Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page2 of 35

CONTENTS 

Page 

1. PURPOSE................................................................................................................................ 
4

2. METHOD ................................................................................................................................ 
4

3. ASSUMPTIONS ...................................................................................................................... 
4

4. USE OF COMPUTER SOFTWARE AND MODELS ............................................................ 
6

4.1 SOFTWARE APPROVED FOR QUALITY ASSURANCE (QA) WORK.................. 
6

4.2 SOFTWARE ROUTINES..............................................................................................
6

4.2.1 BIN.EXE............................................................................................................... 
6

4.2.2 SURFACESORT.EXE ....................................................................................... 14

4.3 MODELS......................................................................................................................16

5. CALCULATION.................................................................................................................... 16

5.1 CALCULATION INPUTS...........................................................................................16

5.1.1 Assembly Constraints ......................................................................................... 16

5.1.2 Commercial Waste Streams................................................................................ 18

5.1.3 Source Terms......................................................................................................19

5.2 PROCEDURE............................................................................................................... 23

6. RESULTS..............................................................................................................................23

7. ATTACHMENTS .................................................................................................................. 30

8. REFERENCES ....................................................................................................................... 35


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Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
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TABLES 

Page 

1. Output File Heading Descriptions......................................................................................... 12

2. SURFACESORT.EXE Waste Package Translation ............................................................. 15

3. Waste Package CriticalityCoefficients.................................................................................17

4. Commercial Waste Package Designs....................................................................................17

5. Arrival Case Characteristics.................................................................................................. 19

6. Representative Assembly Characteristics ............................................................................. 19

7. Zircaloy-Clad Assembly Burnup/Enrichment Combinations ............................................... 20

8. Stainless-Steel-Clad Assembly Burnup/Enrichment Combinations ..................................... 20

9. Source Term Files Used as Input .......................................................................................... 21

10. Case A - 63,000 MTU Waste Package Characteristics ......................................................... 24

11. Case A - 83,800 MTU Waste Package Characteristics ......................................................... 25

12. Case B - 63,000 MTU Waste Package Characteristics ......................................................... 26

13. Case B - 83,800 MTU Waste Package Characteristics ......................................................... 27

14. Case C - 63,000 MTU Waste Package Characteristics ......................................................... 28

15. Case C - 83,800 MTU Waste Package Characteristics ......................................................... 29

16. List of Attachments ............................................................................................................... 30

17. Disc 1 File Listing ................................................................................................................. 30

18. Disc 2 File Listing ................................................................................................................. 31

19. Disc 3 File Listing ................................................................................................................. 32


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Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
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1. PURPOSE 
This calculation is prepared by the Monitored Geologic Repository Waste Package Requirements 
& Integration Department. The purpose of this calculation is to compile source term and 
commercial waste stream information for use in the analysis of waste package (WP) designs for 
commercial fuel. Information presented will consist of the number of WPs, source terms, metric 
tons of uranium, and the average characteristics of assemblies to be placed in each WP design. 
The source terms provide thermal output, radiation sources, and radionuclide inventories. The 
results of this calculation will support WP analysis for commercial fuel including Performance 
Assessment Operations calculations for nuclide releases. This calculation is prepared in 
accordance with AP-3.12Q, REV 00, ICN 0, Calculations. 

2. METHOD 
A software routine was created (see Section 4.2) for this calculation. The routine is used to (1) 
determine the WP design that can accommodate each assembly in the forecasted waste streams 
based on criticality level, (2) determine source terms for each assembly, and (3) use counters and 
averaging functions to determine other information of interest. See Section 4.2 for the full list of 
software routine functions. 

When calculating WP numbers, this calculation presumes that WPs will have been completely 
loaded to full assembly capacity, with the exception of the last WP loaded for each design type. 
In order to meet limits for total heat generation of a WP, three options are possible: (1) store 
higher thermal output assemblies until they cool, (2) store higher thermal output assemblies until 
enough assemblies with cooler thermal outputs arrive to create a WP that meets the thermal 
limits, and (3) load WPs partially full. The WP numbers presented in this calculation support 
options 1 and 2. 

3. ASSUMPTIONS 
3.1 
CRWMS M&O (1999c) developed source term information for a Babcock & Wilcox 
Mark B pressurized water reactor (PWR) assembly with an initial heavy metal loading of 
475 kg (CRWMS M&O 1999c, p. 7). This assembly was chosen because it has 
characteristics that are generally representative of other PWR assemblies. It is assumed 
that source term values from this assembly can be applied to other PWR assemblies of 
different classes and initial uranium loadings by a simple ratio of initial uranium loading. 
The basis of this assumption is Section 3 of CRWMS M&O (1999c), which states that 
based on the development of the representative PWR assembly and engineering 
judgement, it is assumed that this representative PWR assembly can approximate other 
PWR assembly classes. This assumption is used in Sections 4.2 and 5.1.3. 
3.2 
CRWMS M&O (1999b) developed source term information for a General Electric 2/3 
boiling water reactor (BWR) assembly with an initial heavy metal loading of 200 kg 
(CRWMS M&O 1999b, p. 8). This assembly was chosen because it has characteristics 

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Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
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that are generally representative of other BWR assemblies. It is assumed that source term 
values from this assembly can be applied to other BWR assemblies of different classes 
and initial uranium loadings by a simple ratio of initial uranium loading. The basis of 
this assumption is Assumption 3.1 on page 5 of CRWMS M&O (1999b), which states 
that based on the development of the representative BWR assembly and engineering 
judgement, it is assumed that this representative BWR assembly can approximate other 
BWR assembly classes. This assumption is used in Sections 4.2 and 5.1.3. 

3.3 
CRWMS M&O (1997, pp. 25-26), developed a longer WP to accommodate the South 
Texas PWR assemblies, which were designed for a 14-foot reactor core rather than the 
standard 12-foot reactor core. The WP design that accommodates South Texas assemblies 
is the 12 PWR Absorber Plate-Long WP (see WP Bin 3 in Table 3). While the 12 PWR 
Absorber Plate-Long WP will accommodate other assemblies, either PWR or BWR that 
will not meet loading constraints of other WPs, it is assumed that only South Texas 
assemblies will be loaded into it. The basis of this assumption is that while additional 
assembly types have the potential to be placed into a 12 PWR Absorber Plate-Long WP, 
it is preferred to wait until those assemblies are better characterized as the total number of 
WPs required for disposal should not significantly be affected by this assumption. This 
assumption will underestimate the total number of 12 PWR Absorber Plate-Long WPs. 
See Assumption 3.4 for additional constraints concerning assemblies that could 
potentially be loaded into this WP. This assumption is used in Section 4.2. 
3.4 
It is assumed that the Combustion Engineering 16 x 16 and 16 x 16 System 80 assemblies 
will either arrive without non-fuel components or that the non-fuel components will be 
removed at the repository. This assumption is required to facilitate placing these 
assemblies into a 21 PWR WP instead of a 12 PWR Absorber Plate-Long WP. It is 
currently unknown how many of these assemblies will arrive with non-fuel components. 
For the assemblies that may contain non-fuel components, a study will need to be 
performed to determine if it is more cost-effective to place the assembly in the 12 PWR 
Absorber Plate-Long WP or remove the components for separate disposal and place the 
assemblies into a 21 PWR WP. The basis of this assumption is the same as for 
Assumption 3.3. This assumption is used in Section 4.2. 
3.5 
It is assumed that Big Rock Point assemblies will be placed one each into a basket 
position of a 21 PWR Absorber Plate WP (see WP Bin 1 in Table 3) because Big Rock 
Point BWR Spent Nuclear Fuel (SNF) assemblies have a larger assembly square cross-
sectional area than other BWR assemblies. The basis of this assumption is Section 7.1.2 
of CRWMS M&O (1997), which identified that these assemblies will be disposed of in 
PWR WPs. This assumption is used in Section 4.2. 
3.6 
The current repository thermal design features an upper limit for total heat generation of a 
WP. To accommodate this, pre-emplacement thermal blending of waste may be 
performed. Blending requires that high heat output assemblies be loaded with low heat 

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Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
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output assemblies, such that the WPs heat output falls within a set range. An analysis 
has not been performed to determine if any specific criteria will be required when 
blending high and low heat output assemblies. For this calculation, it is assumed that no 
thermal criteria will be violated when loading a WP with assemblies with large variances 
in heat generation rate as long as the mix of assemblies placed into a WP are below the 
maximum allowable limit. For the Viability Assessment, WP designs were developed to 
hold assemblies with higher heat-generation rates while maintaining cladding 
temperature limits. This assumption is based on the analysis of previous WP designs. 
This assumption is used in Section 5.1.1. 

3.7 
If an arriving assembly has structurally failed, it is assumed that the assembly will be 
placed into a disposable canister that can be loaded in the same WP design as if the 
assembly was intact. The basis of this assumption is the 1999 Design Basis Waste Input 
Report for Commercial Spent Nuclear Fuel (CRWMS M&O 1999a, p. C-5) which states 
that It can be assumed that all of these canisters [unsealed canisters of failed fuel] will 
be screened-end containment vessels essentially identical to those currently in use and 
dimensionally compatible with an uncanistered assembly. Specific historical or 
projected failed assemblies are not presented in the transmittal of the waste arrival cases 
(CRWMS M&O 1999d). This assumption is used in Section 4.2. 
4. USE OF COMPUTER SOFTWARE AND MODELS 
4.1 SOFTWARE APPROVED FOR QUALITY ASSURANCE (QA) WORK 
None used. 

4.2 SOFTWARE ROUTINES 
Microsoft Excel 97 spreadsheet program was used to perform simple calculations that are 
documented in Section 5 and Attachment II. Additionally, these files have been placed as an 
electronic media attachment to this calculation, Attachment III. 

4.2.1 BIN.EXE 
Software Routine Name: BIN.EXE 

Software Routine Version: 00 

Software Routine Developed Using: C89, Version HP92453-01, C programming language 
compiler on a Hewlett-Packard HP-UX operating system, 
Release 10.20 

The BIN.EXE software routine performs the following four functions: 

1. 
For each assembly in the design basis waste stream, BIN.EXE looks up and interpolates, 
if necessary, source term values from source term input files extracted from CRWMS 

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M&O (1999b, 1999c). For the interpolation, eight points must bracket the source terms 
of interest. These eight points represent values in the source tables at locations relative to 
the point of interest as follows: 

Point 1: pre-time, pre-enrichment, pre-burnup
Point 2: pre-time, pre-enrichment, post-burnup
Point 3: pre-time, post-enrichment, pre-burnup
Point 4: pre-time, post-enrichment, post-burnup
Point 5: post-time, pre-enrichment, pre-burnup
Point 6: post-time, pre-enrichment, post-burnup
Point 7: post-time, post-enrichment, pre-burnup
Point 8: post-time, post-enrichment, post-burnup

To obtain the value of interest, seven interpolations are necessary. The first set of 
interpolations is along the plane for burnup and is performed between Points 1 and 2, 
then Points 3 and 4, then Points 5 and 6, then Points 7 and 8. The resulting values can be 
considered a, b, c, and d, respectively. The second set of interpolations is along the 
enrichment plane, interpolating between values a and b, then values c and d. The 
resulting values can be considered ab and cd, respectively. The final interpolation in the 
time plane is between ab and cd, which results in the value of interest. 

All interpolations use the following equation: 

. value2 .

ln.. 

. value1 . 
. assy .. post -assy . 
value =(value2)
.
post - assy 
.
ln ..
. pre-assy ..
. 
.. 

where, 

 
Value is the resulting value from the interpolation. 
 
Value1 and value2 are the values that are being interpolated between, which occur 
at the locations of pre-plane and post-plane, respectively. 
 
Assy represents the value of a assembly characteristic, such as burnup, 
enrichment, or age. 
 
Pre-assy represents the lower interpolation (or extrapolation) bracket value of the 
assembly characteristic, assy. 
 
Post-assy represents the upper interpolation (or extrapolation) bracket value of the 
assembly characteristic, assy. 

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The equation above, when performed for the seven interpolations, represents a three-
dimensional power log interpolation. This same equation was used in the Spent Nuclear 
Fuel Decay Heat Function code and was validated in the software qualification report as 
appropriate for use for interpolating source term values (CRWMS M&O 1996, pp. 9-11). 
It should be noted that this equation will also perform extrapolations. In this calculation, 
the only time these equations are used for extrapolation is when calculating thermal heat 
generation values at 1,000,000 years after the time of waste receipt and for a few 
assemblies that fall outside the burnup/enrichment combinations provided in the source 
term files. To extrapolate, as the pre-assy and post-assy values cannot bracket the values, 
they are assigned to the first two or last two values of burnup, enrichment, or time 
depending on whether the extrapolation needs to be performed below or above the 
existing values. For this calculation, as the extrapolations are very minor, there will be no 
effect on the results. See Section 5.1.3 for detailed information concerning the source 
term files. 

2. 
Determine the WP design type that an assembly can be loaded into, based on keffective 
criticality loading curves (see Section 5.1.1). keffective is defined as the effective neutron 
multiplication factor for an assembly and the calculation of keffective is dependant upon the 
geometry of the packaging of assemblies inside a WP design. Using a simple counter, the 
routine keeps track of the number of assemblies allocated to each WP design. 
3. 
Create average assembly heat generation rate curves for each WP design type. These 
curves are based on normalizing the heat generation curves for each assembly to the time 
of arrival. This is calculated by using the following four steps: (1) determining which 
WP design an assembly will be loaded into based on criticality loading curves, (2) 
calculating assembly heat output, (3) summing the calculated heat output for all 
assemblies that will be loaded into a specific WP design at each time step, and (4) 
dividing the sums at each time step by the number of assemblies loaded into that WP 
design to determine the average heat output at each time step. 
The heat generation rates for the various time-steps evaluated are output in two formats, 
as a simple array and in a format that can be used directly by the software ANSYS. 

4. 
Determine assembly averages for age, burnup, enrichment, and metric tons of uranium 
(MTU) for each WP design. Each of these items is determined by adding together the 
values for each assembly in a given WP design and then dividing by the number of 
assemblies. 
BIN.EXE uses 23 input files: 

 
binInfo.sourcea file which provides WP design information (including design ranges 
for heat output, criticality coefficients, and assembly capacity for each WP design type). 
This input is discussed in Section 5.1.1. 

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WS.sourceA file containing commercial SNF assembly data (including number of 
assemblies, burnup, enrichment, MTU, and age). This input is discussed below in 
Section 5.1.2. 
 
timeSteps.sourceA file containing the time steps used in the source term input files. 
 
20 source term files containing radionuclide activities, gamma and neutron radiation 
sources, cobalt-60 activities, and heat generation rates. See Table 9 for a complete file 
listing, with file descriptions, for these 20 source term input files. 
BIN.EXE creates the following files: 

1. 
AnsysBin[Bin #].datA file which provides a thermal decay curve that represents the 
average assembly to be loaded into a specific WP bin in a format that can be directly 
incorporated into an ANSYS thermal evaluation. These curves, which are in watts, begin at 
the time of assembly receipt at the repository and continue for 1 million years after receipt. 
The creation of these average curves was discussed previously in this Section. As an 
example, AnsysBin1.dat will provide the thermal decay curve that represents the average 
assembly to be placed into WP Bin 1. See Table 3 for the five bins used for this calculation. 
2. 
thermal.datThis file contains the same thermal decay curves as contained in the 
AnsysBin[Bin #].dat suite of files. The values are presented in a fashion that can easily be 
read into Microsoft Excel. 
3. 
average_nuclides.datA file that contains the average assembly curie value for 61 
radionuclides. These average values for assemblies are presented for each WP bin (see Table 
3) and several time steps (time of repository receipt, time of last receipt at the repository, 
then 100, 5000, 10000, 20000, and 1 million years after repository receipt). Table 9 provides 
a listing of the 61 radionuclides. 
4. 
nuclide.datA file that contains the curie value for 61 radionuclides for each assembly 
forecast to be received at the repository. The curie values are based on the assembly age at 
time of repository receipt. For each assembly, this file also reprints the assembly 
characteristics and batch identification number that were read into BIN.EXE from input 
waste stream file. Additionally, the WP bin that each assembly is designated to is output to 
this file. 
5. 
nuclide_mgr_end.datA file that contains the curie value for 61 radionuclides for each 
assembly forecast to be received at the repository. The curie values are based on the 
assembly age based on the time of last repository receipt. For the waste streams in this 
document, the year last receipt is 2033 for the 63,000 MTU arrival cases and 2040 for the 
83,800 MTU arrival cases. For each assembly, this file also reprints the assembly 
characteristics and batch identification number that were read into BIN.EXE from input 

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waste stream file. Additionally, the WP bin that each assembly is designated to is output to 
this file. 

6. 
nuclide_100_years.datA file that contains the curie value for 61 radionuclides for each 
assembly forecast to be received at the repository. The curie values are based on the 
assembly age 100 years after the time of repository receipt. For each assembly, this file also 
reprints the assembly characteristics and batch identification number that were read into 
BIN.EXE from input waste stream file. Additionally, the WP bin that each assembly is 
designated to is output to this file. 
7. 
nuclide_5000_years.datA file that contains the curie value for 61 radionuclides for each 
assembly forecast to be received at the repository. The curie values are based on the 
assembly age 5,000 years after the time of repository receipt. For each assembly, this file 
also reprints the assembly characteristics and batch identification number that were read into 
BIN.EXE from input waste stream file. Additionally, the WP bin that each assembly is 
designated to is output to this file. 
8. 
nuclide_10000_years.datA file that contains the curie value for 61 radionuclides for each 
assembly forecast to be received at the repository. The curie values are based on the 
assembly age 10,000 years after the time of repository receipt. For each assembly, this file 
also reprints the assembly characteristics and batch identification number that were read into 
BIN.EXE from input waste stream file. Additionally, the WP bin that each assembly is 
designated to is output to this file. 
9. 
nuclide_20000_years.datA file that contains the curie value for 61 radionuclides for each 
assembly forecast to be received at the repository. The curie values are based on the 
assembly age 20,000 years after the time of repository receipt. For each assembly, this file 
also reprints the assembly characteristics and batch identification number that were read into 
BIN.EXE from input waste stream file. Additionally, the WP bin that each assembly is 
designated to is output to this file. 
10. nuclide_1mil_years.datA file that contains the curie value for 61 radionuclides for each 
assembly forecast to be received at the repository. The curie values are based on the 
assembly age 1 million years after the time of repository receipt. For each assembly, this file 
also reprints the assembly characteristics and batch identification number that were read into 
BIN.EXE from input waste stream file. Additionally, the WP bin that each assembly is 
designated to is output to this file. 
11. bin.datA file that contains the bin number, the heat generation rate, and the cobalt-60 
values for each assembly forecast to be received at the repository. The cobalt-60 values are 
presented for four assembly regions: top end-fitting, bottom end-fitting, plenum, and fuel. 
The values are based on the assembly age at the time of repository receipt. For each 
assembly, this file also reprints the assembly characteristics and batch identification number 

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that were read into BIN.EXE from input waste stream file. Additionally, the WP bin that 
each assembly is designated to is output to this file. 

