ML15222A242

From kanterella
Jump to navigation Jump to search
Enclosure 2 - Attachment 3 - Atkins-NS-DAC-SHN-15-02, Revision 0
ML15222A242
Person / Time
Site: SHINE Medical Technologies, PROJ0792
Issue date: 07/23/2015
From:
SHINE Medical Technologies
To:
Office of Nuclear Reactor Regulation
Shared Package
ML15222A231 List:
References
SMT-2015-036 Atkins-NS-DAC-SHN-15-02, Rev 0
Download: ML15222A242 (40)
v • d • e


Text

ENCLOSURE 2 ATTACHMENT 3 SHINE MEDICAL TECHNOLOGIES, INC.

SHINE MEDICAL TECHNOLOGIES, INC. APPLICATION FOR CONSTRUCTION PERMIT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 6B.3-30 ATKINS-NS-DAC-SHN-15-02, REVISION 0 CRITICALITY SAFETY CALCULATIONS FOR THE PRELIMINARY DESIGN OF ANNULAR TANKS FOR THE SHINE MEDICAL ISOTOPE FACILITY 39 pages follow

Design Analyses and Calculation Table of Contents 1 INTRODUCTION .................................................................................................................................. 4

1.1 BACKGROUND

/PURPOSE ......................................................................................................................... 4 1.2 LIMITS OF APPLICABILITY ......................................................................................................................... 4 2 CONCLUSIONS ................................................................................................................................... 4 3 ANALYSIS/PROCESS METHODOLOGY ........................................................................................... 4 4 COMPUTER CODES USED IN DAC ................................................................................................... 4 5 ASSUMPTIONS & OPEN ITEMS......................................................................................................... 6 5.1 ASSUMPTIONS......................................................................................................................................... 6 5.2 OPEN ITEMS ........................................................................................................................................... 6 6 ACCEPTANCE CRITERIA ................................................................................................................... 6 6.1 BIASES AND UNCERTAINTIES.................................................................................................................... 6 6.2 AREA OF APPLICABILITY (AOA) ................................................................................................................ 6 7 CALCULATIONS.................................................................................................................................. 8 7.1 METHOD DISCUSSION.............................................................................................................................. 8 7.2 INPUTS ................................................................................................................................................. 13 7.3 EVALUATIONS, ANALYSIS, AND DETAILED CALCULATIONS ........................................................................ 15 8 REFERENCES ................................................................................................................................... 34 APPENDIX 1: REPRESENTATIVE INPUT FILES .................................................................................... 35 Page 3 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation 1 INTRODUCTION 1.1 Background/Purpose The SHINE Medical Technologies project will use uranium sulfate solution as a subcritical neutron fission target to produce 99Mo for medical uses. In addition, the facility will handle uranium metal as a feed material and uranium oxide for recycling uranium during the process.

Tanks containing fissile material will be necessary throughout the process. Tank volumes have been determined for those tanks which must contain all material in a single vessel. Through discussion with the designers, an annular tank design was decided upon. The height of the tank was defined by the designers. Therefore using the assumed height and defined volume, the tank diameters were calculated. Preference was given to minimizing the footprint area of the tank. Criticality safety calculations were then performed to determine if the design met the Upper Subcritical Limit (USL).

1.2 Limits of Applicability The results of this report are only applicable to the material types and tank designs that have been studied at the enrichment limit assumed.

2 CONCLUSIONS The following tank designs have been shown to meet the keff limit:

  • [ Proprietary Information ] [Security-Related Information ] tall annular tank with an outer diameter of[ Proprietary Information ] [Security-Related Information ].
  • [ Proprietary Information ] [Security-Related Information ] tall annular tank with an outer diameter of [ Proprietary Information ] [Security-Related Information ].
  • [ Proprietary Information ] [Security-Related Information ] tall annular tank with an outer diameter of [ Proprietary Information ] [Security-Related Information ].

The tanks all have a fissile material thickness of [ Proprietary Information ]

[Security-Related Information ] and a tank wall thickness of no greater than [ Proprietary Information ]

[Security-Related Information ]. The tank wall is modeled as fissile material effectively making the fissile thickness [ Proprietary Information ] [Security-Related Information ]. A

[ Proprietary Information ] [Security-Related Information ] neutron absorber plate consisting of PPC-B is present on the outside and inside diameters of the tank. The acceptable gap size between the neutron absorber and the tank wall is discussed in the report.

