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DECLASSIFIED
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This document classified by This document consists of
.,.,_, CONVERSION ,RATIO TABLES
By
ll /l / _
c_ R.A. Chltwoo4 _,=:
Reactor Physics
Research and E_Ineering ...).
C_Ic_CQ_ July 30. 1965
DISTRIBUTION
lflllI .........
_a_e_ O_ [LL_[5. B_,ttelle Northwest Laboratorles
e_l__ta_.: 6-11-_ 1. DP Oranquist
vae_ley (_u q__,_i,, o _-Ib.._i9 General, Electric
2. RR Bloomstrand 1_o J Milne
3. RA Chitwood 15. WS Nechodom
o HG DeVoss 16. R Nilson
5. EF Fairweather 17o GF 0wsley
6. GC Fullmer 18o EG Pierick
7, LL Orunne 19. JW Riches
8_ JW H&ndshuh 20. RJ Shields
9. AK Hardin 21. RD Shlmer
10s NE Ingrs_ 22° 700 Files
11, MC Leverett 230 Record Center
12o M Lewis 24-27o Extra
13o EE Mills
,i e.
t
CONVERSION RATIO TABLES
IIi i
m oDu ios
Thls manual pr_ides a lletln_ of the quantltles of plutonium and plutonium
isotope for_tion, Other isotopes whose concentrations &re important and
included in this report _re U-236 buildup, U-235 burnout, U burnout, Np-237
buildups GVR (the Gas Volume R_tio) in coproduct target elements and
e%utvalent _ of plutonium. These conversion tables hLve been c_ulated
on the IBM 7090 dlSltal c_puter uslnE a pro&t-_ entitled "FLEX-3. ''_j The
results of. the c_puter solutions have not been normalized to conversion
observed by Chemical Processing Deps_t_ent measurement since none are yet
available. Such a correction By be required _fter fuel fr_ N-Reactor is
processed.
Conversion ratios for four types of N-Reactar fuel have been evaluated, they
are:
.9_7 percent U-S3_ normal fuel loading
1,2_ percent U-235 "spike" enrichment
1.2_ percent U-235 outer, Lt-A1 inner - coproduct fuel
1.96 percent U-235 outer, 'Li-A1 inner - coproduct fuel
DISCUSSION
These studies rel_esent the current best estates of plutonium yield. The
results for various fuel loadings are of some importance in the plant
account.ability operation and in the determination of unit cost.
An effort to obtain some measure of the accuracy of the FLEX-3 program was
made by using a K-Reactor loaded with the KV fuel in zirconium tubes. For
reference, the input to that computer ru_ _s included in this report in
Table 1. The results were compared with _2) the accepted conversion ratio
tables for IPDe and the _reement was quite good. The test case is in
Table 2.
OF,co s os
These conversion tables are tabulated by _uel type. The p_eaeters reported
a_e as follows:
,,,, , DEIL SSlFIED
(I) RL-NRD-226_ "FLEX 3 - A Fuel Element Design Analysis Code_" R. J. Shields,
Februs_7 8, 196_.
(2) IIL-REA-_76, "Irradlatlon Processing Fuel and Product Conversion Tables,"
E. Re Perl and A. D° Vaughn, June i_ 1965, SECRET.
A,
RL-NRD-h_7
.......... Page 3
percent Pu-239 The fraction of the plutonium formed that
is the Pu-239 isotope.
percent Pu-2_0 The fraction of the plutonium formed that
is the Pu-2_0 isotope.
percent Pu-2_l The fraction of the plutonium formed that
is the Pu-241 isotope.
grams Pu/ton The grams of total plutonium per ton of
fuel.
_ams Np-_/ton Grams of the isotope Np-237 per ton of
fuel.
_aas U-235/ton Grams of the isotope U-236 per ton of
fuel.
ibs. Bo0. U-235 Pounds of U-235 burned per ton of fUel.
lbs. B.D. U Pounds of U _urned per ton of fuel.
gra_ Pu/NgD Grams of plutoniun formed per megawatt
day of production.