12. gamma.datA file that contains the photons per second value for each assembly forecast to 
be received at the repository. The values are based on the assembly age at the time of 
repository receipt and are presented for 18 energy bands. For each energy band, the values 
are presented for four assembly regions: top end-fitting, bottom end-fitting, plenum, and 
fuel. For each assembly, this file also reprints the assembly characteristics and batch 
identification number that were read into BIN.EXE from input waste stream file. 
Additionally, the WP bin that each assembly is designated to is output to this file. 
13. neutron.datA file that contains the neutrons per second value for each assembly forecast to 
be received at the repository. The values are based on the assembly age at the time of 
repository receipt and are presented for 18 energy bands. For each assembly, this file also 
reprints the assembly characteristics and batch identification number that were read into 
BIN.EXE from input waste stream file. Additionally, the WP bin that each assembly is 
designated to is output to this file. 
14. preblend.datA file that contains the bin number and the heat generation rate for each 
assembly forecast to be received at the repository. This file was especially setup to print only 
one assembly per file line to allow the file to be easily incorporated as input to another 
software routine which performs a scoping analysis for thermal blending of assemblies. For 
each assembly, this file also reprints the assembly characteristics and batch identification 
number that were read into BIN.EXE from input waste stream file. Additionally, the WP bin 
that each assembly is designated to is output to this file. 
15. summary.datThis file contains a summary of the WP bins and assembly arrivals. This 
summary presents the yearly number of assemblies to arrive for each WP bin and the number 
of WPs that would result from the loading of those assemblies. This file also contains other 
summary information for each WP bin, including the number of assemblies, average 
assembly age, average assembly heat generation rate at time of repository receipt, average 
assembly burnup, average assembly enrichment, average assembly initial MTU, and total 
MTU. 
Output files 2 through 15 contain header lines to label the information contained in the file. 
Table 1 lists all the heading descriptions used in the output files and their meaning. 


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Table 1. Output File Heading Descriptions 

Heading Description Units 
.20E+02to.64E+01 
.64E+01to.30E+01 
.30E+01to.19E+01 
.19E+01to.14E+01 
.14E+01to.90E+00 
.90E+00to.40E+00 
.40E+00to.10E+00 
.10E+00to.17E-01 
.17E-01to.30E-02 
.30E-02to.55E-03 
.55E-03to.10E-03 
.10E-03to.30E-04 
.30E-04to.10E-04 
.10E-04to.31E-05 
.31E-05to.18E-05 
.18E-05to.13E-05 
.13E-05to.11E-05 
.11E-05to.10E-05 
.10E-05to.80E-06 
.80E-06to.40E-06 
.40E-06to.33E-06 
.33E-06to.22E-06 
.22E-06to.10E-06 
.10E-06to.50E-07 
.50E-07to.30E-07 
.30E-07to.10E-07 
.10E-07to.10E-10 
These headings pertain to the 27 
neutron energy bands and represent 
the MeV range for each energy band 
Information under these headings 
are in neutrons per second 
.50E-01to.10E-01 
.10E+00to.50E-01 
.20E+00to.10E+00 
.30E+00to.20E+00 
.40E+00to.30E+00 
.60E+00to.40E+00 
.80E+00to.60E+00 
.10E+01to.80E+00 
.13E+01to.10E+01 
.17E+01to.13E+01 
.20E+01to.17E+01 
.25E+01to.20E+01 
.30E+01to.25E+01 
.40E+01to.30E+01 
.50E+01to.40E+01 
.65E+01to.50E+01 
.80E+01to.65E+01 
.10E+02to.80E+01 
These headings pertain to the 18 
gamma energy bands and represent 
the MeV range for each energy band 
Information under these headings 
are in photons per second 
age Assembly age years 
assy_# This represents a distinct assembly 
number assigned by BIN.EXE to 
each assembly in the preblend.dat 
file 
N/A 
assy_count Number of assemblies per output file 
line 
N/A 
assy_Mtu Assembly initial metric tons uranium metric tons 
Avg. Age Average assembly age years 


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Heading Description Units 
Avg. Assy Watts Average assembly heat generation 
rate 
watts 
Avg. Burnup Average assembly burnup GWd/MTU 
Avg. Enrich. Average assembly initial enrichment % 
Avg. MTU/Assy Average metric tons uranium per 
assembly 
metric tons 
batch-ID Batch identification provided in waste 
stream input files 
N/A 
Bin WP bin that assembly will be loaded 
into 
N/A 
bottom Bottom end-fitting region N/A 
burnup Assembly burnup GWd/MTU 
cask_# Arriving cask number provided by 
waste stream input files 
N/A 
Co60(bottom) Cobalt-60 value for the assembly 
bottom end-fitting region 
curies 
Co60(fuel) Cobalt-60 value for the assembly fuel 
region 
curies 
Co60(plenum) Cobalt-60 value for the assembly 
plenum region 
curies 
Co60(top) Cobalt-60 value for the assembly top 
end-fitting region 
curies 
csk_type Cask type R = rail cask, T = truck cask, D = rail 
cask containing a non-disposable 
dual-purpose canister 
D_Yr Assembly discharge year year 
enrich Assembly initial enrichment % 
fuel Assembly fuel region N/A 
MTU or Mtu Metric tons of uranium metric tons 
Number of Assy Number of assemblies N/A 
Number of WPs Number of WPs N/A 
plenum Assembly plenum region N/A 
R_Yr Assembly receipt year at the 
repository 
year 
reactor name Reactor name N/A 
SS Indicates whether the assembly has 
stainless steel cladding 
0 = zircaloy cladding, 
1 = stainless-steel cladding 
top Assembly top end-fitting region N/A 
Total MTU Total metric tons of uranium metric tons 
type Assembly type BWR or PWR 
watts Assembly heat generation rate watts 
WP WP bin number N/A 
Years after loading This description is used in the 
thermal.dat output file and for this 
calculation signifies the time since 
repository receipt. For thermal 
evaluations, the assembly thermal 
outputs are assumed to be based on 
time since WP loading, which is what 
is reflected in this heading. 
years 

This software routine was checked to ensure that it provided the correct results for its intended 
use in this calculation. Check of BIN.EXE by the use of a simple spreadsheet calculation is 
provided in Attachment III. 


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4.2.2 SURFACESORT.EXE 
Software Routine Name: SURFACESORT.EXE 
Software Routine Version: 00 
Software Routine Developed Using: C89, Version HP92453-01, C programming language 

compiler on a Hewlett-Packard HP-UX operating system, 
Release 10.20 

In addition to the BIN.EXE software routine, a second routine entitled SURFACESORT.EXE 
was developed to translate the output from BIN.EXE into a format that can be directly input into 
the WITNESS software code. The WITNESS software code is used to simulate the operations of 
the repository surface facilities. 

SURFACESORT.EXE uses the preblend.dat output file from BIN.EXE and translates it into a 
form that can be directly input into WITNESS. For each commercial waste stream arrival case, 
there are three files generated by SURFACESORT.EXE. These files are truck.dat, rail.dat, and 
DPC.dat. Truck.dat contains cask information for casks arriving by truck. Rail.dat contains cask 
information for rail casks transporting uncanistered assemblies. DPC.dat contains cask 
information for rail casks containing dual-purpose canisters. 

The output files from SURFACESORT.EXE are all in the same comma delimited format: 

Cask Line: Cask Type, Cask Quantity, Cask Arrival Time , , , Cask Number, Cask Arrival Year 
Assembly Line: Assembly Loading, Assembly Quantity, Assembly Arrival Time, "HEAT=" Assembly Heat Output 

The number of assembly lines is equal to the number of assemblies in the cask. This sequence of 
cask line followed by multiple assembly lines repeats until all arrivals are complete. 

The items for the output lines are described below: 

 
Cask TypeR = rail, T = truck, C = dual-purpose canister shipped via rail. The output 
files from SURFACESORT.EXE have been separated by cask type and will not contain 
varying cask types. 
 
Cask QuantityAlways set as 1, required for WITNESS. 
 
Cask Arrival TimeThis is determined by dividing the number of repository operating 
minutes (set at 504,000 minutes) by the number of casks arriving in a given year. All 
casks are then spaced to arrive evenly throughout the year. This is required for 
WITNESS. Arrival time does not start at zero for each year but continues from the 
previous year. 

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NOTE: The sequencing specified within a year by a design basis waste stream is just a 
reflection of the CALVIN software code and was not intended as an actual arrival 
sequence. SURFACESORT.EXE provides the within-year sequencing as output by 
CALVIN. This sequence will provide one variation of a potential receipt scenario. 

 
Cask NumberThis is a unique cask identifier and is directly extracted from the 
preblend.dat file, which recorded it from the design basis waste stream files (CRWMS 
M&O 1999d). 
 
Cask Arrival YearThis is the year the cask is forecast to arrive at the repository and is 
directly extracted from the preblend.dat file, which recorded it from the design basis 
waste stream files (CRWMS M&O 1999d). 
 
Assembly LoadingThis defines the WP design type that can accommodate the 
assembly. The WP design type is directly extracted from the preblend.dat file and then 
translated as shown in Table 2. 
NOTE: There are five commercial WP designs, so one design type was neglected due to 
current WITNESS constraints. The neglected design is the 12 PWR Absorber Plate-Long 
(Bin 3 in Table 3). 

Table 2. SURFACESORT.EXE Waste Package Translation 

WP Design WP Bin as Identified in 
BIN.EXE preblend.dat file 
WP as identified in 
SURFACESORT.EXE 
output files 
21 PWR Absorber Plate 1 PWR1 
21 PWR Control Rod 2 PWR2 
44 BWR Absorber Plate 4 BWR1 
24 BWR Thick Absorber 
Plate 
5 BWR2 

 
Assembly QuantityAlways set as 1, required for WITNESS. 
 
Assembly Arrival TimeThis value is equal to the cask arrival time for the cask that the 
assembly will arrive in (see description for Cask Arrival Time above). 
 
Assembly Heat OutputThis value is in watts and denotes the heat generation rate of the 
assembly at the time of repository receipt. This value is recorded as presented in the 
preblend.dat file. 
The SURFACESORT.EXE output is readily checked by visual inspection. 


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4.3 MODELS 
None used. 

5. CALCULATION 
5.1 CALCULATION INPUTS 
5.1.1 Assembly Constraints 
This calculation uses the WP designs and constraints from Tables 3 and 4 to determine which 
assemblies can be placed into a specific WP design. While BIN.EXE has the capability to 
exclude an assembly from being placed into a WP design based on heat generation rate at time of 
arrival, for this calculation the heat generation rate limits are set such that no assembly will be 
disqualified from loading (see Assumption 3.6). Therefore, criticality level and assembly class 
determine which WP design an assembly will be placed into. 

This calculation evaluates criticality based on keffective. The keffective equation used is: 

keffective + 2s = c0 + c1B + c2E + c3B2 + c4E2 + c5B3 + c6E3 

where, 

 
c0, c1, c2, c3, c4, c5, and c6 are criticality coefficients as shown in Table 3. 
 
B is the assembly burnup, in gigawatts-days per MTU, provided by CRWMS M&O 
(1999d) (see Section 5.1.2). 
 
E is the assembly initial U-235 enrichment, in weight percent, provided by CRWMS M&O 
(1999d) (see Section 5.1.2). 
Criticality coefficients have only been developed for two of the five WP designs (see Table 3), 
the 21 PWR Absorber Plate WP, and the 44 BWR Absorber Plate WP. These coefficients were 
developed in the Disposal Criticality Analysis Methodology Topical Report (YMP 1998, Table 
C-12 and Eq. C-7, p. C-43). The criticality equation above applies to scenarios where the fuel 
has degraded and is lumped at the bottom of the WP. This represents the most reactive 
geometric configuration. For the degraded configuration, the maximum acceptable keffective + 2s 
limit was set at 0.98. The coefficients that were used for this calculation are provided in Table 

3. 
The criticality coefficients for WP Bins 2, 3, and 5 in Table 3 have been set to zero. When all 
coefficients are set to zero, keffective will always be calculated as zero. Therefore, if a PWR 
assembly (excluding South Texas assemblies) cannot be placed in Bin 1, then it will always be 


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placed in Bin 2. All South Texas assemblies will be placed into Bin 3. If a BWR assembly 
cannot be placed into Bin 4, then it will always be placed in Bin 5. As criticality coefficients are 
generated for the remaining WP designs, it may be determined that some assemblies exceed 
acceptable criticality levels and will require special handling. 

Table 3. Waste Package Criticality Coefficients 

Waste Package Designs 
Bin 1 Bin 2 Bin 3 Bin 4 Bin 5 
Criticality 
Coefficients 
21 PWR 
Absorber Plate 
21 PWR 
Control Rod 
12 PWR 
Absorber 
Plate-Long 
44 BWR 
Absorber Plate 
24 BWR Thick 
Absorber Plate 
c0 0.640653 0 0 0.850736 0 
c1 -0.0102912 0 0 -0.007751 0 
c2 0.300169 0 0 0.087294 0 
c3 -2.54581E-05 0 0 0 0 
c4 -0.0490929 0 0 0 0 
c5 9.92035E-07 0 0 0 0 
c6 0.00364521 0 0 0 0 

The WPs listed in Tables 3 and 4 are slightly modified from those presented in the License 
Application Design Selection Feature Report: Aging and Blending (CRWMS M&O 1999e, p. 
10). The WP designs in CRWMS M&O (1999e) with no absorber plates for criticality control 
were removed from the design list to ensure defense-in-depth and reduce the chance of criticality 
misload. 

Table 4. Commercial Waste Package Designs 

Bin # WP Design Assembly 
Capacity 
Allowable Assembly 
Heat Generation 
Range, watts 
min max 
1 21 PWR Absorber Plate 21 0 2100 
2 21 PWR Control Rod 21 0 2100 
3 12 PWR Absorber Plate-Long 12 0 2100 
4 44 BWR Absorber Plate 44 0 750 
5 24 BWR Thick Absorber Plate 24 0 750 

The Waste Container Cavity Size Determination document (CRWMS M&O 1997, pp. 25-26) 
determined which assembly classes could be placed in a standard WP basket cell. All classes of 
PWR assemblies evaluated in Section 4 of CRWMS M&O (1997) can be placed into WP Bins 1 
and 2 in Table 4 with the exception of the longer South Texas assemblies. South Texas 
assemblies will be placed into WP Bin 3. Additionally, WP Bin 3 could hold other assembly 
classes but not enough definition is available to determine the number of assemblies that would 
need to be placed into it (see Assumptions 3.3 and 3.4). The cavity size for WP Bins 4 and 5 can 
hold all of the BWR assembly classes identified in Section 4 of CRWMS M&O (1997). 


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5.1.2 Commercial Waste Streams 
Information for assembly type, burnup, initial U-235 enrichment, MTU per assembly, discharge 
year, repository receipt year, and other shipment information is provided in CRWMS M&O 
(1999d). This information was developed for the 1999 Design Basis Waste Stream Input Report 
for Commercial Spent Nuclear Fuel (CRWMS M&O 1999a). Since it is unknown which 
assemblies the utilities will send at a given time, six arrival forecasts were developed based on 
three different arrival case methodologies to account for the most likely scenarios. 

The six arrival forecasts are as follows: 

1. Case A63,000 MTU, fuel selection begins with 10-year-old spent fuel 
2. Case A83,800 MTU, fuel selection begins with 10-year-old spent fuel 
3. Case B63,000 MTU, fuel selection begins with 10-year-old spent fuel in strict order of age 
4. Case B83,800 MTU, fuel selection begins with 10-year-old spent fuel in strict order of age 
5. Case C63,000 MTU, fuel selection begins with oldest fuel first 
6. Case C83,800 MTU, fuel selection begins with oldest fuel first. 
More description of these cases can be found on pages A-3 through A-5 in CRWMS M&O 
(1999a). It should be noted that two additional cases, D and E, were evaluated in CRWMS 
M&O (1999a), but were deemed inappropriate for design (CRWMS M&O 1999a, p. A-5) and 
are not evaluated herein. 

Table 5 provides general waste stream arrival case characteristics, which were calculated using 
Microsoft Excel 97. It should be noted that occasionally the 83,800 MTU forecasts are referred 
to as 84k MTU cases for convenience. 

When deciding which WP designs can accommodate assemblies from the detailed waste streams, 
Big Rock Point and South Texas assemblies must be identified (see Assumptions 3.3 and 3.5). 
As assembly classes are not listed in the waste stream source files (CRWMS M&O 1999d), these 
assembly classes will be determined solely on the identification of the Big Rock Point and South 
Texas reactor sites. Some assemblies could potentially be held at other locations, but as the 
number of unidentified should not be significant, it will not have any appreciable effect on the 
results of this calculation. 


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Table 5. Arrival Case Characteristics 

Arrival Case Assembly 
Type 
Number of 
Assemblies 
Average 
Assembly 
Age 
(years) 
Median 
Assembly 
Age 
(years) 
Average 
Assembly 
Burnup 
(MWd/MTU) 
Average 
Assembly 
Initial U-235 
Enrichment 
(wt.%) 
Average 
Assembly 
Initial MTU 
Case A BWR 
126984 22.7 18 33626 3.03 0.177 
63,000 MTU PWR 93770 23.1 19 41214 3.75 0.432 
Case A BWR 
166942 25.3 21 33592 3.02 0.177 
83,800 MTU PWR 124761 25.3 21 41697 3.75 0.434 
Case B BWR 
127212 22.1 17 34803 3.09 0.177 
63,000 MTU PWR 93770 21.9 16 42615 3.82 0.432 
Case B BWR 
166942 25.3 19 33592 3.02 0.177 
83,800 MTU PWR 124761 25.3 19 41697 3.75 0.434 
Case C BWR 
126316 24.6 23 31969 2.94 0.178 
63,000 MTU PWR 93870 24.6 23 40132 3.67 0.432 
Case C BWR 
166942 25.4 24 33592 3.02 0.177 
83,800 MTU PWR 124761 25.3 24 41697 3.75 0.434 

5.1.3 Source Terms 
Source terms for BWR and PWR assemblies were taken from CRWMS M&O (1999b and 
1999c, respectively). In these documents, a representative assembly was developed to determine 
source terms. In these calculations, the representative assemblies are assumed (see Assumptions 

3.1 and 3.2) to be applicable to assemblies of different classes and MTU loadings. The 
representative assembly characteristics are presented in Table 6. 
Table 6. Representative Assembly Characteristics 

PWR Assembly BWR Assembly 
Initial Mass of Uranium 
per Assembly 0.475 MTU 0.200 MTU 
Assembly Class Babcock & Wilcox Mark B 15x15 General Electric 2/3 8x8 

The assemblies in Table 6 were evaluated for both zircaloy cladding and stainless-steel cladding 
using various burnup and enrichment combinations. Table 7 reflects the burnup/enrichment 
combinations used in this calculation for zircaloy-clad assemblies and Table 8 reflects those used 
for stainless-steel-clad assemblies. These burnup and enrichment combinations were evaluated 
for 180 time steps, ranging from 1 year after reactor discharge to 1 million years after reactor 
discharge. 


