IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)
PHDOSE Program
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Contact:
Dr. Raymond B. Pond
Physicist
Technology Development - 362
Argonne
National Laboratory
9700 South Cass Avenue
Argonne, IL 60439 USA
Phone: (630) 252-7090
Fax: (630) 252-5161
IAEA/USA Interregional Training Course
Technical and Administrative Preparations Required for Shipment of Research Reactor Spent
Fuel to its Country of Origin
13-24 January 1997
Argonne, IL
L.3.3a
PHDOSE Program
R. B. Pond
RERTR Program
Argonne National Laboratory
PHDOSE Program Package:
- Introduction
- Example Input
- Example Output
- Input/Output Description
- PHDOSE Program (Fortran)
1. Introduction
The PHDOSE code calculates the photon dose rate of a line-source model (see
attached figure) of spent fuel as a function of:
1. Fuel assembly power density, MW/kg 235U
a. fuel assembly power, MW
b. fuel assembly mass, kg 235U
2. U-235 Burnup, %
3. Fission product decay time, year
A dose rate estimate for an MTR-, TRIGA- or DIDO-type fuel assembly can be made
based upon the line-source model dose rate. An MTR-type fuel assembly dose rate
is a factor of about 0.92 times the line-source model dose rate; a TRIGA-type
fuel assembly is a factor of about 1.04 times an MTR-type fuel assembly dose
rate; and a DIDO-type fuel assembly is a factor of about 1.05 times an MTR-type
fuel assembly dose rate.
Calculates the photon source (ph/s), photon dose (rem/h), radioactivity (Curies) and gamma decay heat (Watts) of 12 fission products. The fission products are:
Sr-90 |
Y-90 |
Cs-133 |
Cs-134 |
Cs-137 |
Ba-137m |
Ce-144 |
Pr-144 |
Ru-106 |
Rh-106 |
Zr-95 |
Nb-95 |
Similar data are also calculated for Co-60, since it is a possible photon source
in spent fuel arising from the activation of Co-59.
2. PHDOSE Example Input
-3584.0 0.025 0.0892857 3.0 4.0 10.0 40.0 (Please check input description for proper format)
3. PHDOSE Example Output:
0input: irrad time (d), power (MW), pow den (MW/kgU-235), decay time (y), asby mass (kg), Co-59 (ppm), U-235 burnup (%), avg flux (n/cm**2-s) -3.58400D+03 2.50000D-02 8.92857D-02 3.00000D+00 4.00000D+00 1.00000D+01 4.00000D-01 3.29464D+12 output: U-235 burned (g), FP source (ph/s per g), Co-60 source (ph/s), self-pro U-235 mass (g), FP dose (rem/h per g), Co-60 dose (rem/h) 1.12000D+02 1.34115D+11 6.39796D+10 8.94664D+01 1.11774D+00 8.73080D-01 material formation rates, atoms/s 4.52545D+13 0.00000D+00 5.21987D+13 0.00000D+00 4.82975D+13 0.00000D+00 4.29138D+13 0.00000D+00 3.12880D+12 0.00000D+00 5.07162D+13 0.00000D+00 5.34375D+10 material loss rates, atoms/s 7.84987D-10 3.00501D-06 3.40007D-10 1.10129D-08 7.30132D-10 4.53000D-03 2.82139D-08 6.68400D-04 2.17415D-08 2.31800D-02 1.22500D-07 2.28512D-07 4.19008D-09 material n0, atoms (time=ti) 1.24395D+22 3.23551D+18 1.53419D+22 4.02355D+20 1.33854D+22 2.15615D+15 1.52072D+21 6.41825D+16 1.43736D+20 1.34806D+14 4.14010D+20 2.21942D+20 9.97537D+18 material n, atoms (time=td) 1.15529D+22 3.00490D+18 1.53419D+22 1.46762D+20 1.24925D+22 2.01232D+15 1.05430D+20 4.44971D+15 1.83788D+19 1.72371D+13 3.83499D+15 4.43184D+15 6.71965D+18 material disintegration rates, curies 2.44047D+02 2.44047D+02 0.00000D+00 4.22834D+01 2.46373D+02 2.46373D+02 8.03834D+01 8.03834D+01 1.07988D+01 1.07988D+01 1.26969D-02 2.73696D-02 7.58412D-01 material/group photon source rates, ph/s 4.23494D+10 3.96405D+07 4.46069D+11 1.46282D+11 2.23937D+10 3.75476D+12 4.84990D+10 9.20697D+10 3.86510D+08 9.57160D+12 2.97419D+11 2.23956D+11 1.28485D+11 2.57862D+10 6.11319D+10 1.37047D+11 2.07769D+10 5.40254D+08 1.23546D+09 6.39796D+10 material/group photon dose rates, rem/h 1.82942D-01 3.42041D-04 1.92694D+00 1.26220D+00 3.05590D-01 3.23983D+01 6.61829D-01 3.97725D-01 3.33503D-03 8.25893D+01 1.28480D+00 9.67452D-01 1.10864D+00 3.51884D-01 2.64079D-01 1.18252D+00 2.83526D-01 4.66162D-03 1.06603D-02 8.73080D-01 group photon heat, wt 5.59001D-02 1.38693D+00 2.07005D-02 1.46353D+00 1.12758D-02 group photon flux, ph/cm**2-s 8.94575D+06 1.05691D+08 9.03470D+05 1.15540D+08 4.92131D+05 group photon source rate, ph/s 1.16299D+12 1.37404D+13 1.17456D+11 1.50208D+13 6.39796D+10 group photon dose rate, rem/h 5.02394D+00 1.18560D+02 1.60283D+00 1.25187D+02 8.73080D-01
4. Input/Output Description
Purpose: To calculate the photon dose rate from spent fuel.
Input (format 7D10.5)
ti | Irradiation time (d) |
|
|
power | Assembly power (MW) |
powden | Assembly power density (MW/kg235U) |
td | Fission product decay time (y) |
kg | Structural material mass (kg) |
ppm | 59Co in structural material (ppm) |
burnup | 235U burnup in fuel (%) |
Normal Output
Record #1:
|
Record #2:
|
Fission products (FP):
90Sr, 90Y, 134Cs, 137Cs, 137mBa, 144Ce, 144Pr, 106Rh, 95Zr, 95Nb
Optional Output
|
Material (Group #) order:
90Sr(1,2), 90Y(1,2,3), 133Cs, 134Cs(2,3), 137Cs(1,2), 137mBa(2), 144Ce(1),
144Pr(1,2,3), 106Ru, 106Rh(1,2,3), 95Zr(2), 95Nb(2), 60Co(5)
Group:
#1=0.30 MeV, #2=0.63 MeV, #3=1.10 MeV,
#4=sum #1 - #3, #5=1.10 MeV (60Co)
5. PHDOSE Program (Fortran)
Fortran 77 source code is provided in the following text files for use on PCs and Unix workstations. The code can be downloaded, compiled, and executed.