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Remove examples/xml/
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aba1c4a16d
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26 changed files with 0 additions and 529 deletions
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cmake_minimum_required(VERSION 3.3 FATAL_ERROR)
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project(openmc_sources CXX)
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add_library(source SHARED source_ring.cpp)
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find_package(OpenMC REQUIRED)
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if (OpenMC_FOUND)
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message(STATUS "Found OpenMC: ${OpenMC_DIR}")
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endif()
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target_link_libraries(source OpenMC::libopenmc)
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@ -1,15 +0,0 @@
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<?xml version="1.0"?>
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<geometry>
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<!-- Definition of Cells -->
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<cell id="1" universe="0" fill="37" region="-2" />
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<cell id="100" universe="37" material="40" region="-1" />
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<cell id="101" universe="37" material="41" region="1" />
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<cell id="2" universe="0" material="41" region="2 -3" />
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<!-- Defition of Surfaces -->
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<surface id="1" type="z-cylinder" coeffs="0 0 7" />
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<surface id="2" type="z-cylinder" coeffs="0 0 9" />
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<surface id="3" type="z-cylinder" coeffs="0 0 11" boundary="vacuum" />
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</geometry>
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@ -1,16 +0,0 @@
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<?xml version="1.0"?>
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<materials>
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<material id="40">
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<density value="4.5" units="g/cc" />
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<nuclide name="U235" ao="1.0" />
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</material>
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<material id="41">
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<density value="1.0" units="g/cc" />
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<nuclide name="H1" ao="2.0" />
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<nuclide name="O16" ao="1.0" />
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<sab name="c_H_in_H2O"/>
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</material>
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</materials>
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@ -1,14 +0,0 @@
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<?xml version="1.0"?>
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<settings>
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<run_mode>fixed source</run_mode>
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<batches>10</batches>
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<inactive>0</inactive>
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<particles>100000</particles>
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<!-- Starting source -->
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<source>
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<library>build/libsource.so</library>
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</source>
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</settings>
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@ -1,26 +0,0 @@
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#include <cmath> // for M_PI
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#include "openmc/random_lcg.h"
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#include "openmc/source.h"
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#include "openmc/particle.h"
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// you must have external C linkage here otherwise
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// dlopen will not find the file
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extern "C" openmc::Particle::Bank sample_source(uint64_t* seed)
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{
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openmc::Particle::Bank particle;
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// wgt
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particle.particle = openmc::Particle::Type::neutron;
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particle.wgt = 1.0;
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// position
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double angle = 2. * M_PI * openmc::prn(seed);
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double radius = 3.0;
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particle.r.x = radius * std::cos(angle);
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particle.r.y = radius * std::sin(angle);
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particle.r.z = 0.0;
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// angle
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particle.u = {1.0, 0.0, 0.0};
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particle.E = 14.08e6;
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particle.delayed_group = 0;
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return particle;
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}
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@ -1,17 +0,0 @@
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<?xml version="1.0"?>
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<tallies>
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<filter id="1" type="cell">
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<bins>100</bins>
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</filter>
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<filter id="2" type="energy">
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<bins>0 20.0e6</bins>
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</filter>
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<tally id="3">
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<filters>1 2 </filters>
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<scores>flux</scores>
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</tally>
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</tallies>
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@ -1,43 +0,0 @@
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<?xml version="1.0"?>
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<geometry>
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<cell id="1" fill="6" region="1 -2 3 -4" />
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<cell id="2" universe="5" fill="4" region="1 -2 3 -4" />
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<cell id="101" universe="1" material="1" region="-5" />
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<cell id="102" universe="1" material="2" region="5" />
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<cell id="201" universe="2" material="1" region="-6" />
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<cell id="202" universe="2" material="2" region="6" />
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<cell id="301" universe="3" material="1" region="-7" />