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Table 7. Zircaloy-Clad Assembly Burnup/Enrichment Combinations 

Enrichment (% initial U235 
enrichment) 
Burnups Evaluated for Each Enrichment (GWd/MTU) 
PWR and BWR Assemblies 
0.711 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
1.00 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
1.50 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
2.00 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
2.50 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
3.00 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
3.50 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
4.00 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
4.50 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
5.00 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 
5.50 0.001, 0.01, 0.1, 1, 10, 20, 30, 40, 50, 60, 70, 75 

Table 8. Stainless-Steel-Clad Assembly Burnup/Enrichment Combinations 

Enrichment (% initial U235 
enrichment) 
Burnups Evaluated for Each Enrichment (GWd/MTU) 
PWR Assemblies 
1.00 1, 10, 20, 30, 40 
1.50 1, 10, 20, 30, 40 
2.00 1, 10, 20, 30, 40 
2.50 1, 10, 20, 30, 40 
3.00 1, 10, 20, 30, 40 
3.50 1, 10, 20, 30, 40 
4.00 1, 10, 20, 30, 40 
4.50 1, 10, 20, 30, 40 
5.00 1, 10, 20, 30, 40 
5.50 1, 10, 20, 30, 40 
BWR Assemblies 
3.50 1, 10, 20, 30, 40 
4.00 1, 10, 20, 30, 40 

Table 9 provides an overview of the source files used in this calculation that were developed in 
CRWMS M&O (1999b, 1999c) and provided as electronic attachments to those references 
(Attachments IV and VII, respectively). These source files are based on calculations for the 
representative assemblies shown in Table 6 and reflect the burnup and enrichment combinations 
shown in Tables 7 and 8. 

It should be noted that the source term files provide the average source terms for an assembly or 
assembly regions, as appropriate. For some calculations, it may be appropriate to add an axial 
peaking factor to the results of this calculation. 


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Table 9. Source Term Files Used as Input 

File Names Description 
PWR.thermal.source 
BWR.thermal.source 
Provides six components of heat generation rates, in watts, for a zircaloy-clad PWR 
and BWR assembly, respectively: light elements in the fuel region, fission products in 
the fuel region, actinides in the fuel region, light elements in the bottom end-fitting, 
light elements in the plenum region, and light elements in the top end-fitting region. 
PWRSS.thermal.source 
BWRSS.thermal.source 
Provides six components of heat generation rates, in watts, for a stainless-steel-clad 
PWR and BWR assembly, respectively. These components are the same as listed 
above for zircaloy-clad assemblies. 
PWR.nuclide.source 
BWR.nuclide.source 
Provides 61 nuclides, in curies per assembly, for a zircaloy-clad PWR and BWR 
assembly, respectively: 
ac-227 am-241 am-242m am-243 ba-137m 
c-14 cd-113m cl-36 cm-242 cm-243 
cm-244 cm-245 cm-246 cm-247 co-60 
cs-134 cs-135 cs-137 eu-154 eu-155 
fe-55 fr-221 h-3 I-129 kr-85 
nb-93m nb-94 ni-59 ni-63 np-237 
pa-231 pb-210 pd-107 pm-147 po-218 
pu-238 pu-239 pu-240 pu-241 pu-242 
ra-226 ra-228 ru-106 sb-125 se-79 
sm-147 sm-151 sn-126 sr-90 tc-99 
th-229 th-230 th-232 u-232 u-233 
u-234 u-235 u-236 u-238 y-90 
zr-93 
PWRSS.nuclide.source 
BWRSS.nuclide.source 
Provides 61 nuclides, in curies per assembly, for a stainless-steel-clad PWR and 
BWR assembly, respectively. These nuclides are the same as those listed above for 
zircaloy-clad assemblies. 
PWR.gamma.source 
BWR.gamma.source 
Provides values for 18 gamma energy bands, in photons per second, for the fuel, 
bottom end-fitting, plenum, and top end-fitting regions of a zircaloy-clad PWR and 
BWR assembly, respectively: 
Energy Bands, MeV 
Energy, high Energy, low 
5.00E-02 1.00E-02 
1.00E-01 5.00E-02 
2.00E-01 1.00E-01 
3.00E-01 2.00E-01 
4.00E-01 3.00E-01 
6.00E-01 4.00E-01 
8.00E-01 6.00E-01 
1.00E+00 8.00E-01 
1.33E+00 1.00E+00 
1.66E+00 1.33E+00 
2.00E+00 1.66E+00 
2.50E+00 2.00E+00 
3.00E+00 2.50E+00 
4.00E+00 3.00E+00 
5.00E+00 4.00E+00 
6.50E+00 5.00E+00 
8.00E+00 6.50E+00 
1.00E+01 8.00E+00 
PWRSS.gamma.source 
BWRSS.gamma.source 
Provides values for 18 gamma energy bands, in photons per second, for the fuel 
region of a stainless-steel-clad PWR and BWR assembly, respectively. The energy 
bands are the same as those listed above for zircaloy-clad assemblies. 


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File Names Description 
PWR.neutron.source 
BWR.neutron.source 
Provides values for 27 neutron energy bands, in neutrons per second, for the fuel 
region of a zircaloy-clad PWR and BWR assembly, respectively: 
Energy Bands, MeV 
Energy, high Energy, low 
2.00E+01 6.43E+00 
6.43E+00 3.00E+00 
3.00E+00 1.85E+00 
1.85E+00 1.40E+00 
1.40E+00 9.00E-01 
9.00E-01 4.00E-01 
4.00E-01 1.00E-01 
1.00E-01 1.70E-02 
1.70E-02 3.00E-03 
3.00E-03 5.50E-04 
5.50E-04 1.00E-04 
1.00E-04 3.00E-05 
3.00E-05 1.00E-05 
1.00E-05 3.05E-06 
3.05E-06 1.77E-06 
1.77E-06 1.30E-06 
1.30E-06 1.13E-06 
1.13E-06 1.00E-06 
1.00E-06 8.00E-07 
8.00E-07 4.00E-07 
4.00E-07 3.25E-07 
3.25E-07 2.25E-07 
2.25E-07 1.00E-07 
1.00E-07 5.00E-08 
5.00E-08 3.00E-08 
3.00E-08 1.00E-08 
1.00E-08 1.00E-11 
PWRSS.neutron.source 
BWRSS.neutron.source 
Provides values for 27 neutron energy bands, in neutrons per second, for the fuel 
region of a stainless-steel clad PWR and BWR assembly, respectively. The energy 
bands are the same as those listed above for zircaloy-clad assemblies. 
PWR.cobalt.source 
BWR.cobalt.source 
Provides cobalt-60 source terms, in curies, for the fuel, bottom end-fitting, plenum, 
and top end-fitting regions of a zircaloy-clad PWR and BWR assembly, respectively. 
PWRSS.cobalt.source 
BWRSS.cobalt.source 
Provides cobalt-60 source terms, in curies, for the fuel, bottom end-fitting, plenum, 
and top end-fitting regions of a stainless-steel-clad PWR and BWR assembly, 
respectively. 

It should be noted that the detailed waste stream information from CRWMS M&O 1999d 
contains projected commercial mixed-oxide (MOX) assemblies. As the current MOX source 
terms are not in the proper format to be included as source files to the BIN.EXE software 
routine, the MOX assemblies are approximated as standard uranium-oxide assemblies when 
calculating source terms. MOX assemblies compromise a small percentage, 0.6% (1800 
assemblies), of the total assemblies projected to be discharged from reactors. Because of this, 
treating MOX assemblies as uranium-oxide assemblies will have little impact on average values 
determined by this calculation. For evaluations that are performed on a per assembly basis, 
MOX source terms from other references should be considered. 


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5.2 PROCEDURE 
The software routine BIN.EXE was run for the set of WP designs identified in Section 5.1.1 for 
each waste stream identified in Section 5.1.2. The source terms identified in Section 5.1.3 were 
used for all runs. After the BIN.EXE runs were complete, the SURFACESORT.EXE software 
routine was run for each waste arrival case using the BIN.EXE preblend.dat output file. 

6. RESULTS 
The output files for the software routines BIN.EXE and SURFACESORT.EXE are contained as 
an electronic media attachment to this calculation. Tables 17 through 19 detail the file listings for 
the electronic media. 

Summaries of the number of WPs and average thermal properties are presented in Tables 10 
through 15 and are based on information from the BIN.EXE summary.dat output files. The 
number of WPs presented is based on WPs that have been loaded to full assembly capacity, with 
the exception of the final WPs loaded. The average WP heat generation rates provided are based 
on the average assembly heat generation rate for each WP design multiplied by the assembly 
capacity for that design. 

The source term results from this calculation are not based on the use of an axial peaking factor. 
For analysis that will be based on the results of this calculation, it may be appropriate to apply an 
axial peaking factor. Additionally, it should again be noted that the MOX assemblies in this 
report are treated as uranium-oxide assemblies. For evaluations that are performed on a per 
assembly basis, MOX source terms from other references should be considered. 

This document and its conclusions may be affected by technical product input information that 
requires confirmation. Any changes to the document or its conclusions that may occur as a result 
of completing the confirmation activities will be reflected in subsequent revisions. The status of 
the input information quality may be confirmed by review of the Document Input Reference 
System database. 


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Table 10. Case A -63,000 MTU Waste Package Characteristicsa 

WP Design Average 
WP Heat 
Generation 
Rate Based 
on 
Assembly 
Heat at 
Repository 
Arrival 
(kW)b 
Number of 
Assemblies 
Number 
of WPs 
Average 
Initial 
Burnup 
(GWd / 
MTU) 
Average 
Initial U-235 
Enrichment 
Average 
MTU / 
Assembly 
Average 
Assembly 
Age 
(years) 
Total MTU 
21 PWR 
Absorber 
Plate 
11.53 90262 4299 41.485 3.74 0.430 23.00 38818.86 
21 PWR 
Control 
Rod 
3.11 1992 95 19.624 3.57 0.368 36.14 733.28 
12 PWR 
Absorber 
Plate-Long 
9.55 1955 163 46.326 4.01 0.540 18.04 1055.71 
44 BWR 
Absorber 
Plate 
7.38 124532 2831 34.080 3.04 0.177 22.41 22050.28 
24 BWR 
Thick 
Absorber 
Plate 
0.52 2013 84 8.065 2.63 0.167 40.32 335.55 
Totals 220754 7472 62993.68 

NOTES: 

a Information in table based on summary.dat file for waste arrival Case A, 63,000 MTU. 

b Average WP Heat Generation Rate, kW: 9.68 
Average PWR WP Heat Generation Rate, kW: 11.28 
Average BWR WP Heat Generation Rate, kW: 7.18 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page25 of 35

Table 11. Case A -83,800 MTU Waste Package Characteristicsa 

WP 
Design 
Average 
WP Heat 
Generation 
Rate Based 
on 
Assembly 
Heat at 
Repository 
Arrival 
(kW)b 
Number of 
Assemblies 
Number 
of WPs 
Average 
Initial 
Burnup 
(GWd / 
MTU) 
Average 
Initial U-235 
Enrichment 
Average 
MTU / 
Assembly 
Average 
Assembly 
Age 
(years) 
Total MTU 
21 PWR 
Absorber 
Plate 
11.33 119480 5690 41.976 3.75 0.431 25.20 51529.19 
21 PWR 
Control 
Rod 
3.26 2207 106 19.862 3.61 0.376 35.83 829.07 
12 PWR 
Absorber 
Plate-Long 
8.97 3513 293 43.337 3.77 0.540 21.59 1897.56 
44 BWR 
Absorber 
Plate 
7.00 164165 3732 33.981 3.02 0.178 25.08 29140.39 
24 BWR 
Thick 
Absorber 
Plate 
0.54 2338 98 8.480 2.68 0.169 41.82 395.28 
Totals 291703 9919 83791.49 

NOTES: 

a Information in table based on summary.dat file for waste arrival Case A, 83,800 MTU. 

b Average WP Heat Generation Rate, kW: 9.43 
Average PWR WP Heat Generation Rate, kW: 11.07 
Average BWR WP Heat Generation Rate, kW: 6.83 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page26 of 35

Table 12. Case B -63,000 MTU Waste Package Characteristicsa 

WP 
Design 
Average 
WP Heat 
Generation 
Rate Based 
on 
Assembly 
Heat at 
Repository 
Arrival 
(kW)b 
Number of 
Assemblies 
Number 
of WPs 
Average 
Initial 
Burnup 
(GWd / 
MTU) 
Average 
Initial U-235 
Enrichment 
Average 
MTU / 
Assembly 
Average 
Assembly 
Age 
(years) 
Total MTU 
21 PWR 
Absorber 
Plate 
12.51 90310 4301 42.887 3.81 0.43 21.8 38827.55 
21 PWR 
Control 
Rod 
3.06 1944 93 19.544 3.56 0.366 36.31 711.68 
12 PWR 
Absorber 
Plate-Long 
10.92 1955 163 48.302 4.1 0.54 14.9 1055.70 
44 BWR 
Absorber 
Plate 
7.79 124769 2836 35.279 3.1 0.177 21.81 22069.04 
24 BWR 
Thick 
Absorber 
Plate 
0.52 2004 84 8.042 2.63 0.167 40.39 333.95 
Totals 220982 7477 62997.92 

NOTES: 

a Information in table based on summary.dat file for waste arrival Case B, 63,000 MTU. 

b Average WP Heat Generation Rate, kW: 10.43 
Average PWR WP Heat Generation Rate, kW: 12.26 
Average BWR WP Heat Generation Rate, kW: 7.58 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page27 of 35

Table 13. Case B -83,800 MTU Waste Package Characteristicsa 

WP 
Design 
Average 
WP Heat 
Generation 
Rate Based 
on 
Assembly 
Heat at 
Repository 
Arrival 
(kW)b 
Number of 
Assemblies 
Number 
of WPs 
Average 
Initial 
Burnup 
(GWd / 
MTU) 
Average 
Initial U-235 
Enrichment 
Average 
MTU / 
Assembly 
Average 
Assembly 
Age 
(years) 
Total MTU 
21 PWR 
Absorber 
Plate 
11.64 119480 5690 41.976 3.75 0.431 25.2 51529.19 
21 PWR 
Control 
Rod 
3.23 2207 106 19.862 3.61 0.376 36.19 829.07 
12 PWR 
Absorber 
Plate-Long 
9.25 3513 293 43.337 3.77 0.54 21.59 1897.56 
44 BWR 
Absorber 
Plate 
7.10 164165 3732 33.981 3.02 0.178 25.06 29140.39 
24 BWR 
Thick 
Absorber 
Plate 
0.54 2338 98 8.48 2.68 0.169 41.88 395.28 
Totals 291703 9919 83791.49 

NOTES: 

a Information in table based on summary.dat file for waste arrival Case B, 83,800 MTU. 

b Average WP Heat Generation Rate, kW: 9.66 
Average PWR WP Heat Generation Rate, kW: 11.37 
Average BWR WP Heat Generation Rate, kW: 6.93 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page28 of 35

Table 14. Case C -63,000 MTU Waste Package Characteristicsa 

WP 
Design 
Average 
WP Heat 
Generation 
Rate Based 
on 
Assembly 
Heat at 
Repository 
Arrival 
(kW)b 
Number of 
Assemblies 
Number 
of WPs 
Average 
Initial 
Burnup 
(GWd / 
MTU) 
Average 
Initial U-235 
Enrichment 
Average 
MTU / 
Assembly 
Average 
Assembly 
Age 
(years) 
Total MTU 
21 PWR 
Absorber 
Plate 
10.69 90238 4298 40.536 3.68 0.43 24.34 38786.87 
21 PWR 
Control 
Rod 
3.52 2116 101 19.547 3.59 0.373 34.3 790.19 
12 PWR 
Absorber 
Plate-Long 
6.62 1955 163 39.67 3.54 0.54 25.71 1056.24 
44 BWR 
Absorber 
Plate 
6.49 123552 2808 32.448 2.94 0.178 24.36 21970.61 
24 BWR 
Thick 
Absorber 
Plate 
0.59 2325 97 8.466 2.68 0.169 37.34 392.89 
Totals 220186 7467 62996.8 

NOTES: 

a Information in table based on summary.dat file for waste arrival Case C, 63,000 MTU. 

b Average WP Heat Generation Rate, kW: 8.79 
Average PWR WP Heat Generation Rate, kW: 10.39 
Average BWR WP Heat Generation Rate, kW: 6.29 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page29 of 35

Table 15. Case C -83,800 MTU Waste Package Characteristicsa 

WP 
Design 
Average 
WP Heat 
Generation 
Rate Based 
on 
Assembly 
Heat at 
Repository 
Arrival 
(kW)b 
Number of 
Assemblies 
Number 
of WPs 
Average 
Initial 
Burnup 
(GWd / 
MTU) 
Average 
Initial U-235 
Enrichment 
Average 
MTU / 
Assembly 
Average 
Assembly 
Age 
(years) 
Total MTU 
21 PWR 
Absorber 
Plate 
10.97 119480 5690 41.976 3.75 0.431 25.22 51529.19 
21 PWR 
Control 
Rod 
3.55 2207 106 19.862 3.61 0.376 34.74 829.07 
12 PWR 
Absorber 
Plate-Long 
8.32 3513 293 43.337 3.77 0.54 21.6 1897.56 
44 BWR 
Absorber 
Plate 
6.63 164165 3732 33.981 3.02 0.178 25.25 29140.39 
24 BWR Thick 
Absorber 
Plate 
0.59 2338 98 8.48 2.68 0.169 37.39 395.28 
Totals 291703 9919 83791.49 

NOTES: 

a Information in table based on summary.dat file for waste arrival Case C, 83,800 MTU. 

b Average WP Heat Generation Rate, kW: 9.07 
Average PWR WP Heat Generation Rate, kW: 10.71 
Average BWR WP Heat Generation Rate, kW: 6.48 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page30 of 35

7. ATTACHMENTS 

Hardcopy attachments to this calculation are summarized below in Table 16. In addition to the 
attachments listed in Table 16, Attachment III is comprised of three compact discs (CDs) that 
support this calculation. The file listings for the discs are presented in Tables 17 through 19. 