GVR The volume that the gas farmed in a target
element (both tritiwn and helium) would
occupy under standard temperature and pres-
sure divided by the volume of the bare
targe_ element.
E_uivalent grams of P_/MWD This number assumes that every neutron that
was used in the formation of tritium could
have been used to produce plutonium.
A great many of the tubes in N-Reactor contain fuel elements of different
lengths but no effort will be _de to 8e_ent them in this report. One
charge, however, the 1.25 percent U-235 "spike" contains two types of
fuel, and it was necessary to evaluate the spike conversion ratio para-
meters from two separate conversion tables.
CO,.NVERSNIOR_TIO AND RELAT,_/E'PLUTONIUM ISOTOPE GRAPHS
The sraphs were generated from the information in the conversion ratio
tables. They were made to complement the tables, since the exposure steps
are rather large.
R. A. Chitwood
Reactor Physics
Research and Engineering
DEClaSSIFIED
p
1
TAI_E 1
K _R T_T CASE
{550°C''Graphite )
Z 2.000000000 8.h027999o7 1.609999999 550.00o0oo00o-0. 1.000000000
2 1.ooooooooo 1.97o399991 1.0oo00oooo I_oo.ooooooooo-o. -o.
3 11,.000000000 1.806999996 1.000000000 2O0.000.0OO000-0. -0.
_ 3.000oooo00 1.723999992 1.000000o00 Zo0.ooo000000-0. -0.
p 13.ooooooooo z. 527999997 1.289999992 120.0o0000o00 -0. -0.
6 11.00000o000 1.E3o99999h 17.7500oo0o0 60o.00oo000oo-0. -0.
T 13.00000oo00 O.533000000 1.289999992 12Q.00000o000 -0. -0.
8 3,ooooooooo 0._1999999_ 1.ooo0oo000 10o.0o0000000-0. -0.
Z9 -o. oo0000000 -0. 800.00oo00000 8.0_00o0000 Z. O59999967 O.9_9999996
20 38.000000000 0.730399996 1.399999991 38_31_9999905 38.3149999905 0.219999999
2] ]700.000000000 _60.000000000 85.000000OO0 10,000000000 80.0OO00000030000.000000000
22 -0.000000000 5,_69999969 5.l_69999969 8.00ooooo00 o. -0.
26 O.029999991, -0. -o. -0. -0, -0.
27 0.250000000 -0. -0. -0. -0. -0.
30 _.OOO000000 -0. -0. -0. -0. -0.
31 14.000000000 -0. -0. -0. -0. -0.
32 1.000000000 O.1'11l_99996 -0. 99.2881_99832 -0. -0.
36 Ir-'r"llo.Tpooooooo 1.199999988 -o. 0,799999997 -0. o.Sh999999h ,_
rl=-.
13_ P"_I. 000o0ooo0 18.85999989.5 -0. -0. -0. -0. ,J:-
lmlemmmml
--'r'l
I-1"l
__ Ill
°
!
_,_Ls2
(TestCue)
500°C Graphite 550°C Graphite
n_-Rn-576 _sx-3 F_x-3
Pu-239 92.139 92.339 91.986
P_-2_O 7.126 7.120 7. _6o
Pu-2_l .719 .513 .532
Pu _/ton 699.610 713.600 709.600
B.O.U-235 lbs 1,813 1.775 1.769
B.O,U Ibs 3,650 3.662 3.653
PulM_D .875 .892 .887
These points are for an exposure of 800 M_D/Ton.