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<cell id="302" universe="3" material="2" region="7" />
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<!-- 4 x 4 assembly -->
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<lattice id="4">
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<dimension>2 2</dimension>
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<lower_left>-1.0 -1.0</lower_left>
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<pitch>1.0 1.0</pitch>
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<universes>
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1 2
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2 3
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</universes>
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</lattice>
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<!-- 4 x 4 core -->
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<lattice id="6">
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<dimension>2 2</dimension>
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<lower_left>-2.0 -2.0</lower_left>
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<pitch>2.0 2.0</pitch>
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<universes>
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5 5
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5 5
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</universes>
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</lattice>
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<surface id="1" type="x-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="2" type="x-plane" coeffs="2.0" boundary="vacuum" />
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<surface id="3" type="y-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="4" type="y-plane" coeffs="2.0" boundary="vacuum" />
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<surface id="5" type="z-cylinder" coeffs="0.0 0.0 0.4" />
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<surface id="6" type="z-cylinder" coeffs="0.0 0.0 0.3" />
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<surface id="7" type="z-cylinder" coeffs="0.0 0.0 0.2" />
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</geometry>
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@ -1,17 +0,0 @@
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<?xml version="1.0"?>
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<materials>
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<!-- Definition of materials -->
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<material id="1">
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<density value="4.5" units="g/cc" />
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<nuclide name="U235" ao="1.0" />
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</material>
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<material id="2">
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<density value="1.0" units="g/cc" />
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<nuclide name="H1" ao="2.0" />
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<nuclide name="O16" ao="1.0" />
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<sab name="c_H_in_H2O" />
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</material>
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</materials>
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@ -1,10 +0,0 @@
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<?xml version="1.0"?>
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<plots>
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<plot id="1" color_by="material">
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<origin>0. 0. 0.</origin>
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<width>4.0 4.0</width>
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<pixels>400 400</pixels>
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</plot>
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</plots>
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@ -1,17 +0,0 @@
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<?xml version="1.0"?>
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<settings>
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<!-- Parameters for k-eigenvalue calculation -->
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<run_mode>eigenvalue</run_mode>
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<batches>20</batches>
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<inactive>10</inactive>
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<particles>10000</particles>
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<!-- Starting source -->
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<source>
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<space type="box">
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<parameters>-1 -1 -1 1 1 1</parameters>
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</space>
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</source>
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</settings>
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@ -1,20 +0,0 @@
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<?xml version="1.0"?>
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<tallies>
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<mesh id="1">
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<type>regular</type>
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<dimension>4 4</dimension>
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<lower_left>-2.0 -2.0</lower_left>
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<width>1.0 1.0</width>
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</mesh>
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<filter id="1" type="mesh">
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<bins>1</bins>
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</filter>
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<tally id="1">
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<filters>1</filters>
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<scores>total</scores>
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</tally>
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</tallies>
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@ -1,32 +0,0 @@
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<?xml version="1.0"?>
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<geometry>
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<cell id="1" fill="5" region="1 -2 3 -4" />
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<cell id="101" universe="1" material="1" region="-5" />
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<cell id="102" universe="1" material="2" region="5" />
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<cell id="201" universe="2" material="1" region="-6" />
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<cell id="202" universe="2" material="2" region="6" />
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<cell id="301" universe="3" material="1" region="-7" />
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<cell id="302" universe="3" material="2" region="7" />
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<lattice id="5">
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<dimension>4 4</dimension>
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<lower_left>-2.0 -2.0</lower_left>
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<pitch>1.0 1.0</pitch>
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<universes>
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1 2 1 2
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2 3 2 3
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1 2 1 2
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2 3 2 3