Table 16. List of Attachments 

Attachment 
Number 
Title / Description Number of 
Pages 
I Document Input Reference System Report 2 
II Spreadsheet Check of BIN.EXE Software 
Routinea 
28 

NOTES: 

a The electronic spreadsheet file is contained in Attachment III, disc 3 file 
routine_check.xls 

Table 17. Disc 1 File Listing 

File Name Date Transferred Time of Transfer File Size (bytes) 
Directory: BIN.EXE_FILES\OUTPUT_FILES\CASE_A_63K 
AnsysBin1.dat 12/09/99 12:06p 4,548 
AnsysBin2.dat 12/09/99 12:06p 4,548 
AnsysBin3.dat 12/09/99 12:06p 4,548 
AnsysBin4.dat 12/09/99 12:06p 4,548 
AnsysBin5.dat 12/09/99 12:06p 4,548 
average_nuclides.dat 12/09/99 12:06p 31,125 
bin.dat 12/09/99 12:06p 3,555,474 
gamma.dat 12/09/99 12:05p 26,697,850 
neutron.dat 12/09/99 11:56a 11,154,032 
nuclide.dat 12/09/99 11:53a 15,461,236 
nuclide_10000_years.dat 12/09/99 11:43a 15,461,236 
nuclide_100_years.dat 12/09/99 11:48a 15,461,236 
nuclide_1mil_years.dat 12/09/99 11:38a 15,501,870 
nuclide_20000_years.dat 12/09/99 11:33a 15,461,236 
nuclide_5000_years.dat 12/09/99 11:28a 15,461,236 
nuclide_mgr_end.dat 12/09/99 11:25a 15,461,236 
preblend.dat 12/09/99 11:20a 24,283,049 
summary.dat 12/09/99 11:12a 10,782 
thermal.dat 12/09/99 11:12a 10,546 
Directory: BIN.EXE_FILES\OUTPUT_FILES\CASE_A_84K 
AnsysBin1.dat 12/09/99 1:21p 4,548 
AnsysBin2.dat 12/09/99 1:21p 4,548 
AnsysBin3.dat 12/09/99 1:21p 4,548 
AnsysBin4.dat 12/09/99 1:21p 4,548 
AnsysBin5.dat 12/09/99 1:21p 4,548 
average_nuclides.dat 12/09/99 1:21p 31,125 
bin.dat 12/09/99 1:21p 4,582,024 
gamma.dat 12/09/99 1:20p 34,405,774 
neutron.dat 12/09/99 1:12p 14,374,466 
nuclide.dat 12/09/99 1:08p 19,925,262 
nuclide_10000_years.dat 12/09/99 12:55p 19,925,262 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page31 of 35

File Name Date Transferred Time of Transfer File Size (bytes) 
nuclide_100_years.dat 12/09/99 1:02p 19,925,262 
nuclide_1mil_years.dat 12/09/99 12:48p 19,977,628 
nuclide_20000_years.dat 12/09/99 12:42p 19,925,262 
nuclide_5000_years.dat 12/09/99 12:35p 19,925,262 
nuclide_mgr_end.dat 12/09/99 12:29p 19,925,262 
preblend.dat 12/09/99 12:22p 32,087,439 
summary.dat 12/09/99 12:11p 13,512 
thermal.dat 12/09/99 12:11p 10,546 
Directory: BIN.EXE_FILES\OUTPUT_FILES\CASE_B_63K 
AnsysBin1.dat 12/09/99 2:35p 4,548 
AnsysBin2.dat 12/09/99 2:35p 4,548 
AnsysBin3.dat 12/09/99 2:35p 4,548 
AnsysBin4.dat 12/09/99 2:35p 4,548 
AnsysBin5.dat 12/09/99 2:35p 4,548 
average_nuclides.dat 12/09/99 2:35p 31,125 
bin.dat 12/09/99 2:35p 3,823,749 
gamma.dat 12/09/99 2:34p 28,712,212 
neutron.dat 12/09/99 2:27p 11,995,649 
nuclide.dat 12/09/99 2:23p 16,627,849 
nuclide_10000_years.dat 12/09/99 2:16p 16,627,849 
nuclide_100_years.dat 12/09/99 2:20p 16,627,849 
nuclide_1mil_years.dat 12/09/99 2:10p 16,671,549 
nuclide_20000_years.dat 12/09/99 2:05p 16,627,849 
nuclide_5000_years.dat 12/09/99 2:01p 16,627,849 
nuclide_mgr_end.dat 12/09/99 1:55p 16,627,849 
preblend.dat 12/09/99 1:50p 24,308,129 
summary.dat 12/09/99 1:41p 10,782 
thermal.dat 12/09/99 1:41p 10,546 

Table 18. Disc 2 File Listing 

File Name Date Transferred Time of Transfer File Size (bytes) 
Directory: BIN.EXE_FILES\OUTPUT_FILES\CASE_B_84K 
AnsysBin1.dat 12/09/99 4:11p 4,548 
AnsysBin2.dat 12/09/99 4:11p 4,548 
AnsysBin3.dat 12/09/99 4:11p 4,548 
AnsysBin4.dat 12/09/99 4:11p 4,548 
AnsysBin5.dat 12/09/99 4:11p 4,548 
average_nuclides.dat 12/09/99 4:11p 31,125 
bin.dat 12/09/99 4:11p 4,807,949 
gamma.dat 12/09/99 4:09p 36,102,148 
neutron.dat 12/09/99 3:57p 15,083,225 
nuclide.dat 12/09/99 3:53p 20,907,713 
nuclide_10000_years.dat 12/09/99 3:39p 20,907,713 
nuclide_100_years.dat 12/09/99 3:46p 20,907,713 
nuclide_1mil_years.dat 12/09/99 3:32p 20,962,661 
nuclide_20000_years.dat 12/09/99 3:25p 20,907,713 
nuclide_5000_years.dat 12/09/99 3:05p 20,907,713 
nuclide_mgr_end.dat 12/09/99 2:59p 20,907,713 
preblend.dat 12/09/99 2:52p 32,087,439 
summary.dat 12/09/99 2:44p 13,512 
thermal.dat 12/09/99 2:44p 10,546 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page32 of 35

File Name Date Transferred Time of Transfer File Size (bytes) 
Directory: BIN.EXE_FILES\OUTPUT_FILES\CASE_C_63K 
AnsysBin1.dat 12/09/99 5:06p 4,548 
AnsysBin2.dat 12/09/99 5:06p 4,548 
AnsysBin3.dat 12/09/99 5:06p 4,548 
AnsysBin4.dat 12/09/99 5:06p 4,548 
AnsysBin5.dat 12/09/99 5:06p 4,548 
average_nuclides.dat 12/09/99 5:06p 31,125 
bin.dat 12/09/99 2:42p 3,594,149 
gamma.dat 12/09/99 5:06p 26,988,244 
neutron.dat 12/09/99 4:57p 11,275,361 
nuclide.dat 12/09/99 4:53p 15,629,417 
nuclide_10000_years.dat 12/09/99 4:43p 15,629,417 
nuclide_100_years.dat 12/09/99 4:48p 15,629,417 
nuclide_1mil_years.dat 12/09/99 4:39p 15,670,493 
nuclide_20000_years.dat 12/09/99 4:34p 15,629,417 
nuclide_5000_years.dat 12/09/99 4:29p 15,629,417 
nuclide_mgr_end.dat 12/09/99 4:25p 15,629,417 
preblend.dat 12/09/99 4:20p 24,220,569 
summary.dat 12/09/99 4:13p 10,782 
thermal.dat 12/09/99 4:13p 10,546 
Directory: BIN.EXE_FILES\OUTPUT_FILES\CASE_C_84K 
AnsysBin1.dat 12/09/99 7:18p 4,548 
AnsysBin2.dat 12/09/99 7:18p 4,548 
AnsysBin3.dat 12/09/99 7:18p 4,548 
AnsysBin4.dat 12/09/99 7:18p 4,548 
AnsysBin5.dat 12/09/99 7:18p 4,548 
average_nuclides.dat 12/09/99 7:18p 31,125 
bin.dat 12/09/99 7:18p 4,595,149 
gamma.dat 12/09/99 7:16p 34,504,324 
neutron.dat 12/09/99 7:08p 14,415,641 
nuclide.dat 12/09/99 7:04p 19,982,337 
nuclide_10000_years.dat 12/09/99 6:51p 19,982,337 
nuclide_100_years.dat 12/09/99 6:57p 19,982,337 
nuclide_1mil_years.dat 12/09/99 6:44p 20,034,853 
nuclide_20000_years.dat 12/09/99 6:37p 19,982,337 
nuclide_5000_years.dat 12/09/99 6:31p 19,982,337 
nuclide_mgr_end.dat 12/09/99 6:24p 19,982,337 
preblend.dat 12/09/99 6:17p 32,087,439 
summary.dat 12/09/99 6:07p 13,512 
thermal.dat 12/09/99 6:07p 10,546 

Table 19. Disc 3 File Listing 

File Name Date Transferred Time of Transfer File Size (bytes) 
Directory: SURFACESORT.EXE_FILES\OUTPUT_FILES\CASE_A_63K 
DPC.dat 12/15/99 2:23p 2,797,099 
rail.dat 12/15/99 2:24p 5,435,464 
truck.dat 12/15/99 2:24p 239,924 
Directory: SURFACESORT.EXE_FILES \OUTPUT_FILES\CASE_A_84K 
DPC.dat 12/15/99 2:20p 5,121,886 
rail.dat 12/15/99 2:22p 5,772,904 
truck.dat 12/15/99 2:22p 239,924 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page33 of 35

File Name Date Transferred Time of Transfer File Size (bytes) 
Directory: SURFACESORT.EXE_FILES \OUTPUT_FILES\CASE_B_63K 
DPC.dat 12/15/99 2:16p 2,793,705 
rail.dat 12/15/99 2:18p 5,490,224 
truck.dat 12/15/99 2:18p 260,750 
Directory: SURFACESORT.EXE_FILES \OUTPUT_FILES\CASE_B_84K 
DPC.dat 12/15/99 2:14p 5,108,272 
rail.dat 12/15/99 2:15p 5,828,206 
truck.dat 12/15/99 2:16p 260,750 
Directory: SURFACESORT.EXE_FILES \OUTPUT_FILES\CASE_C_63K 
DPC.dat 12/15/99 2:11p 2,801,742 
rail.dat 12/15/99 2:12p 5,416,536 
truck.dat 12/15/99 2:12p 236,689 
Directory: SURFACESORT.EXE_FILES \OUTPUT_FILES\CASE_C_84K 
DPC.dat 12/15/99 2:08p 5,146,996 
rail.dat 12/15/99 2:10p 5,753,697 
truck.dat 12/15/99 2:10p 236,689 
Directory: SURFACESORT.EXE_FILES \SOURCE_CODE 
Numberconverter.h 12/15/99 2:05p 432 
SurfaceSort.c 12/15/99 2:05p 9,321 
Directory: BIN.EXE_FILES \SOURCE_CODE 
bin.c 12/09/99 11:11a 142,765 
bracketValue.h 12/09/99 11:11a 1,159 
interpolate.h 12/09/99 11:11a 922 
Numberconverter.h 12/09/99 11:11a 432 
Directory: BIN.EXE_FILES \INPUT_FILES 
binInfo.source 01/26/00 3:54p 577 
BWR.cobalt.source 01/26/00 3:54p 1,179,265 
BWR.gamma.source 01/26/00 3:54p 33,331,668 
BWR.neutron.source 01/26/00 3:44p 28,009,428 
BWR.nuclide.source 01/26/00 3:36p 14,794,537 
BWR.thermal.source 01/26/00 3:31p 1,654,333 
BWRSS.cobalt.source 01/26/00 3:30p 89,328 
BWRSS.gamma.source 01/26/00 3:30p 2,523,280 
BWRSS.neutron.source 01/26/00 3:30p 2,120,080 
BWRSS.nuclide.source 01/26/00 3:29p 1,120,788 
BWRSS.thermal.source 01/26/00 3:29p 125,318 
PWR.cobalt.source 01/26/00 3:29p 1,179,289 
PWR.gamma.source 01/26/00 3:28p 33,335,988 
PWR.neutron.source 01/26/00 3:18p 28,013,748 
PWR.nuclide.source 01/21/00 4:43p 14,794,561 
PWR.thermal.source 01/21/00 4:39p 1,654,357 
PWRSS.cobalt.source 01/21/00 4:38p 446,640 
PWRSS.gamma.source 01/21/00 4:38p 12,616,400 
PWRSS.neutron.source 01/21/00 4:34p 10,600,400 
PWRSS.nuclide.source 01/21/00 4:31p 5,603,940 
PWRSS.thermal.source 01/21/00 4:29p 626,590 
timeSteps.source 01/26/00 3:19p 879 
Directory: BIN.EXE_FILES \INPUT_FILES\CONDITIONED_WASTESTREAM_FILES 
Case_A_63 01/26/00 5:01p 3,047,550 
Case_A_84 01/26/00 5:00p 3,927,450 
Case_B_63 01/26/00 4:59p 3,277,500 
Case_B_84 01/26/00 4:58p 4,121,100 
Case_C_63 01/26/00 4:57p 3,080,700 
Case_C_84 01/26/00 4:56p 3,938,700 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page34 of 35

File Name Date Transferred Time of Transfer File Size (bytes) 
Directory: SPREADSHEET_FILES 
Case_A63_Characteristics.xls 02/07/00 4:02p 7,847,424 
Case_A84_Characteristics.xls 02/07/00 4:07p 10,109,440 
Case_B63_Characteristics.xls 02/07/00 4:06p 8,197,632 
Case_B84_Characteristics.xls 02/07/00 3:34p 10,794,496 
Case_C63_Characteristics.xls 02/07/00 3:39p 7,662,080 
Case_C84_Characteristics.xls 02/07/00 3:59p 10,336,256 
routine_check.xls 02/14/00 5:12p 20,419,072 


asstttee PPaacckkaaggee OOppeerraatttiiioonnsCacuaon 

WaWase Package Operaons 
Caalllccuulllaatttiiioon

Title: Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Document Identifier: CAL-MGR-MD-000001 REV 00 Page35 of 35

8. REFERENCES 
CRWMS M&O (Civilian Radioactive Waste Management System Management & Operating 
Contractor) 1996. Software Qualification Report for the Spent Nuclear Fuel Decay Heat 
Function (SNFDHF). 20026-2003, Rev. 0. Las Vegas, Nevada: CRWMS M&O. ACC: 
MOV.19970212.0231. 

CRWMS M&O 1997. Waste Container Cavity Size Determination. BBAA00000-01717-020000026 
REV 00. Las Vegas, Nevada: CRWMS M&O. ACC: MOL.19980106.0061. 

CRWMS M&O 1999a. 1999 Design Basis Waste Input Report for Commercial Spent Nuclear 
Fuel. B00000000-01717-5700-00041 REV 00. Washington, D.C.: CRWMS M&O. ACC: 
MOV.19991006.0003. 

CRWMS M&O 1999b. BWR Source Term Generation and Evaluation. BBAC00000-017170210-
00006 REV 01. Las Vegas, NV: CRWMS M&O. ACC: MOL.20000113.0334. 

CRWMS M&O 1999c. PWR Source Term Generation and Evaluation. BBAC00000-017170210-
00010 REV 01. Las Vegas, NV: CRWMS. ACC: MOL.20000113.0333. 

CRWMS M&O 1999d. Transmittal of Site Recommendation Waste Streams. Input Transmittal 
WP-SEV-99233.Ta. Las Vegas, Nevada: CRWMS M&O. ACC: MOL.19990824.0138. 

CRWMS M&O 1999e. License Application Design Selection Feature Report: Aging and 
Blending. B00000000-01717-2200-00217 REV 00. Las Vegas, Nevada: CRWMS M&O. 
ACC: MOL.19990407.0039. 

YMP (Yucca Mountain Project) 1998. Disposal Criticality Analysis Methodology Topical 
Report. YMP/TR-004Q, Rev. 0. Las Vegas, Nevada: Yucca Mountain Site Characterization 
Office. ACC: MOL.19990210.0236. 


OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT 
DOCUMENT INPUT REFERENCE SYSTEM 
1. Document Identifier No./Rev.: 
CAL-MGR-MD-000001 REV 00 
Change: 
N/A 
Title: 
Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
Input Document 
4. Input 
Status 
5. Section 
Used in 6. Input Description 
7. 
TBV/TBD 
Priority 
8. TBVDue To 
2a. 2. Technical Product Input Source Title and 
Identifier(s) with Version 
3. 
Section Unqual. 
From 
Uncontrolled 
Source 
Un-
Confirmed 
1 
CRWMS M&O 1997. Waste Container 
Cavity Size Determination. BBAA0000001717-
0200-00026 REV 00. Las Vegas, 
Nevada: CRWMS M&O. ACC: 
MOL.19980106.0061. 
7 N/A -Not 
Critical 
3,5 Waste package assembly basket 
requirements 
N/A N/A N/A N/A 
5 
YMP (Yucca Mountain Project) 1998. 
Disposal Criticality Analysis Methodology 
Topical Report. YMP/TR-004Q, Rev. 0. 
Las Vegas, Nevada: Yucca Mountain Site 
Characterization Office. ACC: 
MOL.19990210.0236. 
5 N/A Qualified/ 
Confirmed 
/Controlle 
d 
5 keffective loading curves for 
waste package designs 
N/A N/A N/A N/A 
6 
CRWMS M&O 1999. Transmittal of Site 
Recommendation Waste Streams. Input 
Transmittal WP-SEV-99233.Ta. Las 
Vegas, Nevada: CRWMS M&O. ACC: 
MOL.19990824.0138. 
Entire N/A Reference 
Only 
Entire Transmittal of detailed assembly 
characteristics and arrival years 
N/A N/A N/A N/A 
7 
CRWMS M&O 1999. License Application 
Design Selection Feature Report: Aging 
and Blending. B00000000-01717-220000217 
REV 00. Las Vegas, Nevada: 
CRWMS M&O. ACC: 
MOL.19990407.0039. 
3 N/A Reference 
Only 
5 General description of 
commercial waste package 
design types used for LADS 
Blending 
N/A N/A N/A N/A 
8 
CRWMS M&O 1996. Software 
Qualification Report for the Spent Nuclear 
Fuel Decay Heat Function (SNFDHF). 
20026-2003, Rev. 0. Las Vegas, Nevada: 
CRWMS M&O. ACC: 
MOV.19970212.0231. 
5.3.1 N/A Reference 
Only 
4.2.1 Validation of Power Log 
Equations 
N/A N/A N/A N/A 

CAL-MGR-MD-000001 REV 00 Attachment I Page I-1 of I- 2 


OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT 
DOCUMENT INPUT REFERENCE SYSTEM 
1. Document Identifier No./Rev.: 
CAL-MGR-MD-000001 REV 00 
Change: 
N/A 
Title: 
Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
Input Document 
4. Input 
Status 
5. Section 
Used in 6. Input Description 
7. 
TBV/TBD 
Priority 
8. TBVDue To 
2a. 2. Technical Product Input Source Title and 
Identifier(s) with Version 
3. 
Section Unqual. 
From 
Uncontrolled 
Source 
Un-
Confirmed 
9 
CRWMS M&O 1999. 1999 Design Basis 
Waste Input Report for Commercial Spent 
Nuclear Fuel. B00000000-01717-570000041 
REV 00. Washington, D.C.: 
CRWMS M&O. ACC: 
MOV.19991006.0003. 
Appendi 
x A 
N/A Reference 
Only 
5 Description of waste arrival 
cases 
N/A N/A N/A 
Appendi 
x C 
N/A Reference 
Only 
3 Canistered fuel characteristics N/A N/A N/A 
10 
CRWMS M&O 1999. BWR Source Term 
Generation and Evaluation. BBAC0000001717-
0210-00006 REV 01. Las Vegas, 
Nevada: CRWMS M&O. ACC: 
MOL.20000113.0334. 
5 N/A Reference 
Only 
3, 4, 5 Development of representative 
BWR assembly 
N/A N/A N/A 
Attachm 
ent VII 
TBV-4110 4, 5 BWR assembly thermal, cobalt, 
gamma, neutron, and nuclide 
source term files 
2 X N/A N/A 
3 TBV-4108 3 Assumption 3.1 which states that 
representative assembly in the 
calculation can approximate 
other various BWR types 
2 X N/A N/A 
11 
CRWMS M&O 1999. PWR Source Term 
Generation and Evaluation. BBAC0000001717-
0210-00010 REV 01. Las Vegas, 
Nevada: CRWMS M&O. ACC: 
MOL.20000113.0333. 
5 N/A Reference 
Only 
3,4,5 Development of Representative 
PWR Assembly 
N/A N/A N/A 
Attachm 
ent IV 
TBV-4111 4,5 PWR assembly thermal, cobalt, 
gamma, neutron, and nuclide 
source term files 
2 X N/A N/A 
3 TBV-4109 3 Assumption that representative 
assembly in the calculation can 
approximate other various PWR 
types 
2 X N/A N/A 

CAL-MGR-MD-000001 REV 00 Attachment I Page I-2 of I- 2 


Spreadsheet Check of BIN.EXE Software Routine 

Section 4.2.1 lists the following functions of BIN.EXE: 

FUNCTION 1. For each assembly in the design basis waste stream, BIN.EXE looks up and interpolates or extrapolates, if necessary, source term values 
from source term input files extracted from CRWMS M&O (1999b, 1999c). 

FUNCTION 2. Determine the WP design type that an assembly can be loaded into, based on coefficients for keffective criticality loading curves input into the 
software routine (see Section 5.1.1). Using a simple counter, the routine keeps track of the number of assemblies allocated to each WP design. 

FUNCTION 3. Create average assembly heat generation curves for each WP design type. These curves are based on normalizing the heat generation 
curves for each assembly to the time of arrival. This is calculated by using the following four steps: (1) determining which WP design a group of assemblies 
will be loaded into, (2) calculating assembly heat output by summing the contributions from 4 assembly regions, (3) summing the calculated heat output for 
all assemblies that will be loaded into a specific WP design at each time step, and (4) dividing the sums at each time step by the number of assemblies in 
that WP design to determine the average heat output at each time step. 

FUNCTION 4. Determine assembly averages for age, burnup, enrichment, and MTU for each WP design. Each of these items is determined by adding 
together the values for each assembly in a given WP design and then dividing by the number of assemblies. 

Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
CAL-MGR-MD-000001 REV 00 Attachment II Page II-1 of Page II-28 


Function Check 

The checks for Functions 1 and 2, as listed above, were performed for 8 assemblies based on specific assemblies selected from the Case A, 84k MTU, 
waste stream. These assemblies have low, middle and high initial enrichments for zircaloy clad assemblies. For the stainless steel assemblies, as there 
are a limited amount, the assemblies chosen represent the middle values for initial enrichment. The assemblies chosen for this check are shown in 
Table II-1. 

Table II-1. Assemblies for Check of Functions 1 and 2 

Assembly 
Number Type Cladding Type 
Initial 
Enrichment (% 
U-235) Initial MTU 
Burnup 
(GWd/MTU) 
Age (time 
since reactor 
discharge) at 
Repository 
Arrival (years) 
CALVIN 
Batch ID 
Number 
Cask Load 
Number Reactor Name 
1 BWR Zircaloy 0.70 0.185 4.000 42 4393 6894 LASALLE 2 
2 BWR Zircaloy 3.00 0.173 27.000 21 6668 1634 QUAD CITIES 1 
3 BWR Zircaloy 4.28 0.173 57.000 10 16362 9521 LIMERICK 2 
4 PWR Zircaloy 0.71 0.374 39.149 44 3740 6861 GINNA 
5 PWR Zircaloy 3.75 0.456 37.399 35 7315 7151 CATAWBA 
2 6 PWR Zircaloy 5.00 0.460 60.000 26 13242 10226 SEABROOK 1 
7 BWR Stainless Steel 3.71 0.110 5.000 23 4540 30 LACROSSE 
8 PWR Stainless Steel 4.00 0.411 26.000 25 5195 937 HADDAM NECK 

For each assembly there are over 100 source terms that are looked up and interpolated or extrapolated. Assembly 1 requires an extrapolation for the 
enrichment plane, while all calculations for Assemblies 2 through 8 will be interpolations. For this check, selective points were chosen to check the 20 input 
source term files. These files are grouped into five areas: nuclides, heat generation, gamma, neutron, and cobalt-60. To ensure that each source file is 
read into the software routine correctly, assemblies with low, average, and high enrichments are evaluated. This checks that source terms, which are 
grouped in various burnup/enrichment combinations, are being properly read into the BIN.EXE routine. It should be noted that Section 4.2 explains the 
eight points, seven interpolations or extrapolations, and MTU ratio necessary to achieve the final source term value. The eight points represent: 

Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
CAL-MGR-MD-000001 REV 00 Attachment II Page II-2 of Page II-28 


Point 1: pre-time, pre-enrichment, pre-burnup 
Point 2: pre-time, pre-enrichment, post-burnup 
Point 3: pre-time, post-enrichment, pre-burnup 
Point 4: pre-time, post-enrichment, post-burnup 
Point 5: post-time, pre-enrichment, pre-burnup 
Point 6: post-time, pre-enrichment, post-burnup 
Point 7: post-time, post-enrichment, pre-burnup 
Point 8: post-time, post-enrichment, post-burnup 

Interpolations are performed between Points 1 and 2, then Points 3 and 4, then Points 5 and 6, and then Points 7 and 8. The resulting values can be 
considered a, b, c, and d, respectively. The second set of interpolations are interpolating between values a and b, then values c and d. The resulting 
values can be considered ab and cd, respectively. The final interpolation is between ab and cd, which results in the value at the MTU of the assembly used 
to generate the source terms. This value must then be adjusted, by simple MTU ratio, to achieve the final value for the assembly from the waste stream 
(see Assumptions 3.1 and 3.2). 

Check of Function 1 

Table II-2. Pre- and Post-Values 

Assembly 
Number Pre-Time Post-Time 
Pre-
Enrichment 
Post-
Enrichment Pre-Burnup Post-Burnup 
1 42 42 0.711 1.000 1.00 10.00 
2 21 21 3.000 3.000 20.00 30.00 
3 10 10 4.000 4.500 50.00 60.00 
4 44 44 0.711 1.000 30.00 40.00 
5 35 35 3.500 4.000 30.00 40.00 
6 26 26 5.000 5.000 60.00 60.00 
7 23 23 3.500 4.000 1.00 10.00 
8 25 25 4.000 4.000 20.00 30.00 

The pre-and post-values in Table II-2 represent actual burnup, enrichments and times that directly correlate with values presented in the source term files. 
The pre-and post-times reflect the age of the assemblies at the time of repository arrival. As the source term files contain the exact age of interest for 
times less than 100 years, it is not necessary to interpolate for time. The pre-and post-values in the table above are used to extract the source term values 
for Tables II-3, II-5, II-7, II-9 through II-14, II-22 through II-25, II-30, II-32 through II-35, and II-41. 

Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
CAL-MGR-MD-000001 REV 00 Attachment II Page II-3 of Page II-28 


Nuclide Check for Function 1 

Table II-3. Values for Ac-227 at the Eight Points (curies) 

Assembly 
Number 
Ac-227 
Value at 
Point 1 
Ac-227 Value at 
Point 2 
Ac-227 Value at 
Point 3 
Ac-227 Value at 
Point 4 
Ac-227 Value at 
Point 5 
Ac-227 Value at 
Point 6 
Ac-227 Value 
at Point 7 
Ac-227 Value 
at Point 8 Source File 
1 0 0 0 0 0 0 0 0 BWR.nuclide.source 
2 0 0 0 0 0 0 0 0 BWR.nuclide.source 
3 0 0 0 0 0 0 0 0 BWR.nuclide.source 
4 0 0 0 0 0 0 0 0 PWR.nuclide.source 
5 1.28E-05 1.51E-05 1.53E-05 1.82E-05 1.28E-05 1.51E-05 1.53E-05 1.82E-05 PWR.nuclide.source 
6 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.55E-05 PWR.nuclide.source 
7 0 0 0 0 0 0 0 0 BWRSS.nuclide.source 
8 0 1.19E-05 0 1.19E-05 0 1.19E-05 0 1.19E-05 PWRSS.nuclide.source 

Table II-4. Values for Ac-227 for the Seven Interpolations (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
Final Ac-227 
Value After 
MTU Ratio 
Ac-227 Value from 
BIN.EXEa 
1 0 0 0 0 0 0 0 0 0 
2 0 0 0 0 0 0 0 0 0 
3 0 0 0 0 0 0 0 0 0 
4 0 0 0 0 0 0 0 0 0 
5 1.45E-05 1.75E-05 1.45E-05 1.75E-05 1.60E-05 1.60E-05 1.60E-05 1.53E-05 1.53E-05 
6 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.55E-05 2.47E-05 2.47E-05 
7 0 0 0 0 0 0 0 0 0 
8 5.95E-06 5.95E-06 5.95E-06 5.95E-06 5.95E-06 5.95E-06 5.95E-06 5.15E-06 5.15E-06 

a The BIN.EXE values are extracted from the output file nuclide.dat for the Case A, 84k MTU waste stream. 

Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
CAL-MGR-MD-000001 REV 00 Attachment II Page II-4 of Page II-28 


Table II-5. Values for Ni-63 at the Eight Points (curies) 

Assembly 
Number 
Ni-63 Value 
at Point 1 
Ni-63 Value at 
Point 2 
Ni-63 Value at 
Point 3 
Ni-63 Value at 
Point 4 
Ni-63 Value at 
Point 5 
Ni-63 Value at 
Point 6 
Ni-63 Value at 
Point 7 
Ni-63 Value 
at Point 8 Source File 
1 3.87E+00 3.23E+01 3.05E+00 2.75E+01 3.87E+00 3.23E+01 3.05E+00 2.75E+01 BWR.nuclide.source 
2 3.01E+01 4.84E+01 3.01E+01 4.84E+01 3.01E+01 4.84E+01 3.01E+01 4.84E+01 BWR.nuclide.source 
3 7.75E+01 1.00E+02 6.89E+01 8.93E+01 7.75E+01 1.00E+02 6.89E+01 8.93E+01 BWR.nuclide.source 
4 3.16E+02 3.90E+02 2.90E+02 3.65E+02 3.16E+02 3.90E+02 2.90E+02 3.65E+02 PWR.nuclide.source 
5 1.53E+02 2.11E+02 1.37E+02 1.90E+02 1.53E+02 2.11E+02 1.37E+02 1.90E+02 PWR.nuclide.source 
6 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.71E+02 PWR.nuclide.source 
7 1.17E+01 1.16E+02 1.04E+01 1.04E+02 1.17E+01 1.16E+02 1.04E+01 1.04E+02 BWRSS.nuclide.source 
8 4.70E+02 7.19E+02 4.70E+02 7.19E+02 4.70E+02 7.19E+02 4.70E+02 7.19E+02 PWRSS.nuclide.source 

Table II-6. Values for Ni-63 for the Seven Interpolations (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd - Final Ni63 
Value 
Final Ni-63 
Value After 
MTU Ratio 
Ni-63 Value from 
BIN.EXEa 
1 1.39E+01 1.15E+01 1.39E+01 1.15E+01 1.40E+01 1.40E+01 1.40E+01 1.30E+01 1.30E+01 
2 4.28E+01 4.28E+01 4.28E+01 4.28E+01 4.28E+01 4.28E+01 4.28E+01 3.70E+01 3.70E+01 
3 9.31E+01 8.30E+01 9.31E+01 8.30E+01 8.72E+01 8.72E+01 8.72E+01 7.53E+01 7.53E+01 
4 3.84E+02 3.59E+02 3.84E+02 3.59E+02 3.84E+02 3.84E+02 3.84E+02 3.03E+02 3.03E+02 
5 1.96E+02 1.76E+02 1.96E+02 1.76E+02 1.85E+02 1.85E+02 1.85E+02 1.78E+02 1.78E+02 
6 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.71E+02 2.62E+02 2.62E+02 
7 5.82E+01 5.20E+01 5.82E+01 5.20E+01 5.54E+01 5.54E+01 5.54E+01 3.05E+01 3.05E+01 
8 6.19E+02 6.19E+02 6.19E+02 6.19E+02 6.19E+02 6.19E+02 6.19E+02 5.35E+02 5.35E+02 

a The BIN.EXE values are extracted from the output file nuclide.dat for the Case A, 84k MTU waste stream. 

Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
CAL-MGR-MD-000001 REV 00 Attachment II Page II-5 of Page II-28 


Table II-7. Values for Zr-93 at The Eight Points (curies) 

Assembly 
Number 
Zr-93 Value 
at Point 1 
Zr-93 Value at 
Point 2 
Zr-93 Value at 
Point 3 
Zr-93 Value at 
Point 4 
Zr-93 Value at 
Point 5 
Zr-93 Value at 
Point 6 
Zr-93 Value at 
Point 7 
Zr-93 Value 
at Point 8 Source File 
1 1.07E-02 9.01E-02 1.05E-02 9.09E-02 1.07E-02 9.01E-02 1.05E-02 9.09E-02 BWR.nuclide.source 
2 1.79E-01 2.59E-01 1.79E-01 2.59E-01 1.79E-01 2.59E-01 1.79E-01 2.59E-01 BWR.nuclide.source 
3 4.16E-01 4.88E-01 4.20E-01 4.93E-01 4.16E-01 4.88E-01 4.20E-01 4.93E-01 BWR.nuclide.source 
4 5.07E-01 6.47E-01 5.18E-01 6.61E-01 5.07E-01 6.47E-01 5.18E-01 6.61E-01 PWR.nuclide.source 
5 5.85E-01 7.51E-01 5.92E-01 7.63E-01 5.85E-01 7.51E-01 5.92E-01 7.63E-01 PWR.nuclide.source 
6 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.11E+00 PWR.nuclide.source 
7 8.37E-03 7.96E-02 8.42E-03 8.06E-02 8.37E-03 7.96E-02 8.42E-03 8.06E-02 BWRSS.nuclide.source 
8 3.69E-01 5.30E-01 3.69E-01 5.30E-01 3.69E-01 5.30E-01 3.69E-01 5.30E-01 PWRSS.nuclide.source 

Table II-8. Values for Zr-93 for the Seven Interpolations (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd - Final Zr93 
Value 
Final Zr-93 
Value After 
MTU Ratio 
Zr-93 Value from 
BIN.EXEa 
3.86E-02 3.85E-02 3.86E-02 3.85E-02 3.86E-02 3.86E-02 3.86E-02 3.57E-02 3.57E-02 
2.35E-01 2.35E-01 2.35E-01 2.35E-01 2.35E-01 2.35E-01 2.35E-01 2.04E-01 2.04E-01 
4.67E-01 4.71E-01 4.67E-01 4.71E-01 4.69E-01 4.69E-01 4.69E-01 4.05E-01 4.05E-01 
6.35E-01 6.49E-01 6.35E-01 6.49E-01 6.35E-01 6.35E-01 6.35E-01 5.01E-01 5.01E-01 
7.08E-01 7.19E-01 7.08E-01 7.19E-01 7.14E-01 7.14E-01 7.14E-01 6.85E-01 6.85E-01 
1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.11E+00 1.07E+00 1.07E+00 
4.04E-02 4.08E-02 4.04E-02 4.08E-02 4.06E-02 4.06E-02 4.06E-02 2.23E-02 2.23E-02 
4.66E-01 4.66E-01 4.66E-01 4.66E-01 4.66E-01 4.66E-01 4.66E-01 4.04E-01 4.04E-01 

a The BIN.EXE values are extracted from the output file nuclide.dat for the Case A, 84k MTU waste stream. 

Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
CAL-MGR-MD-000001 REV 00 Attachment II Page II-6 of Page II-28 


Heat Generation Rate Check for Function 1 

Table II-9. Values for Heat Generation Rates at the Eight Points - FUEL REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Heat 
Generation 
Rate Value 
at Point 1 
Heat Generation 
Rate Value at 
Point 2 
Heat Generation 
Rate Value at 
Point 3 
Heat Generation 
Rate Value at 
Point 4 
Heat 
Generation 
Rate Value at 
Point 5 
Heat 
Generation 
Rate Value at 
Point 6 
Heat 
Generation 
Rate Value at 
Point 7 
Heat 
Generation 
Rate Value at 
Point 8 Source File 
1 2.48E-03 1.89E-02 1.99E-03 1.65E-02 2.48E-03 1.89E-02 1.99E-03 1.65E-02 BWR.thermal.source 
2 2.33E-01 3.40E-01 2.33E-01 3.40E-01 2.33E-01 3.40E-01 2.33E-01 3.40E-01 BWR.thermal.source 
3 1.91E+00 2.26E+00 1.75E+00 2.08E+00 1.91E+00 2.26E+00 1.75E+00 2.08E+00 BWR.thermal.source 
4 4.45E-01 5.26E-01 4.16E-01 5.00E-01 4.45E-01 5.26E-01 4.16E-01 5.00E-01 PWR.thermal.source 
5 7.40E-01 9.65E-01 6.80E-01 8.89E-01 7.40E-01 9.65E-01 6.80E-01 8.89E-01 PWR.thermal.source 
6 3.61E+00 3.61E+00 3.61E+00 3.61E+00 3.61E+00 3.61E+00 3.61E+00 3.61E+00 PWR.thermal.source 
7 3.06E-01 2.71E+00 2.78E-01 2.49E+00 3.06E-01 2.71E+00 2.78E-01 2.49E+00 BWRSS.thermal.source 
8 6.81E+00 9.86E+00 6.81E+00 9.86E+00 6.81E+00 9.86E+00 6.81E+00 9.86E+00 PWRSS.thermal.source 

In the software routine, there are six separate heat generation rates that are looked up and interpolated between, then are added together for the final heat 
calculation. In this check, the numbers presented at each point are the sum of the six heat generation rates which will be used for the calculation in this 
check. 

