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 N (1 e t ( r ) ) e t (s )
ACTIVATION A = A 0 e- t + N act (1 e t ) dps = A 0 e- t + Curies 3.7 x 1010 A = nt, where = [ln (2)]/t1/2 FLUX = nv (neutrons/cm2-sec)
FUCHS PULSE MODEL EQUATIONS (ESTIMATES ONLY) 2( ) 2( )
Tmax = T0 + °C Etot = MWS k ( )
( )2 I Pmax = MW T = initial period 2 (k ) I 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 6 6
=
T Keff
+ 1+ i T 1= 6T 1 i 1
$ = For T > 10 sec with = 0.084 1+ T
SUBCRITICAL MULTIPLICATION FACTOR (M)
C 1 M = =
C0 1 K 1 C
= 0 Plotted vs. fuel added ( rodswithdrawn)
M C NEUTRON SOURCE Am241 6 2He4 + Np237 2 He4 + 4Be9 6 [6C13]* 6 6 C12 + 0n1 PERIOD -
N = N0 et/T N = N0 et P = P0 et/T P = P0 et POWER - P V f P = Watts where V = Volume (cm3 )
3.1x 1010 P = P0 e(k/I)t
NEUTRON GENERATION TIME I = I + ( eff K ) for K eff and = 12.70 sec REACTIVITY K 1 K 1
= = = 1 K K Keff K 1
$ = Where eff = 0.007 Keff REACTOR SCRAM DECAY TIME From Group 6: T = 80 sec =
t1/2 = 55.6 sec NEUTRON DETECTION 5 B10 + 0n1 6 3Li7 + 24 SIX FACTOR FORMULA K4 = pf Keff = pffth HEALTH PHYSICS 6CEn = R/hr at 1 foot
I1D12 = I2D22 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
E Max Integral R Worth Cu D
Worth of Most Reactive Control Element CC Critical Rod Height Worth of Most Reactive Control Element B
A H Rod fully ou C
H