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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:

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.

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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)

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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

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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)

Group:

#1=0.30 MeV, #2=0.63 MeV, #3=1.10 MeV,

#4=sum #1 - #3, #5=1.10 MeV (60Co)

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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