Table II-10. Values for Heat Generation Rates at the Eight Points - FUEL REGION - ACTINIDES (watts) 

Assembly 
Number 
Heat 
Generation 
Rate Value 
at Point 1 
Heat Generation 
Rate Value at 
Point 2 
Heat Generation 
Rate Value at 
Point 3 
Heat Generation 
Rate Value at 
Point 4 
Heat 
Generation 
Rate Value at 
Point 5 
Heat 
Generation 
Rate Value at 
Point 6 
Heat 
Generation 
Rate Value at 
Point 7 
Heat 
Generation 
Rate Value at 
Point 8 Source File 
1 7.22E-01 1.42E+01 5.62E-01 1.26E+01 7.22E-01 1.42E+01 5.62E-01 1.26E+01 BWR.thermal.source 
2 1.73E+01 3.40E+01 1.73E+01 3.40E+01 1.73E+01 3.40E+01 1.73E+01 3.40E+01 BWR.thermal.source 
3 8.53E+01 1.38E+02 7.69E+01 1.23E+02 8.53E+01 1.38E+02 7.69E+01 1.23E+02 BWR.thermal.source 
4 1.35E+02 1.95E+02 1.30E+02 1.89E+02 1.35E+02 1.95E+02 1.30E+02 1.89E+02 PWR.thermal.source 
5 9.51E+01 1.50E+02 8.98E+01 1.43E+02 9.51E+01 1.50E+02 8.98E+01 1.43E+02 PWR.thermal.source 
6 2.85E+02 2.85E+02 2.85E+02 2.85E+02 2.85E+02 2.85E+02 2.85E+02 2.85E+02 PWR.thermal.source 
7 2.56E-01 5.96E+00 2.38E-01 5.39E+00 2.56E-01 5.96E+00 2.38E-01 5.39E+00 BWRSS.thermal.source 
8 4.85E+01 9.63E+01 4.85E+01 9.63E+01 4.85E+01 9.63E+01 4.85E+01 9.63E+01 PWRSS.thermal.source 

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Table II-11. Values for Heat Generation Rates at the Eight Points - FUEL REGION - FISSION PRODUCTS (watts) 

Assembly 
Number 
Heat 
Generation 
Rate Value 
at Point 1 
Heat Generation 
Rate Value at 
Point 2 
Heat Generation 
Rate Value at 
Point 3 
Heat Generation 
Rate Value at 
Point 4 
Heat 
Generation 
Rate Value at 
Point 5 
Heat 
Generation 
Rate Value at 
Point 6 
Heat 
Generation 
Rate Value at 
Point 7 
Heat 
Generation 
Rate Value at 
Point 8 Source File 
1 2.36E+00 2.10E+01 2.47E+00 2.21E+01 2.36E+00 2.10E+01 2.47E+00 2.21E+01 BWR.thermal.source 
2 7.98E+01 1.14E+02 7.98E+01 1.14E+02 7.98E+01 1.14E+02 7.98E+01 1.14E+02 BWR.thermal.source 
3 2.52E+02 2.90E+02 2.56E+02 2.95E+02 2.52E+02 2.90E+02 2.56E+02 2.95E+02 BWR.thermal.source 
4 1.30E+02 1.66E+02 1.35E+02 1.72E+02 1.30E+02 1.66E+02 1.35E+02 1.72E+02 PWR.thermal.source 
5 2.00E+02 2.55E+02 2.04E+02 2.60E+02 2.00E+02 2.55E+02 2.04E+02 2.60E+02 PWR.thermal.source 
6 4.69E+02 4.69E+02 4.69E+02 4.69E+02 4.69E+02 4.69E+02 4.69E+02 4.69E+02 PWR.thermal.source 
7 4.23E+00 4.00E+01 4.25E+00 4.04E+01 4.23E+00 4.00E+01 4.25E+00 4.04E+01 BWRSS.thermal.source 
8 1.78E+02 2.57E+02 1.78E+02 2.57E+02 1.78E+02 2.57E+02 1.78E+02 2.57E+02 PWRSS.thermal.source 

Table II-12. Values for Heat Generation Rates at the Eight Points - BOTTOM END-FITTING REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Heat 
Generation 
Rate Value 
at Point 1 
Heat Generation 
Rate Value at 
Point 2 
Heat Generation 
Rate Value at 
Point 3 
Heat Generation 
Rate Value at 
Point 4 
Heat 
Generation 
Rate Value at 
Point 5 
Heat 
Generation 
Rate Value at 
Point 6 
Heat 
Generation 
Rate Value at 
Point 7 
Heat 
Generation 
Rate Value at 
Point 8 Source File 
1 6.31E-04 5.58E-03 5.06E-04 4.86E-03 6.31E-04 5.58E-03 5.06E-04 4.86E-03 BWR.thermal.source 
2 6.55E-02 9.74E-02 6.55E-02 9.74E-02 6.55E-02 9.74E-02 6.55E-02 9.74E-02 BWR.thermal.source 
3 5.07E-01 5.97E-01 4.67E-01 5.51E-01 5.07E-01 5.97E-01 4.67E-01 5.51E-01 BWR.thermal.source 
4 5.49E-02 6.52E-02 5.12E-02 6.19E-02 5.49E-02 6.52E-02 5.12E-02 6.19E-02 PWR.thermal.source 
5 8.94E-02 1.17E-01 8.21E-02 1.08E-01 8.94E-02 1.17E-01 8.21E-02 1.08E-01 PWR.thermal.source 
6 4.37E-01 4.37E-01 4.37E-01 4.37E-01 4.37E-01 4.37E-01 4.37E-01 4.37E-01 PWR.thermal.source 
7 2.28E-03 2.26E-02 2.07E-03 2.07E-02 2.28E-03 2.26E-02 2.07E-03 2.07E-02 BWRSS.thermal.source 
8 2.04E-01 3.00E-01 2.04E-01 3.00E-01 2.04E-01 3.00E-01 2.04E-01 3.00E-01 PWRSS.thermal.source 

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CAL-MGR-MD-000001 REV 00 Attachment II Page II-8 of Page II-28 


Table II-13. Values for Heat Generation Rates at the Eight Points - PLENUM REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Heat 
Generation 
Rate Value 
at Point 1 
Heat Generation 
Rate Value at 
Point 2 
Heat Generation 
Rate Value at 
Point 3 
Heat Generation 
Rate Value at 
Point 4 
Heat 
Generation 
Rate Value at 
Point 5 
Heat 
Generation 
Rate Value at 
Point 6 
Heat 
Generation 
Rate Value at 
Point 7 
Heat 
Generation 
Rate Value at 
Point 8 Source File 
1 3.68E-03 2.77E-02 2.95E-03 2.40E-02 3.68E-03 2.77E-02 2.95E-03 2.40E-02 BWR.thermal.source 
2 3.43E-01 5.02E-01 3.43E-01 5.02E-01 3.43E-01 5.02E-01 3.43E-01 5.02E-01 BWR.thermal.source 
3 2.75E+00 3.27E+00 2.50E+00 2.99E+00 2.75E+00 3.27E+00 2.50E+00 2.99E+00 BWR.thermal.source 
4 2.79E-02 3.30E-02 2.61E-02 3.14E-02 2.79E-02 3.30E-02 2.61E-02 3.14E-02 PWR.thermal.source 
5 4.64E-02 6.05E-02 4.26E-02 5.57E-02 4.64E-02 6.05E-02 4.26E-02 5.57E-02 PWR.thermal.source 
6 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 PWR.thermal.source 
7 2.12E-02 1.90E-01 1.92E-02 1.74E-01 2.12E-02 1.90E-01 1.92E-02 1.74E-01 BWRSS.thermal.source 
8 2.52E-01 3.65E-01 2.52E-01 3.65E-01 2.52E-01 3.65E-01 2.52E-01 3.65E-01 PWRSS.thermal.source 

Table II-14. Values for Heat Generation Rates at the Eight Points - TOP END-FITTING REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Heat 
Generation 
Rate Value 
at Point 1 
Heat Generation 
Rate Value at 
Point 2 
Heat Generation 
Rate Value at 
Point 3 
Heat Generation 
Rate Value at 
Point 4 
Heat 
Generation 
Rate Value at 
Point 5 
Heat 
Generation 
Rate Value at 
Point 6 
Heat 
Generation 
Rate Value at 
Point 7 
Heat 
Generation 
Rate Value at 
Point 8 Source File 
1 7.82E-04 6.64E-03 6.27E-04 5.78E-03 7.82E-04 6.64E-03 6.27E-04 5.78E-03 BWR.thermal.source 
2 8.02E-02 1.19E-01 8.02E-02 1.19E-01 8.02E-02 1.19E-01 8.02E-02 1.19E-01 BWR.thermal.source 
3 6.22E-01 7.32E-01 5.73E-01 6.75E-01 6.22E-01 7.32E-01 5.73E-01 6.75E-01 BWR.thermal.source 
4 3.52E-02 4.18E-02 3.28E-02 3.97E-02 3.52E-02 4.18E-02 3.28E-02 3.97E-02 PWR.thermal.source 
5 5.75E-02 7.51E-02 5.28E-02 6.91E-02 5.75E-02 7.51E-02 5.28E-02 6.91E-02 PWR.thermal.source 
6 2.81E-01 2.81E-01 2.81E-01 2.81E-01 2.81E-01 2.81E-01 2.81E-01 2.81E-01 PWR.thermal.source 
7 2.90E-03 2.81E-02 2.63E-03 2.57E-02 2.90E-03 2.81E-02 2.63E-03 2.57E-02 BWRSS.thermal.source 
8 1.31E-01 1.93E-01 1.31E-01 1.93E-01 1.31E-01 1.93E-01 1.31E-01 1.93E-01 PWRSS.thermal.source 

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Table II-15. Heat Generation Rates for the Seven Interpolations - FUEL REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
1 8.42E-03 7.11E-03 8.42E-03 7.11E-03 8.49E-03 8.49E-03 8.49E-03 
2 3.08E-01 3.08E-01 3.08E-01 3.08E-01 3.08E-01 3.08E-01 3.08E-01 
3 2.16E+00 1.98E+00 2.16E+00 1.98E+00 2.05E+00 2.05E+00 2.05E+00 
4 5.19E-01 4.93E-01 5.19E-01 4.93E-01 5.20E-01 5.20E-01 5.20E-01 
5 9.07E-01 8.35E-01 9.07E-01 8.35E-01 8.69E-01 8.69E-01 8.69E-01 
6 3.61E+00 3.61E+00 3.61E+00 3.61E+00 3.61E+00 3.61E+00 3.61E+00 
7 1.41E+00 1.29E+00 1.41E+00 1.29E+00 1.35E+00 1.35E+00 1.35E+00 
8 8.65E+00 8.65E+00 8.65E+00 8.65E+00 8.65E+00 8.65E+00 8.65E+00 

Table II-16. Heat Generation Rates for the Seven Interpolations - FUEL REGION - ACTINIDES (watts) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
1 4.34E+00 3.66E+00 4.34E+00 3.66E+00 4.37E+00 4.37E+00 4.37E+00 
2 2.85E+01 2.85E+01 2.85E+01 2.85E+01 2.85E+01 2.85E+01 2.85E+01 
3 1.21E+02 1.08E+02 1.21E+02 1.08E+02 1.13E+02 1.13E+02 1.13E+02 
4 1.90E+02 1.84E+02 1.90E+02 1.84E+02 1.90E+02 1.90E+02 1.90E+02 
5 1.35E+02 1.28E+02 1.35E+02 1.28E+02 1.31E+02 1.31E+02 1.31E+02 
6 2.85E+02 2.85E+02 2.85E+02 2.85E+02 2.85E+02 2.85E+02 2.85E+02 
7 2.31E+00 2.11E+00 2.31E+00 2.11E+00 2.22E+00 2.22E+00 2.22E+00 
8 7.56E+01 7.56E+01 7.56E+01 7.56E+01 7.56E+01 7.56E+01 7.56E+01 

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CAL-MGR-MD-000001 REV 00 Attachment II Page II-10 of Page II-28 


Table II-17. Heat Generation Rates for the Seven Interpolations - FUEL REGION - FISSION PRODUCTS (watts) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
1 8.80E+00 9.24E+00 8.80E+00 9.24E+00 8.78E+00 8.78E+00 8.78E+00 
2 1.04E+02 1.04E+02 1.04E+02 1.04E+02 1.04E+02 1.04E+02 1.04E+02 
3 2.79E+02 2.83E+02 2.79E+02 2.83E+02 2.81E+02 2.81E+02 2.81E+02 
4 1.63E+02 1.69E+02 1.63E+02 1.69E+02 1.63E+02 1.63E+02 1.63E+02 
5 2.41E+02 2.46E+02 2.41E+02 2.46E+02 2.43E+02 2.43E+02 2.43E+02 
6 4.69E+02 4.69E+02 4.69E+02 4.69E+02 4.69E+02 4.69E+02 4.69E+02 
7 2.03E+01 2.05E+01 2.03E+01 2.05E+01 2.04E+01 2.04E+01 2.04E+01 
8 2.26E+02 2.26E+02 2.26E+02 2.26E+02 2.26E+02 2.26E+02 2.26E+02 

Table II-18. Heat Generation Rates for the Seven Interpolations - BOTTOM END-FITTING REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
1 2.34E-03 1.98E-03 2.34E-03 1.98E-03 2.36E-03 2.36E-03 2.36E-03 
2 8.79E-02 8.79E-02 8.79E-02 8.79E-02 8.79E-02 8.79E-02 8.79E-02 
3 5.70E-01 5.26E-01 5.70E-01 5.26E-01 5.44E-01 5.44E-01 5.44E-01 
4 6.44E-02 6.10E-02 6.44E-02 6.10E-02 6.44E-02 6.44E-02 6.44E-02 
5 1.10E-01 1.01E-01 1.10E-01 1.01E-01 1.05E-01 1.05E-01 1.05E-01 
6 4.37E-01 4.37E-01 4.37E-01 4.37E-01 4.37E-01 4.37E-01 4.37E-01 
7 1.13E-02 1.04E-02 1.13E-02 1.04E-02 1.09E-02 1.09E-02 1.09E-02 
8 2.62E-01 2.62E-01 2.62E-01 2.62E-01 2.62E-01 2.62E-01 2.62E-01 

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Table II-19. Heat Generation Rates for the Seven Interpolations - PLENUM REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
1 1.24E-02 1.04E-02 1.24E-02 1.04E-02 1.25E-02 1.25E-02 1.25E-02 
2 4.55E-01 4.55E-01 4.55E-01 4.55E-01 4.55E-01 4.55E-01 4.55E-01 
3 3.11E+00 2.84E+00 3.11E+00 2.84E+00 2.96E+00 2.96E+00 2.96E+00 
4 3.26E-02 3.10E-02 3.26E-02 3.10E-02 3.26E-02 3.26E-02 3.26E-02 
5 5.69E-02 5.23E-02 5.69E-02 5.23E-02 5.45E-02 5.45E-02 5.45E-02 
6 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 
7 9.82E-02 8.96E-02 9.82E-02 8.96E-02 9.43E-02 9.43E-02 9.43E-02 
8 3.20E-01 3.20E-01 3.20E-01 3.20E-01 3.20E-01 3.20E-01 3.20E-01 

Table II-20. Heat Generation Rates for the Seven Interpolations - TOP END-FITTING REGION - LIGHT ELEMENTS (watts) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
1 2.83E-03 2.39E-03 2.83E-03 2.39E-03 2.86E-03 2.86E-03 2.86E-03 
2 1.07E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 
3 6.99E-01 6.45E-01 6.99E-01 6.45E-01 6.67E-01 6.67E-01 6.67E-01 
4 4.13E-02 3.91E-02 4.13E-02 3.91E-02 4.13E-02 4.13E-02 4.13E-02 
5 7.06E-02 6.49E-02 7.06E-02 6.49E-02 6.76E-02 6.76E-02 6.76E-02 
6 2.81E-01 2.81E-01 2.81E-01 2.81E-01 2.81E-01 2.81E-01 2.81E-01 
7 1.42E-02 1.29E-02 1.42E-02 1.29E-02 1.36E-02 1.36E-02 1.36E-02 
8 1.68E-01 1.68E-01 1.68E-01 1.68E-01 1.68E-01 1.68E-01 1.68E-01 

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CAL-MGR-MD-000001 REV 00 Attachment II Page II-12 of Page II-28 


Table II-21. Heat Generation Rate Final Values (watts) 

Assembly 
Number 
Heat from 
Fuel Region 
Light 
Elements 
Heat from Fuel 
Region Actinides 
Heat from Fuel 
Region Fission 
Products 
Heat from Bottom 
End-Fitting 
Region Light 
Elements 
Heat from 
Plenum Region 
Light Elements 
Heat from Top 
End-Fitting 
Region Light 
Elements Total Heat 
Heat After 
MTU Ratio -
FINAL Heat 
Value BIN.EXE Heat Valuea 
1 0.01 4.37 8.78 0.00 0.01 0.00 13.18 12.19 12.19 
2 0.31 28.53 103.91 0.09 0.45 0.11 133.39 115.38 115.38 
3 2.05 113.03 281.45 0.54 2.96 0.67 400.70 346.16 346.16 
4 0.52 189.74 162.97 0.06 0.03 0.04 353.37 278.42 278.42 
5 0.87 131.40 243.37 0.11 0.05 0.07 375.87 360.72 360.72 
6 3.61 285.00 469.00 0.44 0.23 0.28 758.55 734.00 734.00 
7 1.35 2.22 20.41 0.01 0.09 0.01 24.10 13.26 13.26 
8 8.65 75.60 225.75 0.26 0.32 0.17 310.75 268.88 268.88 

a The BIN.EXE values are extracted from the output file bin.dat for the Case A, 84k MTU waste stream. 

Gamma Check for Function 1 

BIN.EXE calculates 18 energy bands for gamma radiation. For each energy band, the software routine interpolates values for four assembly regions and 
outputs values for each region. One mid-level energy band, 0.8 to 1.0 MeV, will be evaluated for each of the eight assemblies for each of the four assembly 
regions. 