3 ANALYSIS/PROCESS METHODOLOGY This DAC does not model a process. See Section 7.1 for description of the models and calculation methodology.

4 COMPUTER CODES USED IN DAC MCNP is a general-purpose Monte Carlo N-Particle code that can be used for neutron, photon, electron, or coupled neutron/photon/electron transport, including the capability to calculate eigenvalues for critical systems (Reference 1).

MCNP 6.1 was run on the Atkins Linux computer cluster. All computers have 64-bit hardware and use the 64-bit version of Linux. Distribution of the calculation jobs among the individual CPUs is controlled by the Sun Grid Engine queue software running on the master Linux computer. Additional Linux execution hosts run calculation jobs at the command of the queue master. MCNP 6.1 has been installed in the read only disk area; the installation has been verified with the execution of the sample problems. This disk is shared with the execution hosts. Hardware and software used with the Atkins Linux computer cluster is managed with the Atkins NS Systems configuration control.

Page 4 of 41 Atkins-NS-DAC-SHN-15-02

Design Analyses and Calculation MCNP models a physical system with a three-dimensional configuration of geometric cells bounded by first and second-degree surfaces and fourth-degree elliptical tori. Each geometric cell contains a material or void as specified by the user to model the physical system. Material characteristics (i.e., cross sections) are represented by point-wise continuous cross-section data.

For neutrons, all reactions given in a particular cross-section library (such as ENDF/B-VII) are taken into account. Thermal neutrons are described by the free gas and S(, ) models. The MCNP neutron data library based on Evaluated Neutron Data File B-VII.1 (ENDF/B-VII.1) is the default for continuous energy neutron transport.

The specific elements and isotopes used in this evaluation are listed here with their library identifiers:

H 1001.80c 10 B 5010.80c 11 B 5011.80c C 6000.80c O 8016.80c Na 11023.80c Al 13027.80c Si-28 14028.80c Si-29 14029.80c Si-30 14030.80c S-32 16032.80c S-33 16033.80c S-34 16034.80c S-36 16036.80c Ca-40 20040.80c Ca-42 20042.80c Ca-43 20043.80c Ca-44 20044.80c Ca-46 20046.80c Ca-48 20048.80c Fe-54 26054.80c Fe-56 26056.80c Fe-57 26057.80c Fe-58 26058.80c U-235 92235.80c U-238 92238.80c The light water S(,) correction (lwtr.20t) is used for water (both in the solution and interstitial in the concrete) and the polyethylene S(,) correction (poly.20t) is used for PPC-B.

Page 5 of 41 Atkins-NS-DAC-SHN-15-02

Design Analyses and Calculation 5 ASSUMPTIONS & OPEN ITEMS 5.1 Assumptions

1. Temperature of all cases is assumed to be 20°C. Higher temperatures will result in lower reactivity due to the increase in neutron absorption due to Doppler broadening of the resonance region within 238U.
2. Solute saturation is assumed to be unlimited. Realistic saturation behavior is ignored in favor of showing the peak reactivity for the various materials regardless of concentration.
3. Uranyl sulfate is modeled assuming no excess acid as a conservative simplification. Excess acid will increase neutron absorption.
4. Uranium is assumed to be enriched to 21 wt% 235U.
5. Uranium dioxide theoretical density is 10.96 g/cc.
6. Water theoretical density is 0.9982 g/cc.
7. Density of PPC-B is assumed to be 0.955 g/cc.
8. Density of KENO Regular Concrete is 2.3 g/cc.
9. The following atom masses are assumed for the modeled isotopes and molecules.

235 U: 235.04392 g/mole 238 U: 238.05079 g/mole U (21 wt%): 237.42 g/mole S: 32.064388 g/mole O: 15.999 g/mole H: 1.0079 g/mole H2O: 18.0148 g/mole H2SO4: 98.076 g/mole UO2SO4: 365.478 g/mole UO2: 269.418 g/mole B: 10.811 g/mole C: 12.0107 g/mole

10. The atomic percentage of 10B in boron is assumed to be 19.9%.
11. Avogadros number is assumed to be 0.6022 atom-cm2/bn.
12. Heterogeneous effects within the solution are not considered in these calculations. The evaluation of the process for which these tanks are used will determine if heterogeneous particles are present and the analysis will be updated accordingly during final design.

