ML043520382
| ML043520382 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 12/21/2004 |
| From: | Madden P NRC/NRR/DRIP/RNRP |
| To: | Miller S US Dept of the Navy, National Naval Medical Ctr |
| Doyle P, NRC/NRR/DRIP/RNRP, 415-1058 | |
| References | |
| 50-170/OL-05-01 50-170/OL-05-01 | |
| Download: ML043520382 (34) | |
Text
REFERENCE EQUATIONS ACTIVATION A = A e
+
A e
+
0
- t 0
- t
N e
dps N
e e
Curies act t
t r t s
(
)
(
)
( )
( )
1 1
37 10 10
=
x
A = nt, where = [ln (2)]/t1/2 FLUX
= nv (neutrons/cm2-sec)
FUCHS PULSE MODEL EQUATIONS (ESTIMATES ONLY)
T T
C max
(
)
=
+
° 0
2
E k
MWS tot =
2(
)
( )
P k I MW max
(
)
( )
=
2 2
T I
initial period
=
I = 39 x 10-6 sec
= 1.26 x 10-4 K/K/EC
= 0.007 k /9.6 Assumptions: Point source, adiabatic system, no delayed neutrons IN-HOUR EQUATION
=
+
+
=
1 1
1 6
6 1
6 T K T
T eff i
i For T > 10 sec with = 0.084
$ =
+
1 1
T
SUBCRITICAL MULTIPLICATION FACTOR (M)
M C
C K
=
=
0 1
1 1
0 M
C C Plottedvs fuel added rodswithdrawn
=
(
)
NEUTRON SOURCE Am241 6 2He4 + Np237 2He4 + 4Be9 6 [6C13]* 6 6C12 + 0n1 PERIOD -
N = N0 et/T N = N0 et P = P0 et/T P = P0 et POWER - P P
V Watts where V Volume cm f
=
x
=
31 1010 3
(
)
P = P0 e(k/I)t
NEUTRON GENERATION TIME I
I K
for K and eff eff
=
+
=
(
)
sec 1270 REACTIVITY
=
=
=
K K
K K
Keff 1
1 1
Where eff = 0.007
$ =
K K eff 1
REACTOR SCRAM DECAY TIME From Group 6: T = 80 sec =
t1/2 = 55.6 sec NEUTRON DETECTION 5B10 + 0n1 6 3Li7 + 24 SIX FACTOR FORMULA K4 = pf Keff = pffth HEALTH PHYSICS 6CEn = R/hr at 1 foot
I1D1 2 = I2D2 2
I = I0 e-ln2(t)/t1/2 I = I0 e-µx MAGIC NUMBERS K.E. of nthermal = 0.025 eV 1 watt = 3.1 x 1010 fissions/sec K.E. of nprompt = 2 MeV
= 2.47 neutrons/fission eff = 0.007 1 curie = 3.7 x 1010 dps bar = 12.7 sec (average precursor mean life)
= 80 sec for group 6 Tank constant = 1.48EC/100 KWH
Critical Rod Height Rod fully ou Integral R Worth Cu HC H
C Max A
B Worth of Most Reactive Control Element Worth of Most Reactive Control Element D
C E