Table II-22. Values for 0.8 to 1.0 MeV Energy Band at the Eight Points - FUEL REGION (photons/s) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
1 2.36E+10 2.46E+11 2.49E+10 2.56E+11 2.36E+10 2.46E+11 2.49E+10 2.56E+11 BWR.gamma.source 
2 1.70E+12 2.98E+12 1.70E+12 2.98E+12 1.70E+12 2.98E+12 1.70E+12 2.98E+12 BWR.gamma.source 
3 3.07E+13 3.92E+13 2.95E+13 3.80E+13 3.07E+13 3.92E+13 2.95E+13 3.80E+13 BWR.gamma.source 
4 1.91E+12 2.58E+12 1.97E+12 2.68E+12 1.91E+12 2.58E+12 1.97E+12 2.68E+12 PWR.gamma.source 
5 3.36E+12 4.74E+12 3.35E+12 4.76E+12 3.36E+12 4.74E+12 3.35E+12 4.76E+12 PWR.gamma.source 
6 1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.33E+13 PWR.gamma.source 
7 4.62E+10 6.05E+11 4.63E+10 5.99E+11 4.62E+10 6.05E+11 4.63E+10 5.99E+11 BWRSS.gamma.source 
8 3.40E+12 6.11E+12 3.40E+12 6.11E+12 3.40E+12 6.11E+12 3.40E+12 6.11E+12 PWRSS.gamma.source 

Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams 
CAL-MGR-MD-000001 REV 00 Attachment II Page II-13 of Page II-28 


Table II-23. Values for 0.8 to 1.0 MeV Energy Band at the Eight Points - BOTTOM REGION (photons/s) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
1 7.28E+06 1.16E+09 5.26E+06 1.05E+09 7.28E+06 1.16E+09 5.26E+06 1.05E+09 BWR.gamma.source 
2 1.22E+10 1.97E+10 1.22E+10 1.97E+10 1.22E+10 1.97E+10 1.22E+10 1.97E+10 BWR.gamma.source 
3 6.56E+10 6.49E+10 6.81E+10 6.81E+10 6.56E+10 6.49E+10 6.81E+10 6.81E+10 BWR.gamma.source 
4 1.96E+09 2.52E+09 1.86E+09 2.42E+09 1.96E+09 2.52E+09 1.86E+09 2.42E+09 PWR.gamma.source 
5 1.27E+09 1.74E+09 1.21E+09 1.65E+09 1.27E+09 1.74E+09 1.21E+09 1.65E+09 PWR.gamma.source 
6 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.43E+09 PWR.gamma.source 
7 6.89E+06 2.70E+09 6.06E+06 2.50E+09 6.89E+06 2.70E+09 6.06E+06 2.50E+09 BWRSS.gamma.source 
8 8.06E+08 1.24E+09 8.06E+08 1.24E+09 8.06E+08 1.24E+09 8.06E+08 1.24E+09 PWRSS.gamma.source 

Table II-24. Values for 0.8 to 1.0 MeV Energy Band at the Eight Points - PLENUM REGION (photons/s) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
3.00E+07 1.33E+09 2.42E+07 1.20E+09 3.00E+07 1.33E+09 2.42E+07 1.20E+09 BWR.gamma.source 
1.24E+10 2.01E+10 1.24E+10 2.01E+10 1.24E+10 2.01E+10 1.24E+10 2.01E+10 BWR.gamma.source 
6.61E+10 6.55E+10 6.84E+10 6.86E+10 6.61E+10 6.55E+10 6.84E+10 6.86E+10 BWR.gamma.source 
1.57E+09 2.01E+09 1.49E+09 1.93E+09 1.57E+09 2.01E+11 1.49E+09 1.93E+09 PWR.gamma.source 
1.01E+09 1.38E+09 9.60E+08 1.31E+09 1.01E+09 1.38E+09 9.60E+08 1.31E+09 PWR.gamma.source 
1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.92E+09 PWR.gamma.source 
4.66E+07 3.44E+09 4.30E+07 3.18E+09 4.66E+07 3.44E+09 4.30E+07 3.18E+09 BWRSS.gamma.source 
7.04E+08 1.08E+09 7.04E+08 1.08E+09 7.04E+08 1.08E+09 7.04E+08 1.08E+09 PWRSS.gamma.source 

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Table II-25. Values for 0.8 to 1.0 MeV Energy Band at the Eight Points - TOP REGION (photons/s) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
1 1.12E+07 1.19E+09 8.56E+06 1.08E+09 1.12E+07 1.19E+09 8.56E+06 1.08E+09 BWR.gamma.source 
2 1.22E+10 1.98E+10 1.22E+10 1.98E+10 1.22E+10 1.98E+10 1.22E+10 1.98E+10 BWR.gamma.source 
3 6.54E+10 6.47E+10 6.78E+10 6.78E+10 6.54E+10 6.47E+10 6.78E+10 6.78E+10 BWR.gamma.source 
4 1.36E+09 1.74E+09 1.29E+09 1.67E+09 1.36E+09 1.74E+09 1.29E+09 1.67E+09 PWR.gamma.source 
5 8.80E+08 1.20E+09 8.35E+08 1.14E+09 8.80E+08 1.20E+09 8.35E+08 1.14E+09 PWR.gamma.source 
6 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.68E+09 PWR.gamma.source 
7 8.65E+06 2.71E+09 7.70E+06 2.52E+09 8.65E+06 2.71E+09 7.70E+06 2.52E+09 BWRSS.gamma.source 
8 5.57E+08 8.59E+08 5.57E+08 8.59E+08 5.57E+08 8.59E+08 5.57E+08 8.59E+08 PWRSS.gamma.source 

Table II-26. Values for 0.8 to 1.0 MeV Energy Band for the Seven Interpolations - FUEL REGION (photons/s) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
9.68E+10 1.01E+11 9.68E+10 1.01E+11 9.66E+10 9.66E+10 9.66E+10 8.93E+10 8.93E+10 
2.58E+12 2.58E+12 2.58E+12 2.58E+12 2.58E+12 2.58E+12 2.58E+12 2.23E+12 2.23E+12 
3.66E+13 3.54E+13 3.66E+13 3.54E+13 3.59E+13 3.59E+13 3.59E+13 3.10E+13 3.10E+13 
2.52E+12 2.62E+12 2.52E+12 2.62E+12 2.52E+12 2.52E+12 2.52E+12 1.99E+12 1.99E+12 
4.37E+12 4.38E+12 4.37E+12 4.38E+12 4.38E+12 4.38E+12 4.38E+12 4.20E+12 4.20E+12 
1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.33E+13 1.29E+13 1.29E+13 
2.79E+11 2.77E+11 2.79E+11 2.77E+11 2.78E+11 2.78E+11 2.78E+11 1.53E+11 1.53E+11 
4.97E+12 4.97E+12 4.97E+12 4.97E+12 4.97E+12 4.97E+12 4.97E+12 4.30E+12 4.30E+12 

a The BIN.EXE values are extracted from the output file gamma.dat for the Case A, 84k MTU waste stream. 

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Table II-27. Values for 0.8 to 1.0 MeV Energy Band for the Seven Interpolations - BOTTOM REGION (photons/s) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
1 1.54E+08 1.28E+08 1.54E+08 1.28E+08 1.56E+08 1.56E+08 1.56E+08 1.44E+08 1.44E+08 
2 1.74E+10 1.74E+10 1.74E+10 1.74E+10 1.74E+10 1.74E+10 1.74E+10 1.50E+10 1.50E+10 
3 6.51E+10 6.81E+10 6.51E+10 6.81E+10 6.68E+10 6.68E+10 6.68E+10 5.77E+10 5.77E+10 
4 2.47E+09 2.37E+09 2.47E+09 2.37E+09 2.47E+09 2.47E+09 2.47E+09 1.95E+09 1.95E+09 
5 1.62E+09 1.53E+09 1.62E+09 1.53E+09 1.57E+09 1.57E+09 1.57E+09 1.51E+09 1.51E+09 
6 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.43E+09 2.35E+09 2.35E+09 
7 4.47E+08 4.08E+08 4.47E+08 4.08E+08 4.30E+08 4.30E+08 4.30E+08 2.36E+08 2.36E+08 
8 1.07E+09 1.07E+09 1.07E+09 1.07E+09 1.07E+09 1.07E+09 1.07E+09 9.22E+08 9.22E+08 

a The BIN.EXE values are extracted from the output file gamma.dat for the Case A, 84k MTU waste stream. 
Table II-28. Values for 0.8 to 1.0 MeV Energy Band for the Seven Interpolations - PLENUM REGION (photons/s) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
1 2.94E+08 2.54E+08 2.94E+08 2.54E+08 2.96E+08 2.96E+08 2.96E+08 2.74E+08 2.74E+08 
2 1.77E+10 1.77E+10 1.77E+10 1.77E+10 1.77E+10 1.77E+10 1.77E+10 1.53E+10 1.53E+10 
3 6.57E+10 6.85E+10 6.57E+10 6.85E+10 6.73E+10 6.73E+10 6.73E+10 5.81E+10 5.81E+10 
4 1.97E+09 1.89E+09 1.97E+09 1.89E+09 1.97E+09 1.97E+09 1.97E+09 1.55E+09 1.55E+09 
5 1.28E+09 1.22E+09 1.28E+09 1.22E+09 1.25E+09 1.25E+09 1.25E+09 1.20E+09 1.20E+09 
6 1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.92E+09 1.86E+09 1.86E+09 
7 9.42E+08 8.71E+08 9.42E+08 8.71E+08 9.10E+08 9.10E+08 9.10E+08 5.01E+08 5.01E+08 
8 9.29E+08 9.29E+08 9.29E+08 9.29E+08 9.29E+08 9.29E+08 9.29E+08 8.03E+08 8.03E+08 

a The BIN.EXE values are extracted from the output file gamma.dat for the Case A, 84k MTU waste stream. 

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Table II-29. Values for 0.8 to 1.0 MeV Energy Band for the Seven Interpolations - TOP REGION (photons/s) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
1 1.86E+08 1.58E+08 1.86E+08 1.58E+08 1.87E+08 1.87E+08 1.87E+08 1.73E+08 1.73E+08 
2 1.75E+10 1.75E+10 1.75E+10 1.75E+10 1.75E+10 1.75E+10 1.75E+10 1.51E+10 1.51E+10 
3 6.49E+10 6.78E+10 6.49E+10 6.78E+10 6.65E+10 6.65E+10 6.65E+10 5.75E+10 5.75E+10 
4 1.71E+09 1.64E+09 1.71E+09 1.64E+09 1.71E+09 1.71E+09 1.71E+09 1.35E+09 1.35E+09 
5 1.12E+09 1.06E+09 1.12E+09 1.06E+09 1.09E+09 1.09E+09 1.09E+09 1.04E+09 1.04E+09 
6 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.68E+09 1.63E+09 1.63E+09 
7 4.80E+08 4.41E+08 4.80E+08 4.41E+08 4.63E+08 4.63E+08 4.63E+08 2.55E+08 2.55E+08 
8 7.37E+08 7.37E+08 7.37E+08 7.37E+08 7.37E+08 7.37E+08 7.37E+08 6.38E+08 6.38E+08 

a The BIN.EXE values are extracted from the output file gamma.dat for the Case A, 84k MTU waste stream. 

Neutron Check for Function 1 

BIN.EXE calculates 27 energy bands for neutron radiation. One mid-level energy band, 0.1 to 0.4 MeV, will be evaluated for each of the eight assemblies. 
It should be noted that all values for energy bands below 0.1 are zero in the BIN.EXE output files. These zero values were checked by visual examination 
of the neutron source term files. 

Table II-30. Values for 0.1 to 0.4 MeV Energy Band at the Eight Points (neutrons/s) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
1 7.22E+02 4.27E+04 5.35E+02 2.89E+04 7.22E+02 4.27E+04 5.35E+02 2.89E+04 BWR.neutron.source 
2 1.00E+05 6.24E+05 1.00E+05 6.24E+05 1.00E+05 6.24E+05 1.00E+05 6.24E+05 BWR.neutron.source 
3 5.00E+06 1.09E+07 3.85E+06 8.64E+06 5.00E+06 1.09E+07 3.85E+06 8.64E+06 BWR.neutron.source 
4 4.80E+06 1.09E+07 3.87E+06 9.34E+06 4.80E+06 1.09E+07 3.87E+06 9.34E+06 PWR.neutron.source 
5 9.01E+05 3.07E+06 6.77E+05 2.36E+06 9.01E+05 3.07E+06 6.77E+05 2.36E+06 PWR.neutron.source 
6 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.16E+07 PWR.neutron.source 
7 2.06E+02 7.34E+03 1.90E+02 6.08E+03 2.06E+02 7.34E+03 1.90E+02 6.08E+03 BWRSS.neutron.source 
8 1.81E+05 1.10E+06 1.81E+05 1.10E+06 1.81E+05 1.10E+06 1.81E+05 1.10E+06 PWRSS.neutron.source 

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Table II-31. Values for 0.1 to 0.4 MeV Energy Band for the Seven Interpolations (neutrons/s) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
1 8.42E+03 5.91E+03 8.42E+03 5.91E+03 8.56E+03 8.56E+03 8.56E+03 7.92E+03 7.92E+03 
2 3.88E+05 3.88E+05 3.88E+05 3.88E+05 3.88E+05 3.88E+05 3.88E+05 3.35E+05 3.35E+05 
3 8.75E+06 6.88E+06 8.75E+06 6.88E+06 7.62E+06 7.62E+06 7.62E+06 6.59E+06 6.59E+06 
4 1.03E+07 8.74E+06 1.03E+07 8.74E+06 1.03E+07 1.03E+07 1.03E+07 8.08E+06 8.08E+06 
5 2.31E+06 1.76E+06 2.31E+06 1.76E+06 2.01E+06 2.01E+06 2.01E+06 1.93E+06 1.93E+06 
6 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.16E+07 1.12E+07 1.12E+07 
7 2.50E+03 2.14E+03 2.50E+03 2.14E+03 2.34E+03 2.34E+03 2.34E+03 1.29E+03 1.29E+03 
8 5.82E+05 5.82E+05 5.82E+05 5.82E+05 5.82E+05 5.82E+05 5.82E+05 5.03E+05 5.03E+05 

a The BIN.EXE values are extracted from the output file neutron.dat for the Case A, 84k MTU waste stream. 

Cobalt-60 Check for Function 1 

BIN.EXE calculates the cobalt-60 activity for four assembly regions.
Table II-32. Cobalt-60 Values at the Eight Points - FUEL REGION (curies)

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
1 1.48E-01 1.07E+00 1.19E-01 9.30E-01 1.48E-01 1.07E+00 1.19E-01 9.30E-01 BWR.cobalt.source 
2 1.41E+01 2.05E+01 1.41E+01 2.05E+01 1.41E+01 2.05E+01 1.41E+01 2.05E+01 BWR.cobalt.source 
3 1.14E+02 1.37E+02 1.04E+02 1.25E+02 1.14E+02 1.37E+02 1.04E+02 1.25E+02 BWR.cobalt.source 
4 2.68E+01 3.15E+01 2.50E+01 3.00E+01 2.68E+01 3.15E+01 2.50E+01 3.00E+01 PWR.cobalt.source 
5 4.68E+01 6.10E+01 4.30E+01 5.62E+01 4.68E+01 6.10E+01 4.30E+01 5.62E+01 PWR.cobalt.source 
6 2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.31E+02 PWR.cobalt.source 
7 1.98E+01 1.75E+02 1.79E+01 1.60E+02 1.98E+01 1.75E+02 1.79E+01 1.60E+02 BWRSS.cobalt.source 
8 4.38E+02 6.34E+02 4.38E+02 6.34E+02 4.38E+02 6.34E+02 4.38E+02 6.34E+02 PWRSS.cobalt.source 

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Table II-33. Cobalt-60 Values at the Eight Points -BOTTOM REGION (curies) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
1 3.71E-02 2.70E-01 2.98E-02 2.34E-01 3.71E-02 2.70E-01 2.98E-02 2.34E-01 BWR.cobalt.source 
2 3.55E+00 5.19E+00 3.55E+00 5.19E+00 3.55E+00 5.19E+00 3.55E+00 5.19E+00 BWR.cobalt.source 
3 2.91E+01 3.50E+01 2.64E+01 3.18E+01 2.91E+01 3.50E+01 2.64E+01 3.18E+01 BWR.cobalt.source 
4 3.23E+00 3.82E+00 3.02E+00 3.63E+00 3.23E+00 3.82E+00 3.02E+00 3.63E+00 PWR.cobalt.source 
5 5.63E+00 7.35E+00 5.17E+00 6.77E+00 5.63E+00 7.35E+00 5.17E+00 6.77E+00 PWR.cobalt.source 
6 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.80E+01 PWR.cobalt.source 
7 1.46E-01 1.30E+00 1.33E-01 1.19E+00 1.46E-01 1.30E+00 1.33E-01 1.19E+00 BWRSS.cobalt.source 
8 1.31E+01 1.93E+01 1.31E+01 1.93E+01 1.31E+01 1.93E+01 1.31E+01 1.93E+01 PWRSS.cobalt.source 

Table II-34. Cobalt-60 Values at the Eight Points -PLENUM REGION (curies) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
2.26E-01 1.64E+00 1.82E-01 1.42E+00 2.26E-01 1.64E+00 1.82E-01 1.42E+00 BWR.cobalt.source 
2.15E+01 3.13E+01 2.15E+01 3.13E+01 2.15E+01 3.13E+01 2.15E+01 3.13E+01 BWR.cobalt.source 
1.74E+02 2.08E+02 1.58E+02 1.90E+02 1.74E+02 2.08E+02 1.58E+02 1.90E+02 BWR.cobalt.source 
1.68E+00 1.98E+00 1.57E+00 1.88E+00 1.68E+00 1.98E+00 1.57E+00 1.88E+00 PWR.cobalt.source 
2.94E+00 3.83E+00 2.70E+00 3.52E+00 2.94E+00 3.83E+00 2.70E+00 3.52E+00 PWR.cobalt.source 
1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.45E+01 PWR.cobalt.source 
1.37E+00 1.21E+01 1.24E+00 1.11E+01 1.37E+00 1.21E+01 1.24E+00 1.11E+01 BWRSS.cobalt.source 
1.63E+01 2.35E+01 1.63E+01 2.35E+01 1.63E+01 2.35E+01 1.63E+01 2.35E+01 PWRSS.cobalt.source 

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Table II-35. Cobalt-60 Values at the Eight Points -TOP REGION (curies) 

Assembly 
Number 
Value at 
Point 1 Value at Point 2 Value at Point 3 Value at Point 4 Value at Point 5 Value at Point 6 
Value at Point 
7 
Value at 
Point 8 Source File 
1 4.74E-02 3.43E-01 3.81E-02 2.97E-01 4.74E-02 3.43E-01 3.81E-02 2.97E-01 BWR.cobalt.source 
2 4.51E+00 6.57E+00 4.51E+00 6.57E+00 4.51E+00 6.57E+00 4.51E+00 6.57E+00 BWR.cobalt.source 
3 3.67E+01 4.38E+01 3.33E+01 4.00E+01 3.67E+01 4.38E+01 3.33E+01 4.00E+01 BWR.cobalt.source 
4 2.08E+00 2.46E+00 1.94E+00 2.33E+00 2.08E+00 2.46E+00 1.94E+00 2.33E+00 PWR.cobalt.source 
5 3.62E+00 4.73E+00 3.33E+00 4.35E+00 3.62E+00 4.73E+00 3.33E+00 4.35E+00 PWR.cobalt.source 
6 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.80E+01 PWR.cobalt.source 
7 1.87E-01 1.66E+00 1.70E-01 1.52E+00 1.87E-01 1.66E+00 1.70E-01 1.52E+00 BWRSS.cobalt.source 
8 8.46E+00 1.24E+01 8.46E+00 1.24E+01 8.46E+00 1.24E+01 8.46E+00 1.24E+01 PWRSS.cobalt.source 

Table II-36. Cobalt-60 Values for the Seven Interpolations - FUEL REGION (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
4.87E-01 4.10E-01 4.87E-01 4.10E-01 4.91E-01 4.91E-01 4.91E-01 4.54E-01 4.54E-01 
1.86E+01 1.86E+01 1.86E+01 1.86E+01 1.86E+01 1.86E+01 1.86E+01 1.61E+01 1.61E+01 
1.30E+02 1.19E+02 1.30E+02 1.19E+02 1.23E+02 1.23E+02 1.23E+02 1.07E+02 1.07E+02 
3.11E+01 2.96E+01 3.11E+01 2.96E+01 3.11E+01 3.11E+01 3.11E+01 2.45E+01 2.45E+01 
5.73E+01 5.28E+01 5.73E+01 5.28E+01 5.49E+01 5.49E+01 5.49E+01 5.27E+01 5.27E+01 
2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.31E+02 2.24E+02 2.24E+02 
9.08E+01 8.27E+01 9.08E+01 8.27E+01 8.72E+01 8.72E+01 8.72E+01 4.80E+01 4.80E+01 
5.56E+02 5.56E+02 5.56E+02 5.56E+02 5.56E+02 5.56E+02 5.56E+02 4.81E+02 4.81E+02 

a The BIN.EXE values are extracted from the output file cobalt.dat for the Case A, 84k MTU waste stream. 