5.2 Open Items There are no open items.

6 ACCEPTANCE CRITERIA 6.1 Biases and Uncertainties The methodology and results for the MCNP 6.1 code system validation for its use with the SHINE Medical Technologies applications are documented in Reference 2. Criticality safety experiments were selected from the International Handbook of Evaluated Criticality Safety Benchmark Experiments that adequately match the uranium enrichment, geometry, moderator, reflector, and neutron energy relevant to the processes within the SHINE facility. The bias Page 6 of 41 Atkins-NS-DAC-SHN-15-02

Design Analyses and Calculation results demonstrate that the calculated values sufficiently matched the reality of the experiments.

The final validation is expressed as an Upper Subcritical Limit (USL) calculated using the statistical accumulation of the experiments bias and bias uncertainty.

The Upper Subcritical Limit (USL) is calculated using the following equation:

USL = 1.0 + Bias - Bias Uncertainty - MOS

where, MOS = Margin of Subcriticality = 0.05 k, and Bias = 0.0025 k (positive bias is set to zero in the equation)

Bias Uncertainty = 0.0109 k Therefore the USL = 0.9391.

For an acceptable result, the MCNP keff + 2 must be less than the USL value.

6.2 Area of Applicability (AoA)

The AoA derived in Reference 2 is compared to the calculations performed here in Table 2. All parameters are within the AoA of the MCNP 6.1 validation. Therefore, no additional AoA margin is necessary.

Page 7 of 41 Atkins-NS-DAC-SHN-15-02

Design Analyses and Calculation Table 1: Area of Applicability Summary Area of Applicability from Area of Applicability for Parameter Validation Calculations UO2, UH3, Metal, UO2(NO3)2, Fissile Material UF4, U-ZrH, UO2F2, UxOy, UO2, Metal, UO2SO4 UO2SO4 Fissile Material Form Solid and Solution Solid and Solution H/235U ratio 0 H/235U 1400 64.7 H/235U 223.7 Average Neutron Energy Causing 0.0027 < ANECF < 1.46 0.0279 < ANECF < 0.0952 Fission (MeV)

Enrichment 10 to 36 wt.% 235U 21 wt.% 235U None, Water, nitric acid, sulfuric Moderating Materials Water, sulfuric acid acid, Hydrocarbon, CF2 None, Water, Concrete, BeO, Reflecting Materials Hydrocarbon Material, Iron, Water Graphite Boron, Cadmium, Aluminium, Absorber Materials Steel, Stainless Steel, None Hydrocarbon Material Homogeneous and Heterogeneous Geometry Spheres, Hemispheres, Cylinders Cylinders, Cuboids Single Units and Arrays 7 CALCULATIONS 7.1 Method Discussion 7.1.1 Geometry Model The annular tank model is defined based on the following design.

Page 8 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 1: Sketch of MCNP Model of Annular Tank Tank height is varied based on the specific design requirement. The fissile material thickness is unchanged at [ Proprietary Information ] [Security-Related Information ]. The tank walls are modeled as [ Proprietary Information ] [Security-Related Information ] of fissile material making the effective fissile material thickness [ Proprietary Information ] [Security-Related Information ]. The inner and outer gap between the PPC-B and tank wall are varied to determine the effect on reactivity. The PPC-B is

[ Proprietary Information ] [Security-Related Information ] in thickness. The thickness of the concrete is 36 inches on all sides. The distance between the outside diameter of the outer neutron absorber panel and the concrete reflector walls is 6 inches. The distance between the top and bottom of the tank to the top and bottom concrete reflector walls is 3 inches.

7.1.2 Material Specification Uranyl sulfate and uranium oxide mixed with water were modeled in this report. The following equations were used to determine the MCNP number density input. MCNP inputs are noted with italics.

Uranyl Sulfate Uranyl sulfate density is based on an empirical correlation which is specified in Reference 3. No excess acid (molarity = 0, normality = 0) is assumed for conservatism. The temperature is set at 20°C. The following equation was used to determine the uranyl sulfate density:

Page 9 of 41 Atkins-NS-DAC-SHN-15-02

Design Analyses and Calculation

( + )

= + . ( )

x .

