L Pu-239, Pu-240, Pu-241, Pu-242 o
i Cm-242, Cm-244 l
Cs-134, Cs-137 o
J
i i
t i
Figure 3.1 Electronic Components COMPUTER (GATE CONTROLi Or$K $TORAGE -
80 uBYTES IBM-AI CR PS/OS
=
=
G m '1 -O A
=
=-
(ofa ano 4g3 t
0 i
0 x-v PLOTTER AOC PRINTER
~
(OPTIONAL)
ANALOG TO
~
l (OPTIONAL)
DIGITAL CONVER'E*.
AMPLRER j HtGH VOLTAGE t
i iCDEAMP I
A-AOOL SURFACE s
w i
i f
i i
IPREAMPl A
1 i
1 O
GAMMA NEUTRON DETECTOR DE2CTOR J
e l
h i'.-
ill 1
Figure 3.2 Burnup Meter Control Cabinet r
$ NY
@f DWY 7
f" NuCLt.AA twitavuovtation woouLE M
KD90AND O
.=>cm.
l s****s, t
,o, 0*
4 4
li
=
.i m t
1 6..,,
C i
j
'I I
E 4
L J
l 5
{
q l
)
i Figure 3.3 Signal Flow Diagram i
h 9
i._ i y................,
~
{G:
w,re.y
.A,t oter.
( AttA woMif0R)
.~
l
,0..,v..t
. t my,,
t...............;
( AntA womsf0R)
DEftCTOR 7*
r...........,
(CAww A DCTICTOR's g,ergro }
le (CA wA OctCtDai IE r.EIEEEEIIE
{l" 44 r
DVAD SCA l,
(NEUTm0N OtttCTOR)
.e
}
J f,
Duat Awatsth g
.=
(NtVfRON CtitC10R)
[
g t'----------*9 (EE) f Duat Awpurte r
g (NCUm0N OtttCTOR)
+ *=
.g.g,.g.gg.g 8 L=,
) 8 n.
'r w
.'. A0 WOMA tupptv E
(NtufMON DCftCf04) p i
3n l
ll$M r..............
3 AwPtWtt t
(CAWwa DCTICTOR)
!Q I
be
,,,,)j r
}
3 *,,,j
. a us w PowtR Suppt,Y I
i (CAwwa DCTICf0R) j j
l K
E t..............
4 au WiC#0 Cow'V't#
1 ms.a r c
I
..,N,t.
tav l
l
i i
s i
Figure 3.4 NAC Burnup Meter
/
1
/
/
i I
g l
j j
'l f *)-
r g
v r/
(u/
J'
/f
'r -) fc4'?";p
.A,T%.M8 Mis, p
K o$
,/
,,{
?
I i
I Figure 3.5 Burnup Meter Arrangement t
t b
t 33! III l }
i m
o
..y y
4M un su um.m i
d8 P
- N seem asaw
'3 I
3 3
ama samma emerai no o m no emm.ns ioner amem IEEW188u amCfut asuines e m CTWE f
i, i(
g2, 1
n v
- l. m n.
fddi,t:
d
-a' %,
M g
/
7 ' '.
T"[
W,%1 lh 9k 24'd.
yf,;,, i ' & [.'1)l * "'
, E i
ed
,.,...y a
i
'/
' l
',4 g
..a.,
l i
1 I
Y j
1!
ti.
F F
i
!F j
u v
- v :
u n
, w,,
l ll l
l l
I i
~.... -
r I$
1 i
4 Figure 3.6 NAC Burnup Meter Cask Load / Fuel Storage Methodology
-d\\
t
. /
n 4
s utu1910s COtCM GAastaa m I
l (f1 SON OtAasetR)
(EmeAs ime()
N
/
N
/
Cashmas patA1H i
g
/
1
,', -~;~,N N
1,ll-r.
1 s
~
,e l
() )ft%M SA3'
,:Q
\\
\\
cf,.......'g u..\\
N
\\_
[
I i
s l'
)
J Y
A _x.
l 1
\\
{
/
\\
\\
. 847 W 8,
,r'
--,e o
\\
n QAume 344 1h0hs4 EPI 64 !Pt1hUlttAL FAST FAST
/jl l
I f
f i
i OfftN l
O(CX
!IllillitilllH.1
)
i m==
L f
I l.
i i
SeN
@1Rgg COJNT Raft COUNT Raft t
l gig,pg _
Sueque 6 8
Cott I Coctl
. c a teio i acAf mt w
N l
,7,j
-o 0%%L $4sGL (i
.mnu
>= va i
('
- osmo net paiecnior (y}
1 i
4 j
n i
c=oss i
Gyllesup f GAssesA w
l l
CDUNT 4
. =ca Onz.nsav
- Colk M {g)
J
/.
Figure 3.7 NAC Burnup Meter Reprocessing / Safeguards Methodology N,
jt
[
'a
'n,b 1
i
=e. wWe
A orme, I
I
( M StaasBER)
(Senaf ammC)
N
/
Cannes saane
,....s
's g:
/
s
,e 1
N, O,je s
mm ur qu N,
s
-c.......]
/
-\\_
i._
i-
\\,
!,/
( c ')
- f /T ~s i
\\f
~
s s,,..,.,,,-
../
h
- g-
- a== u.
i m===.. m m
/-
3 Fa57 FAST n
n l
ETCTM CMet
_Illilllilllllii
<*st g
g:
i e me,.
I __
l j
j-cam,.,.,,
came nas Ag i f
i suae. I I
I co.a I SE"..ba,il-
..a
, ur ens i nw
,w,,
cea i.
e gaptcyapos I
- 3 i
I i
- ABC l
y L dUW'ff rog-8 l
'N
- &artsuamos y
k l
ca.018 f'
C8 amei a
l l
C3,N T e
a s
f*c4 OYC:1 nisitstr r
V
,J
- - - - - - - - - - - - - - - - - - - - - - - - -