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Table II-37. Cobalt-60 Values for the Seven Interpolations - BOTTOM REGION (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
1 1.23E-01 1.03E-01 1.23E-01 1.03E-01 1.24E-01 1.24E-01 1.24E-01 1.14E-01 1.14E-01 
2 4.70E+00 4.70E+00 4.70E+00 4.70E+00 4.70E+00 4.70E+00 4.70E+00 4.07E+00 4.07E+00 
3 3.32E+01 3.02E+01 3.32E+01 3.02E+01 3.14E+01 3.14E+01 3.14E+01 2.72E+01 2.72E+01 
4 3.77E+00 3.58E+00 3.77E+00 3.58E+00 3.77E+00 3.77E+00 3.77E+00 2.97E+00 2.97E+00 
5 6.91E+00 6.36E+00 6.91E+00 6.36E+00 6.62E+00 6.62E+00 6.62E+00 6.35E+00 6.35E+00 
6 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.80E+01 2.71E+01 2.71E+01 
7 6.73E-01 6.15E-01 6.73E-01 6.15E-01 6.47E-01 6.47E-01 6.47E-01 3.56E-01 3.56E-01 
8 1.68E+01 1.68E+01 1.68E+01 1.68E+01 1.68E+01 1.68E+01 1.68E+01 1.46E+01 1.46E+01 

a The BIN.EXE values are extracted from the output file cobalt.dat for the Case A, 84k MTU waste stream. 
Table II-38. Cobalt-60 Values for the Seven Interpolations - PLENUM REGION (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
1 7.45E-01 6.27E-01 7.45E-01 6.27E-01 7.51E-01 7.51E-01 7.51E-01 6.95E-01 6.95E-01 
2 2.84E+01 2.84E+01 2.84E+01 2.84E+01 2.84E+01 2.84E+01 2.84E+01 2.46E+01 2.46E+01 
3 1.98E+02 1.80E+02 1.98E+02 1.80E+02 1.88E+02 1.88E+02 1.88E+02 1.62E+02 1.62E+02 
4 1.96E+00 1.85E+00 1.96E+00 1.85E+00 1.96E+00 1.96E+00 1.96E+00 1.54E+00 1.54E+00 
5 3.60E+00 3.31E+00 3.60E+00 3.31E+00 3.45E+00 3.45E+00 3.45E+00 3.31E+00 3.31E+00 
6 1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.45E+01 1.40E+01 1.40E+01 
7 6.28E+00 5.74E+00 6.28E+00 5.74E+00 6.04E+00 6.04E+00 6.04E+00 3.32E+00 3.32E+00 
8 2.07E+01 2.07E+01 2.07E+01 2.07E+01 2.07E+01 2.07E+01 2.07E+01 1.79E+01 1.79E+01 

a The BIN.EXE values are extracted from the output file cobalt.dat for the Case A, 84k MTU waste stream. 

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Table II-39. Cobalt-60 Values for the Seven Interpolations - TOP REGION (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd 
After MTU 
Ratio - FINAL 
Value BIN.EXE Valuea 
1 1.56E-01 1.31E-01 1.56E-01 1.31E-01 1.57E-01 1.57E-01 1.57E-01 1.45E-01 1.45E-01 
2 5.96E+00 5.96E+00 5.96E+00 5.96E+00 5.96E+00 5.96E+00 5.96E+00 5.15E+00 5.15E+00 
3 4.17E+01 3.80E+01 4.17E+01 3.80E+01 3.95E+01 3.95E+01 3.95E+01 3.41E+01 3.41E+01 
4 2.43E+00 2.30E+00 2.43E+00 2.30E+00 2.43E+00 2.43E+00 2.43E+00 1.91E+00 1.91E+00 
5 4.44E+00 4.09E+00 4.44E+00 4.09E+00 4.26E+00 4.26E+00 4.26E+00 4.08E+00 4.08E+00 
6 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.80E+01 1.74E+01 1.74E+01 
7 8.60E-01 7.86E-01 8.60E-01 7.86E-01 8.27E-01 8.27E-01 8.27E-01 4.55E-01 4.55E-01 
8 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 9.37E+00 9.37E+00 

a The BIN.EXE values are extracted from the output file cobalt.dat for the Case A, 84k MTU waste stream. 

Time Plane Interpolation Check for Function 1 

In the above checks of Function 1, the pre-and post-times are the same and no interpolation is required in the time plane. Therefore, to check that the 
interpolation equations are working properly for all three planes (burnup, enrichment, and time), a nuclide calculation for Ac-227 will be checked at 10,000 
years after the end of waste receipt for the same 8 assemblies shown in Table II-1. 

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Table II-40. Pre- and Post-Values 

Assembly 
Number 
Discharge 
Year 
Age at 10,000 
Years After the 
End of Waste 
Receipt Pre-Time Post-Time 
Pre-
Enrichment 
Post-
Enrichment Pre-Burnup 
Post-
Burnup 
1 1987 10053 10000 15000 0.711 1.000 1.00 10.00 
2 1994 10046 10000 15000 3.000 3.000 20.00 30.00 
3 2027 10013 10000 15000 4.000 4.500 50.00 60.00 
4 1985 10055 10000 15000 0.711 1.000 30.00 40.00 
5 1995 10045 10000 15000 3.500 4.000 30.00 40.00 
6 2013 10027 10000 15000 5.000 5.000 60.00 60.00 
7 1987 10053 10000 15000 3.500 4.000 1.00 10.00 
8 1989 10051 10000 15000 4.000 4.000 20.00 30.00 

The pre-and post-values in Table II-40 represent burnup, enrichments, and times that directly correlate with values presented in the source term files and 
reflect the age of the assemblies at the time of repository arrival. The pre-and post-values are used to determine the source term values to extract for the 
check below. 

Table II-41. Values for Ac-227 at the Eight Points (curies) 

Assembly 
Number 
Ac-227 
Value at 
Point 1 
Ac-227 Value at 
Point 2 
Ac-227 Value at 
Point 3 
Ac-227 Value at 
Point 4 
Ac-227 Value at 
Point 5 
Ac-227 Value at 
Point 6 
Ac-227 Value 
at Point 7 
Ac-227 Value 
at Point 8 Source File 
1 5.31E-04 2.37E-04 7.60E-04 3.69E-04 7.65E-04 3.61E-04 1.09E-03 5.49E-04 BWR.nuclide.source 
2 1.11E-03 6.69E-04 1.11E-03 6.69E-04 1.61E-03 9.81E-04 1.61E-03 9.81E-04 BWR.nuclide.source 
3 4.65E-04 2.69E-04 6.50E-04 3.88E-04 6.87E-04 4.06E-04 9.51E-04 5.76E-04 BWR.nuclide.source 
4 2.33E-04 1.90E-04 3.17E-04 2.34E-04 4.15E-04 3.59E-04 5.33E-04 4.21E-04 PWR.nuclide.source 
5 2.42E-03 1.64E-03 3.10E-03 2.16E-03 3.55E-03 2.42E-03 4.51E-03 3.18E-03 PWR.nuclide.source 
6 1.73E-03 1.73E-03 1.73E-03 1.73E-03 2.56E-03 2.56E-03 2.56E-03 2.56E-03 PWR.nuclide.source 
7 2.80E-03 2.11E-03 3.21E-03 2.49E-03 4.00E-03 3.02E-03 4.58E-03 3.57E-03 BWRSS.nuclide.source 
8 4.42E-03 3.25E-03 4.42E-03 3.25E-03 6.40E-03 4.73E-03 6.40E-03 4.73E-03 PWRSS.nuclide.source 

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Table II-42. Values for Ac-227 for the Seven Interpolations (curies) 

Assembly 
Number 
Interpolation 
Between 
Points 1 and 
2 (a) 
Interpolation 
Between Points 3 
and 4 (b) 
Interpolation 
Between Points 
5 and 6 (c ) 
Interpolation 
Between Points 7 
and 8 (d) 
Interpolation 
Between Points 
a and b (ab) 
Interpolation 
Between Points 
c and d (cd) 
Interpolation 
Between 
Points ab and 
cd - Final Ac227 
Value 
Final Ac-227 
Value After 
MTU Ratio 
Ac-227 Value from 
BIN.EXEa 
1 3.27E-04 4.92E-04 4.87E-04 7.21E-04 3.21E-04 4.78E-04 3.22E-04 2.98E-04 2.98E-04 
2 7.63E-04 7.63E-04 1.12E-03 1.12E-03 7.63E-04 1.12E-03 7.66E-04 6.63E-04 6.63E-04 
3 3.14E-04 4.49E-04 4.71E-04 6.63E-04 3.85E-04 5.73E-04 3.86E-04 3.33E-04 3.33E-04 
4 1.93E-04 2.39E-04 3.63E-04 4.28E-04 1.93E-04 3.63E-04 1.94E-04 1.53E-04 1.53E-04 
5 1.80E-03 2.35E-03 2.65E-03 3.45E-03 2.06E-03 3.04E-03 2.07E-03 1.99E-03 1.99E-03 
6 1.73E-03 1.73E-03 2.56E-03 2.56E-03 1.73E-03 2.56E-03 1.73E-03 1.68E-03 1.68E-03 
7 2.30E-03 2.69E-03 3.29E-03 3.85E-03 2.46E-03 3.52E-03 2.47E-03 1.36E-03 1.36E-03 
8 3.62E-03 3.62E-03 5.26E-03 5.26E-03 3.62E-03 5.26E-03 3.64E-03 3.15E-03 3.15E-03 

a The BIN.EXE values are extracted from the output file nuclide_10000_years.dat for the Case A, 84k MTU waste stream. 

Check of Function 2 

Function 2 determines the waste package design that an assembly will be loaded into based on a keffective criticality level. For this check the same 8 
assemblies in Table II-1 are used. It should be additionally noted that Big Rock assemblies are automatically placed in the first PWR waste package design 
(see Assumption 3.6) as specified in the waste package design input file (binInfo.dat). The Big Rock assumption was checked by visual observation of the 
output files. Additionally, a visual check was performed to ensure that the South Texas assemblies were loaded into waste package Bin 3 (12 PWR 
Absorber Plate-Long). 

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Table II-43. Assembly Criticality Level Determination 

Assembly 
Number Type 
Initial 
Enrichment 
(% U-235) 
Burnup 
(GWd/MTU) 
keffective for WP 
Bin 1 (21 PWR 
Absorber Plate) 
keffective for WP 
Bin 2 (21 
PWR Control 
Rod) 
keffective for WP 
Bin 3 (12 
PWR 
Absorber 
Plate-Long) 
keffective for 
WP Bin 4 
(44 BWR 
Absorber 
Plate) 
keffective for 
WP Bin 5 
(24 BWR 
Thick 
Absorber 
Plate) 
WP Bin that Assembly 
Should be Loaded Into 
a 
1 BWR 0.70 4.000 N/A N/A N/A 0.881 0 4 
2 BWR 3.00 27.000 N/A N/A N/A 0.903 0 4 
3 BWR 4.28 57.000 N/A N/A N/A 0.783 0 4 
4 PWR 0.71 39.149 0.448 0 0 N/A N/A 1 
5 PWR 3.75 37.399 0.900 0 0 N/A N/A 1 
6 PWR 5.00 60.000 0.875 0 0 N/A N/A 1 
7 BWR 3.71 5.000 N/A N/A N/A 1.136 0 5 
8 PWR 4.00 26.000 1.022 0 0 N/A N/A 2 

a The first bin of appropriate type (BWR or PWR) which provides a calculated keffective of 0.98 or less is bin that the assembly should be placed into. 
Table II-44. Criticality Level Check 

Assembly 
Number 
Waste Package Bin That 
Assembly Should be Loaded 
Into 
BIN.EXE 
Waste 
Package Bina 
1 4 4 
2 4 4 
3 4 4 
4 1 1 
5 1 1 
6 1 1 
7 5 5 
8 2 2 

a The BIN.EXE WP bin numbers is extracted from the output file bin.dat for the Case A, 84k MTU waste stream. 

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The other portion of Function 2 is the counting of assemblies that are placed into a specific waste package bin. This was checked in Table II-45 using 
arrival Case A, 84k MTU. Additionally checked is that the number of assemblies are translated into the correct number of waste packages. The number of 
waste packages for the check was simply calculated by dividing the number of assemblies for a given waste package design by the number of assemblies 
loaded into it, then rounding up the result. 

Table II-45. Assembly and Waste Package Numbers Check 

Waste 
Package 
Bin 
Number of 
Assemblies 
BIN.EXE number of 
assembliesa 
Number of Waste 
Packages 
BIN.EXE Number of 
Waste Packagesa 
1 119480 119480 5690 5690 
2 2207 2207 106 106 
3 3513 3513 293 293 
4 164165 164165 3732 3732 
5 2338 2338 98 98 

a The BIN.EXE values are extracted from the output file summary.dat for the Case A, 84k MTU waste stream. 

Check of Function 3 

Function 3 creates an average heat value at multiple time steps, normalized to the time of assembly arrival, for each waste package design. The check of 
Function 1 above determined that the interpolations for heat are correct. Therefore, the only check required for Function 3 is that the heat values are being 
appropriately averaged. For this check, the time step checked to determine that averaging was being applied correctly was based on the time of repository 
arrival. For the other time steps, the trend for decreasing heat values with the appropriate exponential decay shape was visually checked. 

BIN.EXE Case A, 84k MTU output file bin.dat was used for this check. 

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Table II-46. Average Heat Generation Rate Check (watts) 

Waste 
Package 
Bin 
Number of 
Assemblies 
Total Heat 
Generation Rate 
at Time of 
Repository 
Receipt from 
BIN.EXE output 
file "bin.dat" 
Average Heat 
Generation Rate 
at Time of 
Repository 
Receipt 
BIN.EXE 
Average Heat 
Generation Rate 
at Time of 
Repository 
Receipt a,b 
1 119480 64439245.97 539.33 539.33 
2 2207 342338.88 155.12 155.11 
3 3513 2626510.77 747.65 747.65 
4 164165 26105156.08 159.02 159.02 
5 2338 52704.46 22.54 22.54 

a Slight discrepancies in average heat as calculated by manipulating the BIN.EXE output file versus the average calculated by BIN.EXE are expected. This 
is because BIN.EXE will carry more significant digits than what it outputs to files. Therefore, the fractional difference for Waste Package Bin 2 is 
b The BIN.EXE values are extracted from the output file summary.dat for the Case A, 84k MTU waste stream. 

Check of Function 4 

Function 4 creates averages for burnup, enrichment, age, and MTU for each waste package design/bin. Through visual inspection, it was determined that 
the values for burnup, enrichment, age, and MTU from the input files were being properly recorded into the BIN.EXE output files. This check, shown in 
Table II-47, uses the "bin.dat" output file for waste stream Case A, 84k MTU. The bin.dat file was opened into Excel so that the averages for burnup, 
enrichment, age, and MTU could be determined for this check. 

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Table II-47. Average Characteristic Check for Waste Package Bins 

Waste 
Package 
Bin 
Average 
Burnup 
(GWd/MTU) 
BIN.EXE Average 
Burnupa 
(GWd/MTU) 
Average Initial 
Enrichment 
(% U-235) 
BIN.EXE 
Average 
Enrichmenta 
(% U-235) 
Average Age 
(years) 
BIN.EXE 
Average Agea 
(years) 
Average 
Assembly 
MTU 
BIN.EXE 
Average 
Assembly 
MTUa 
1 41.98 41.98 3.75 3.75 25.20 25.20 0.431 0.431 
2 19.86 19.86 3.61 3.61 35.83 35.83 0.376 0.376 
3 43.44 43.44 3.77 3.77 21.59 21.59 0.540 0.540 
4 33.98 33.98 3.02 3.02 25.08 25.08 0.178 0.178 
5 8.48 8.48 2.68 2.68 41.82 41.82 0.169 0.169 

a The BIN.EXE values are extracted from the output file summary.dat for the Case A, 84k MTU waste stream. 

This check of the software routine determined that the software routine is properly reading the input files and performing the intended calculations correctly 
for all four functions. 

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