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</universes>
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</lattice>
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<surface id="1" type="x-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="2" type="x-plane" coeffs="2.0" boundary="vacuum" />
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<surface id="3" type="y-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="4" type="y-plane" coeffs="2.0" boundary="vacuum" />
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<surface id="5" type="z-cylinder" coeffs="0.0 0.0 0.4" />
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<surface id="6" type="z-cylinder" coeffs="0.0 0.0 0.3" />
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<surface id="7" type="z-cylinder" coeffs="0.0 0.0 0.2" />
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</geometry>
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@ -1,17 +0,0 @@
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<?xml version="1.0"?>
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<materials>
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<!-- Definition of materials -->
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<material id="1">
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<density value="4.5" units="g/cc" />
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<nuclide name="U235" ao="1.0" />
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</material>
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<material id="2">
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<density value="1.0" units="g/cc" />
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<nuclide name="H1" ao="2.0" />
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<nuclide name="O16" ao="1.0" />
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<sab name="c_H_in_H2O" />
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</material>
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</materials>
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@ -1,10 +0,0 @@
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<?xml version="1.0"?>
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<plots>
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<plot id="1" color_by="material">
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<origin>0. 0. 0.</origin>
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<width>4.0 4.0</width>
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<pixels>400 400</pixels>
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</plot>
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</plots>
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@ -1,17 +0,0 @@
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<?xml version="1.0"?>
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<settings>
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<!-- Parameters for k-eigenvalue calculation -->
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<run_mode>eigenvalue</run_mode>
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<batches>20</batches>
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<inactive>10</inactive>
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<particles>10000</particles>
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<!-- Starting source -->
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<source>
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<space type="box">
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<parameters>-1 -1 -1 1 1 1</parameters>
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</space>
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</source>
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</settings>
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@ -1,20 +0,0 @@
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<?xml version="1.0"?>
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<tallies>
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<mesh id="1">
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<type>regular</type>
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<dimension>4 4</dimension>
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<lower_left>-2.0 -2.0</lower_left>
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<width>1.0 1.0</width>
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</mesh>
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<filter id="1" type="mesh">
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<bins>1</bins>
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</filter>
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<tally id="1">
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<filters>1</filters>
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<scores>total</scores>
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</tally>
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</tallies>
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@ -1,27 +0,0 @@
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<?xml version="1.0"?>
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<geometry>
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<!--
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This is a simple pin cell model based on dimensions from the MIT BEAVRS
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(Benchmarking for Evaluation and Validation of Reactor Simulations)
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benchmark.
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-->
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<!-- Surfaces for fuel, gap, cladding. Dimensions from Figure 2 in BEAVRS -->
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<surface id="1" type="z-cylinder" coeffs="0. 0. 0.39218" /> <!-- Fuel OR -->
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<surface id="2" type="z-cylinder" coeffs="0. 0. 0.40005" /> <!-- Clad IR -->
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<surface id="3" type="z-cylinder" coeffs="0. 0. 0.45720" /> <!-- Clad OR -->
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<!-- Reflective surfaces on outside of pin-cell. The lattice pitch is 1.25984
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cm (taken from Table 2 in BEAVRS). -->
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<surface id="4" type="x-plane" coeffs="-0.62992" boundary="reflective" />
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<surface id="5" type="x-plane" coeffs=" 0.62992" boundary="reflective" />
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<surface id="6" type="y-plane" coeffs="-0.62992" boundary="reflective" />
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<surface id="7" type="y-plane" coeffs=" 0.62992" boundary="reflective" />
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<cell id="1" material="1" region=" -1" /> <!-- UO2 Fuel -->
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<cell id="2" material="2" region="1 -2" /> <!-- Helium gap -->
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<cell id="3" material="3" region="2 -3" /> <!-- Zircaloy cladding -->
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<cell id="4" material="4" region="3 4 -5 6 -7" /> <!-- Borated water -->
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</geometry>
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@ -1,67 +0,0 @@
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<?xml version="1.0"?>
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<materials>
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<!--
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Since O-18 is not present in ENDF/B-VII, it was necessary to combine the
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atom densities for O-17 and O-18 in any materials containing Oxygen.