DEL SSIFIEB
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L ._d
TABLE3
.9_7 PERCEI_ U_,235
(Normal Load)
Rezion Material Diameter (in. ) Tem_eratur_ e°C
1 H20 9.575 65
2 Zircs_oy-2 9.552 95
3 Graphlte 9.5h9 _30
Void , 6.050 h30
5 Gr&phite _. 226. 370
6 Void 3.3h0 370
7 Zircalc_-2 3,2_8 2_2
8 H20 2.708 215
9 Zirealc_-2 2.h06 236
i0 Me_al Fuel 2.351 353
Ii Zircalo_-2 I.815 2_3
12 H20 1,763 218
13 Zircslo¥-2 1.250 237
i_ Metal Fuel 1.16h 379
15 Zircaloy-2 O._93 2_5
16 ,_ H20 0,_38 222
Fuel Element Length: 1,9333 feet
Fuel Element No,: 18
F_fectlve Pile Width: 27.726 feet
F_fective Pile Height: 29.597 feet
Au_entation Distance (front to rear): 1,h5 feet
DECLItSSlFIED
RL-m_D-_7
Page 7
TASLE
I,,2 u-235
(Spike Load)
Re,lea Ma_erSal Diameter (in,) Temperature°C
1 H20 9.575 65
2 Zircslo¥-2 9.552 95
3 Graphite 9.5_9 _30
Void 6.050 _3o
5 Graphite _.226 370
6 Void 3.3_0 370
7 Zircalo¥-2 3.258 232
8 H20 2.708 20P
9 Zircaloy-2 2._06 225
I0 Metal Fuel 2.351 3_5
ii Zircalo_-2 i.815 229
12 H20 1.763 205
13 Zircaloy-2 1.250 220
1_ Metal Fuel 1.16_ 3_
15 Zircalo¥-2 0._93 22
16 H20 0._38 206
Charge Makeup from Rear to Front:
2 (i.933 feet .9_7 parcent U-235) element| + 12 (2.175 feet 1.25 percent
U-235) eleaeats,
+2 (1.9333 feet .9_7 percent U-235) elements + 1 (1.0 feet .9h7 percent
U=235) elmeats.
Effective Pile Width: 27.726 feet
Effective Pile Height: 29.597 feet
Augmentation Distance (front to rear): l.h5 feet
[IECLItSSIFIEI]
e
RL-NRD-A_7
Page 8
T_LE 5
i_25 PERCENT U-235
(Coproduct Load)
Material Diameter Iin.) TemDerature°C
1 H20 9.575 65
2 Zircaloy-2 9.552 95
3 Graphite 9.5_9 _30
Void 6.050 _30
5 Graphite _.226 370
6 Void 3.3_0 370
7 Zircaloy-2 3.258 236
8 H20 2.708 209
9 Zircaloy-2 2.292 239
I0 Me_al Fuel 2.222 hP7
ii Zircaloy-2 1.h91 260
12 H20 I._i 210
13 Zircaloy-2 0.565 210
i_ LI-AI _ 0.h02 210
(
Percent Lithium in Target Alloy: ercent
Percent Lithium that is IA6: 22.0_rcent
l_el Elenent LenKthz 26 inches
Elements per Column: 16
Au_nt&tion Distance: 1.52 feet
Effective Pile Width. 27.726 feet
Effective Pile Height. 29.597 feet
[IECL,SSIFIEg
Pqe 9
1T96 Pm_CE_ U-235
(Coproduct Load)
_ Diameter (in.) Tem_erature°C
1 H20 9.575 65
2 Zircaloy 9.552 95
3 Graphite 9.5_9 _30
Void 6.050 _30
5 Graphite _.226 370
6 Void 3.3_0 370
! 7 ZircaloT-2 3.258 2J;_
8 H20 2.708 218
9 Zircaloy-2 2.3_ 5 2_8
i0 Metal Fuel 2.275 _80
11 Zircaloy-2 1._i_ 263
12 H20 1.36_ 218
13 Zircaloy 0.739 218
i_ Li-AI O.622 218
Percent Lithium in T_rget Alloy. .3.05percent
PLrcent Lio in Lithium" 62.27
Fuel Element Length: 27.8 inches
Elements Per Column: 15
Augmentation Distance: 1.60 feet
Effective Pile Width: 27.726 feet
Effective Pile Height: 29.597 feet
DECLASSIFIED
