Argonne National Laboratory
Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)

PHDOSE Program

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Dr. Raymond B. Pond
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


PHDOSE Program

R. B. Pond
RERTR Program
Argonne National Laboratory

PHDOSE Program Package:
  1.  Introduction
  2.  Example Input
  3. Example Output
  4. Input/Output Description
  5. 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:













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
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
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
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
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
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)
  • if ti = 0.0, ti is calculated from the powden and burnup parameters as: ti = burnup/powden*8, assuming 1.25 g 235U burned per MWd.
  • if ti = or > 0.0, normal output is printed.
  • if ti < 0.0, ti = - ti and optional output is also printed.
  • note: if ti is not = to 0.0, ti must be within 1% of the calculated irradiation time. (= or > 1%, stop code 101)
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:

  • Echo input (ti, power, powden, td, kg, ppm, burnup)
  • Average neutron flux (n/cm2-s)

Record #2:

  • 235U burned (g) [= power/powden*burnup*10]
  • Fission product photon source rate (ph/s) per g235U burned
  • 60Co photon source rate (ph/s)
  • Self-protecting 235U mass (g 235U burned)
  • Fission product photon dose rate (rem/h) per g 235U burned
  • 60Co photon dose rate (rem/h)

Fission products (FP):

90Sr, 90Y, 134Cs, 137Cs, 137mBa, 144Ce, 144Pr, 106Rh, 95Zr, 95Nb

Optional Output
  • Material formation rates (atoms/s)
  • Material loss rates (atoms/s)
  • Material n0 present at time ti (atoms)
  • Material n present at time td (atoms)
  • Material disintegration rates (curies)
  • Material/group photon source rates (ph/s)
  • Material/group photon dose rates (rem/h)
  • Group photon heat (watts)
  • Group photon flux (ph/cm2-s)
  • Group photon source rate (ph/s)
  • Group photon dose rate (rem/h)

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)


#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.

PC Version

UNIX Version

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Last modified on July 29, 2008 11:34 +0200