Where:

= ,

= ,

= ,

+

= ( )

The uranium concentration is specified which allows the uranyl sulfate solution density to be calculated. Then the number densities for all isotopes can be determined using the following equations:

235 U atom density (atoms/bn-cm) = uran_conc/1000

  • 235U_wo / 235U_amu
  • avog 238 U atom density (atoms/bn-cm) = uran_conc/1000
  • 238U_wo / 238U_amu
  • avog U atom density (atoms/bn-cm) = 235U atom density + 238U atom density UO2SO4 density (g/cc) = U atom density/avog
  • UO2SO4_amu H2O density in mixture (g/cc) = solution_dens - UO2SO4 density S atom density (atoms/bn-cm) = U atom density O atom density (atoms/bn-cm) = 6 * (U atom density) + (H2O density in mixture/H2O_amu)
  • avog H atom density (atoms/bn-cm) = 2 * (H2O density in mixture/H2O_amu)
  • avog
where, uran_conc = uranium concentration in g/liter, 235U_wo = mass fraction of 235U in uranium, 238U_wo = mass fraction of 238U in uranium, 235U_amu = atomic mass of 235U, 238U_amu = atomic mass of 238U, UO2SO4_amu = atomic mass of UO2SO4, H2O_amu = atomic mass of H2O, solution_dens = uranyl sulfate density based on uranium concentration, and avog = Avogadros number.

Page 10 of 41 Atkins-NS-DAC-SHN-15-02

Design Analyses and Calculation Uranium Oxide and Water Uranium oxide was modeled as UO2. This molecule has the least number of oxygen atoms per uranium atoms which will result in the highest reactivity when compared other oxide compounds (ie. UO3, U3O8, etc.). A simple volume additive relation is used to derive the constituent element atom densities assuming a given uranium density within the mixture. The following equations were used to derive the number densities:

235 U atom density (atoms/bn-cm) = uran_dens

  • 235U_wo / 235U_amu
  • avog 238 U atom density (atoms/bn-cm) = uran_dens
  • 238U_wo / 238U_amu
  • avog UO2 density in mixture (g/cc) = uran_dens/U_amu
  • UO2_amu H2O density in mixture (g/cc) = (1 - (UO2 density in mixture/10.96))
  • 0.9982 Total density of mixture (g/cc) = UO2 density in mixture + H2O density in mixture O atom density (atoms/bn-cm) = (H2O density in mixture/H2O_amu)
  • avog + (2
  • UO2 density in mixture/UO2_amu)
  • avog H atom density (atoms/bn-cm) = 2 * (H2O density in mixture/H2O_amu)
  • avog
where, uran_dens = uranium density in g/cc, 235U_wo = mass fraction of 235U in uranium, 238U_wo = mass fraction of 238U in uranium, 235U_amu = atomic mass of 235U, 238U_amu = atomic mass of 238U, U_amu = atomic mass of U, UO2_amu = atomic mass of UO2, H2O_amu = atomic mass of H2O, UO2 density in mixture = uranium dioxide mass density in mixture, H2O density in mixture = water mass density in mixture, and avog = Avogadros number.

PPC-B PPC-B is a neutron shielding material manufactured by Liberty Pultrusions (Ref. 5) and primarily used by the Nuclear Navy. The material specification sheet is provided in Figure 2 (Ref. 6).

Page 11 of 41 Atkins-NS-DAC-SHN-15-02

Design Analyses and Calculation Figure 2: Manufacturer Information on PPC-B The following properties of PPC-B are assumed in the calculation of the number densities.

  • The boron weight percent is 5% (it was confirmed with the manufacturer that 5% was well within the capability of the manufacturing process).
  • The hydrogen weight percent is 12% minimum as specified by the manufacturer.

Minimum hydrogen density will result in the least amount of scattering in the absorber and thus the least amount of neutron absorption.

  • The remaining material is carbon which has a weight percent of 83%.
  • The density of PPC-B is 0.955 g/cc.
  • Only 75% of the calculated number density for both 10B and 11B are used.

Page 12 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Therefore the following number densities inputs were used in the modeling of PPC-B.

