ML19322B941
| ML19322B941 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/30/1969 |
| From: | Ross D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Long C US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7912190920 | |
| Download: ML19322B941 (6) | |
Text
j x
4..,.%c.x
\\
....,/.-
.'s.,. \\
Lo.s.;.....,.~.~.,..=
s T'..N
- ' h.
ATOM:C ENERGY COMMISSION ei i ',it, :.
,4 W ash tNGTCN. C.C.
D545 2
x,'. w'm'. -
Sep:enber 30, 1909 Chr.r'es G. i an;, Chief, dese:cr -r,act sr[nch 3 Division of
. actor '.icenz'n-QUES.. 0.
3u n,... C s...., C v.,.... ;. e.2.s.
.-c:
.s.
_.c
., _ a..v.s.
s.. v v.s.:.. s
.. c _
5 0-2 'r),..;,
c.c 30-257
?:w..:c.. re.
.. re prapc.sa. :a.i:i== :: Duka ?=:e: an..... :
Ocenea.
- p. :a:icn.
Sinca :he 73AR m:erial is poorly c.,ani aa, e..
., d4..:e,cn.
u,.
. o
.n e,... e. <.,..
...e
.a...._....
4neadi.igs are:
dydraulic Analysis 2.
Nu:1 car Factors in ""1ernal Analysis Flou Mixing Clad Surf ace Tenperature 5.
Fuel Tenpera:ure
%u.
. k.. 4b.
u 7..a,.3..,8 eng
.k.e c you.*
w.
4_.......... _ _.. e c..:..,. < c 4,. s s
..c
.v.
.., e
.,,.. 3 derivatica fro = a subsequen: sec: r
~u ISA2 is par:icularly 'efi-cient in : hat respect.
The proposed questions, wi:h c:hcr cc=: ar.:3, ara anclosed.
'~
^~
.r. '..
e :.
- -. f q-o Cenucod F. 2:ss 2cac:cr ?rojec: 2:anch 3 31.<a.c
.m...w,.or 4.e
, ~
r v.
w
..s... ;
A,,, a C,.,...c.,.,w,, a,,.
As 3:at2d above ec:
doc.s. s..e 4. le m/
2 v.
ss/
2P3-3 2eading A. Schwencer
- 3. 7. Ross (3)
T..\\i. Novak K. 3. Cady T91219n % O
+
1.
11YDRAULIC A.YALYS!S Tais section should present pump capc.bility, including spaad, horsapcwar, 9
ef ficiency, flywheel inartic, *?S:: raquirements, and calibrations of l
ficw vs d?.
The calculated systa= flew vs d? should be depicted on a graph of pu=p performance ficw vs a?.
3d has no: done' his, a:: cap: for a pu=p flow-c? curve (71;ure 4-3).
Scale modal tes:s for vessel flev distribu:1ca shoald be fully decumen:ed.
If a :opical rapor: is to be sub=1::ad, than a br12f su==ary of resul:a would be satisfac:ory.
2%' can:1cas :his en pp 3-23, 3-32, and 2-37 of the FS.G.
Calculacions shculd be presen:cd for ficw bypass pa:hs around :ha coro.
Results only are presented in the 7S.G.
e l
I i
1 d
i j
I J
i O
m
s s) g_.C,uc
%...t.
.g e.s es a..G w g.a an t.g.az..cca..o
- 5. =.u... \\. 4 g
c.,
c
- a. o v
.. v FACTORS IN 'EI:OLiL.UALYSIS The nuclear f actors include the radial peaking factor, 7,.[$, which has two par:s: assembly-to-assembly, and a ho:-rod factor.
'"he second s.
nuclear f actor is the axial peaking f actor F ".
3 These f actors are centioned in the FSA2, pages 3-25, 3-26, and Figura 3-8.
Not presented are the calcula ions and.rasul:s for varia: ion in nuclear fac: ors with burnup.
'ie also should ask:
Provide a = ore de: ailed graph or a ca:hematical expressien of :he axial variation of flux and hea ;enera: ion race fcr the clipped ccsino case max / avg ratio of 1.5.
Shcu alac :he nor cli cd intagral of :hi.s flux-variatica as a function of dis:anco along the axial dirac:ica.
?rovide additional infor ation en en3 nearing her spot factors tha: are 1
based on ceasurements from prodnetica fuel clamants.
. ov4.oe a es.4._ ate oe
.t. e,, a...., a ve,.., -. <.
a
. c
...._v..
.a..
---.s and hea: flux for the peak fual rod in :he paai uni: cell.
J I
l I
I i
l 1
i i
\\
i l
e.
3.
-, C.,
- r..... s.s.0
.s.
Since the sixing code TD:? haa,o: yet b-c. made available to DRI. for review, we should ask:
?rovide c detailed descric. cion of.icur ti:.iny> ::cc.. TE.2.
- ..cl da the c.unda-en 1.
osst p.4c.s, a
.....4.,.
-. v.. < ;
c....
.r..
t.. us.- :o,
~.
s,. c....
nor=al and desi,;n calcula:icn.s, anc eat;;; c.43 ul:4.
Discuss the effect of less than four-c.uno. operation en cixin'.
4 sd 9
t
a s
4.
CLAD SURFACE TD!?ERATURE We undarstand that your thermal analysis at design overpower (111%)
assumes a reactor inlet temperature several degrees cooler than for 100% pcwcr.
Show how this occurs by depicting the secondary flow rate, and temperature and level conditions in the steam generators.
Provide the following on your ONOR calcula:icns:
Since there is more chan one correia;icn for :he tera :.: :he non-unifor:
heat flux correction f actor F, justify cne one chat you use.
?rovide a graph of DN3R vs axial distanca at your design condition; a.
indicate the Axial distance for minimum ONSK.
b.
Since the calcula.ted flow race for less than four pump ope.:ica drops balcw 17 10 lb /hr-f t',
justify the continued use a: eas W-3 correlation in the computation of DN3 ratics.
j l
i l
l
\\
s 5.
FUEL TTOEPr CRE Provide the burnup effect on ped linar heat generation rate, cen:er line fuel ta perature, and CO -**1 i"3 ***?"##E"#**
2 4
Confirn or correct the statement en paga 3-:i4 concerning a 9-1/2.'l volumetric increase accompanying a burnup of 33,000 Kvd/M""J.
Provide your calculations relating fuel swelling to burnup, anc thence to diametral grcwth.
J e