12% hydrogen 6000.80c 3.97433e-02 1001.80c 6.84728e-02 5010.80c 3.96984e-04 5011.80c 1.59791e-03 15% hydrogen 6000.80c 3.83068e-02 1001.80c 8.55909e-02 5010.80c 3.96984e-04 5011.80c 1.59791e-03 All units are atoms/bn-cm2.

Concrete Concrete was modeled using the KENO Regular Concrete Standard Mix as specified in Reference

4. Water content in the concrete will be evaluated in final design to ensure that reactivity is properly bounded for final concrete composition. The following weight fraction input was used in MCNP:

1001.80c -1.0000E-02 8016.80c -5.3200E-01 14028.80c -3.0959E-01 14029.80c -1.6289E-02 14030.80c -1.1121E-02 13027.80c -3.4000E-02 11023.80c -2.9000E-02 20040.80c -4.2531E-02 20042.80c -2.9804E-04 20043.80c -6.3670E-05 20044.80c -1.0066E-03 20046.80c -2.0180E-06 20048.80c -9.8446E-05 26054.80c -8E-04 26056.80c -1.29E-02 26057.80c -3E-04 26058.80c -4E-05 7.2 Inputs 7.2.1 Model Dimensions Tanks designs were based on the following requirements:

  • A [ Proprietary Information ] [Security-Related Information ] tall tank capable of holding

[ Proprietary Information ] [Security-Related Information ] of uranyl sulfate,

  • A [ Proprietary Information ] [Security-Related Information ] tall tank capable of holding

[ Proprietary Information ] [Security-Related Information ] of uranyl sulfate, and Page 13 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation

  • A [ Proprietary Information ] [Security-Related Information ] tank capable of holding

[ Proprietary Information ] [Security-Related Information ] of uranyl sulfate or uranium dioxide and water.

As discussed in 7.1.1 a fissile material thickness of [ Proprietary Information ]

[Security-Related Information ] was modeled. Assuming this the following tank outer diameters are necessary to meet the volume requirements.

  • A [ Proprietary Information ] [Security-Related Information ] tall tank with an outer diameter of

[ Proprietary Information ] [Security-Related Information ] has a volume of

[ Proprietary Information ] [Security-Related Information ],

  • A [ Proprietary Information ] [Security-Related Information ] tall tank with an outer diameter of

[ Proprietary Information ] [Security-Related Information ] has a volume of

[ Proprietary Information ] [Security-Related Information ], and

  • A [ Proprietary Information ] [Security-Related Information ] tall tank with an outer diameter of

[ Proprietary Information ] [Security-Related Information ] has a volume of

[ Proprietary Information ] [Security-Related Information ].

The remaining dimensions of the tank are based on these dimensions.

As discussed previously, the gap size between the PPC-B neutron absorber and the tank wall was varied. The values modeled were [ Proprietary Information ] [Security-Related Information ]. All combinations of gap sizes were considered.

7.2.2 Material Concentrations/Densities All three tanks were evaluated with uranyl sulfate as the fissile material of interest. The

[ Proprietary Information ] [Security-Related Information ] tall tank was also modeled with uranium dioxide since that tank design will be used to dissolve uranium oxide powder with sulfuric acid to create uranyl sulfate.

Uranyl sulfate densities of 500 to 1100 gU/l were modeled for both void and water flooded conditions. This range was chosen to include the most reactive concentration for each set of conditions. Uranium dioxide densities of 0.8 to 1.6 g/cc were modeled.

All three tank designs were modeled with void in all spaces where tank material is not present including the gap between the tank wall and neutron absorber and between the absorber and the concrete reflector. The tank designs were also modeled with water in all these locations to determine whether void or water is more reactive.

Page 14 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation 7.3 Evaluations, Analysis, and Detailed Calculations The results of the annular tank calculations are listed in the following sections. All cases were inspected for convergence and found to be acceptable. The average uncertainty associated with MCNP calculations was 0.00064 k.

7.3.1 [ Proprietary Information ] [ Security-Related Information ] Tall Tanks Calculations were performed with the previously descripted MCNP annular tank model using uranyl sulfate as the fissile material. Both void and water were used to fill the gaps and space outside the tanks. Results are shown in Figures 1 - 4 for void and Figures 5 - 8 for water.

Proprietary Information Security-Related Information Figure 1: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 2: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 15 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 3: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 4: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 16 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 5: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 6: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 17 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 7: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 8: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

For each inner/outer gap unique combination in the voided condition, the peak keff + 2 value is summarized in Table 2. For each inner/outer gap unique combination in the water flooded condition, the peak keff + 2 value is summarized in Table 3.

Page 18 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Table 2: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Voided Condition Results Summary Proprietary Information Security-Related Information Table 3: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Water Flooded Condition Results Summary Proprietary Information Security-Related Information Results show that largest value for the inner gap is the worst case for both void and water flooded. Results also show that the smallest value for the outer gap is generally the worst case for voided conditions but the largest value for the outer gap is the worst case for water flooded conditions. This behavior is expected. In the voided conditions, moving the neutron absorber closer to the fissile material will increase the neutron reflection caused by the neutron absorber thus increasing the keff. However, with water flooded conditions, moving the neutron absorber further from the fissile material will increase the thickness of water next to the fissile material and increase the neutron reflection provided to the tank.

Therefore, when manufactured, the inner gap must be kept to a minimum size of no greater than

[ Proprietary Information ] [ Security-Related Information ] to meet the USL of 0.9391. Outer gap size must be limited to [ Proprietary Information ] [ Security-Related Information ] to meet the USL of 0.9391. Design tolerances will be defined during final design and comparison to these calculations will be made at that time. Adjustments to the models and calculations will be done, as necessary, to support final design.

Page 19 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation 7.3.2 [ Proprietary Information ] [Security-Related Information ] Tall Tanks Calculations were performed with the previously descripted MCNP annular tank model using uranyl sulfate as the fissile material. Both void and water were used to fill the gaps and space outside the tanks. Results are shown in Figures 9 - 12 for void and Figures 13 - 16 for water.

Proprietary Information Security-Related Information Figure 9: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 10: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 20 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 11: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 12: [ Proprietary Information ] [ Security-Related Information ] annular tank with void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 21 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 13: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 14: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 22 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 15: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 16: [ Proprietary Information ] [ Security-Related Information ] annular tank with water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

For each inner/outer gap unique combination in the voided condition, the peak keff + 2 value is summarized in Table 4. For each inner/outer gap unique combination in the water flooded condition, the peak keff + 2 value is summarized in Table 5.

Page 23 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Table 4: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Voided Condition Results Summary Proprietary Information Security-Related Information Table 5: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Water Flooded Condition Results Summary Proprietary Information Security-Related Information Results show a similar keff behavior with regards to the gap size as in the [ Proprietary Information ]

[ Security-Related Information ] annular tanks. The inner gap must be kept to a minimum size of no greater than [ Proprietary Information ] [ Security-Related Information ] to meet the USL of 0.9391. Outer gap size must be limited to [ Proprietary Information ]

[ Security-Related Information ] to meet the USL of 0.9391. Again, the final design phase will set the values and calculations will be modified, as needed.

Page 24 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation 7.3.3 [ Proprietary Information ] [Security-Related Information ] Tall Tanks Calculations were performed with the previously descripted MCNP annular tank model using uranyl sulfate and uranium dioxide as the fissile material. Both void and water were used to fill the gaps and space outside the tanks. Results are shown in Figures 17 - 20 for sulfate and void, Figures 21 - 24 for sulfate and water, Figures 25 - 28 for oxide and void, and Figures 29 - 32 for oxide and water.

Proprietary Information Security-Related Information Figure 17: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 18: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 25 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 19: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 20: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 26 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 21: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 22: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 27 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 23: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 24: [ Proprietary Information ] [ Security-Related Information ] annular tank with sulfate and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 28 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 25: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 26: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 29 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 27: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 28: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and void, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 30 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 29: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 30: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Page 31 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Figure 31: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

Proprietary Information Security-Related Information Figure 32: [ Proprietary Information ] [ Security-Related Information ] annular tank with oxide and water, Inner Gap [ Proprietary Information ] [ Security-Related Information ]

For each inner/outer gap unique combination in the voided condition, the peak keff + 2 value is summarized in Table 6 and Table 8. For each inner/outer gap unique combination in the water flooded condition, the peak keff + 2 value is summarized in Table 7 and Table 9.

Page 32 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Table 6: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Voided Condition Uranyl Sulfate Results Summary Proprietary Information Security-Related Information Table 7: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Water Flooded Condition Uranyl Sulfate Results Summary Proprietary Information Security-Related Information Table 8: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Voided Condition Uranium Dioxide Results Summary Proprietary Information Security-Related Information Table 9: [ Proprietary Information ] [ Security-Related Information ] Annular Tanks Water Flooded Condition Uranium Dioxide Results Summary Proprietary Information Security-Related Information Results show a similar keff behavior with regards to the gap size as in the

[ Proprietary Information ] [ Security-Related Information ] annular tanks. These results show more margin to the USL limit of 0.9391. There is enough margin to allow the outer gap to be

[ Proprietary Information ] [ Security-Related Information ]. The inner gap may not exceed

[ Proprietary Information ] [ Security-Related Information ]. Again, the final design phase will set the values and calculations will be modified, as needed.

Page 33 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation 7.3.4 Study of Hydrogen Content in PPC-B Calculations were performed with the ten foot annular tanks for both void and water conditions.

The worst case inner and outer gap thickness model was chosen to see the effect of increasing the PPC-B hydrogen content. The hydrogen density was increased to 15% in the new cases. For the void condition, the inner gap was [ Proprietary Information ] [ Security-Related Information ]

and the outer gap was [ Proprietary Information ] [ Security-Related Information ]. For the water condition, the inner gap was [ Proprietary Information ] [ Security-Related Information ] and the outer gap was [ Proprietary Information ] [ Security-Related Information ]. Results are plotted in Figure 33. The results demonstrate that higher hydrogen density in the PPC-B results in lower keff values. Therefore a minimum hydrogen density of 12%, as specified by the manufacturer, will ensure the USL is met.

Proprietary Information Security-Related Information Figure 33: Increased Hydrogen Density with [ Proprietary Information ]

[ Security-Related Information ] Annular Tanks 8 REFERENCES

1. X-5 Monte Carlo Team, MCNP - A General Monte Carlo N-Particle Transport Code, Version 5, LA-UR-03-1987, Los Alamos National Laboratory, April 2003.
2. Revolinski, S., MCNP 6.1 Validation with Continuous Energy ENDF/B-VII.1 Cross Sections for SHINE Medical Technologies, Atkins-NS-DAC-SHN-15-03, Rev. 1, Atkins Nuclear Solutions US, June 2015.
3. Glunz, H., V and V Report: Uranyl Sulfate Solution Densities, NSA-TR-SHN-12-03, Rev. 1, Nuclear Safety Associates, Inc., February, 2013.
4. Goorley, T., Criticality Calculations with MCNP5: A Primer, LA-UR-04-0294, 2004.
5. Liberty Pultrusions: Manufacturer of Engineered FRP Pultrusions, Liberty Pultrusions, Retrieved from http://www.libertypultrusions.com/, 2015.
6. Properties of PPC, Liberty Pultrusions, Retrieved from http://www.libertypultrusions.com/images/Neutron_Shielding_Properties2.pdf, 2015.

Page 34 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation APPENDIX 1: REPRESENTATIVE INPUT FILES Annular tank model with voided conditions All annular tank models with voided conditions inputs are a variation of the model described in this input file with tank diameters, tank height, gap thicknesses (and corresponding diameters) and material #1 changed as appropriate.

Proprietary Information Security-Related Information Page 35 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Page 36 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Page 37 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Annular tank model with water flooded conditions All annular tank models with water flooded conditions inputs are a variation of the model described in this input file with tank diameters, tank height, gap thicknesses (and corresponding diameters) and material #1 changed as appropriate.

Proprietary Information Security-Related Information Page 38 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Page 39 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Page 40 of 41 Atkins-NS-DAC-SHN-15-02

[Proprietary Information - Withheld from Public Disclosure Under 10 CFR 2.390(a)(4)]

Security-Related Information - Withheld Under 10 CFR 2.390 Design Analyses and Calculation Proprietary Information Security-Related Information Page 41 of 41 Atkins-NS-DAC-SHN-15-02

Retrieved from "https://kanterella.com/w/index.php?title=ML15222A242&oldid=2447552"