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-->
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<!-- UO2 fuel at 2.4 wt% enrichment -->
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<material id="1">
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<density value="10.29769" units="g/cm3" />
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<nuclide name="U234" ao="4.4843e-06" />
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<nuclide name="U235" ao="5.5815e-04" />
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<nuclide name="U238" ao="2.2408e-02" />
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<nuclide name="O16" ao="4.5829e-02" />
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<nuclide name="O17" ao="1.1164e-04" />
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</material>
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<!-- Helium for gap -->
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<material id="2">
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<density value="0.001598" units="g/cm3" />
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<nuclide name="He4" ao="2.4044e-04" />
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</material>
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<!-- Zircaloy 4 -->
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<material id="3">
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<density value="6.55" units="g/cm3" />
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<nuclide name="O16" ao="3.0743e-04" />
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<nuclide name="O17" ao="7.4887e-07" />
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<nuclide name="Cr50" ao="3.2962e-06" />
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<nuclide name="Cr52" ao="6.3564e-05" />
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<nuclide name="Cr53" ao="7.2076e-06" />
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<nuclide name="Cr54" ao="1.7941e-06" />
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<nuclide name="Fe54" ao="8.6699e-06" />
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<nuclide name="Fe56" ao="1.3610e-04" />
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<nuclide name="Fe57" ao="3.1431e-06" />
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<nuclide name="Fe58" ao="4.1829e-07" />
|
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<nuclide name="Zr90" ao="2.1827e-02" />
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<nuclide name="Zr91" ao="4.7600e-03" />
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<nuclide name="Zr92" ao="7.2758e-03" />
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<nuclide name="Zr94" ao="7.3734e-03" />
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<nuclide name="Zr96" ao="1.1879e-03" />
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<nuclide name="Sn112" ao="4.6735e-06" />
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<nuclide name="Sn114" ao="3.1799e-06" />
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<nuclide name="Sn115" ao="1.6381e-06" />
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<nuclide name="Sn116" ao="7.0055e-05" />
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<nuclide name="Sn117" ao="3.7003e-05" />
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<nuclide name="Sn118" ao="1.1669e-04" />
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<nuclide name="Sn119" ao="4.1387e-05" />
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<nuclide name="Sn120" ao="1.5697e-04" />
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<nuclide name="Sn122" ao="2.2308e-05" />
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<nuclide name="Sn124" ao="2.7897e-05" />
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</material>
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<!-- Borated water at 975 ppm -->
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<material id="4">
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<density value="0.740582" units="g/cm3" />
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<nuclide name="B10" ao="8.0042e-06" />
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<nuclide name="B11" ao="3.2218e-05" />
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<nuclide name="H1" ao="4.9457e-02" />
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<nuclide name="H2" ao="7.4196e-06" />
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<nuclide name="O16" ao="2.4672e-02" />
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<nuclide name="O17" ao="6.0099e-05" />
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<sab name="c_H_in_H2O" />
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</material>
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|
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</materials>
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@ -1,32 +0,0 @@
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<?xml version="1.0"?>
|
||||
<settings>
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||||
|
||||
<!-- Define how many particles to run and for how many batches -->
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<run_mode>eigenvalue</run_mode>
|
||||
<batches>100</batches>
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<inactive>10</inactive>
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<particles>1000</particles>
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||||
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||||
<!-- The starting source is a uniform distribution over the entire pin
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cell. Note that since this is effectively a 2D model, the z coordinates
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are inconsequential -->
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<source>
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<space type="box">
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||||
<parameters>
|
||||
-0.62992 -0.62992 -1.
|
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0.62992 0.62992 1.
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||||
</parameters>
|
||||
</space>
|
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</source>
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||||
<!-- To assess convergence of the source distribution, we need to define the
|
||||
bounds for a mesh over which the Shannon entropy should be
|
||||
calculated. The extent in the z direction is made arbitrarily large. -->
|
||||
<mesh id="1">
|
||||
<lower_left>-0.39218 -0.39218 -1.e50</lower_left>
|
||||
<upper_right>0.39218 0.39218 1.e50</upper_right>
|
||||
<dimension>10 10 1</dimension>
|
||||
</mesh>
|
||||
<entropy_mesh>1</entropy_mesh>
|
||||
|
||||
</settings>
|
||||
|
|
@ -1,23 +0,0 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="2" type="regular">
|
||||
<dimension>100 100 1</dimension>
|
||||
<lower_left>-0.62992 -0.62992 -1.e50</lower_left>
|
||||
<upper_right>0.62992 0.62992 1.e50</upper_right>
|
||||
</mesh>
|
||||
|
||||
<filter id="1" type="mesh">
|
||||
<bins>2</bins>
|
||||
</filter>
|
||||
|
||||
<filter id="2" type="energy">
|
||||
<bins>0. 4. 20.0e6</bins>
|
||||
</filter>
|
||||
|
||||
<tally id="1">
|
||||
<filters>1 2</filters>
|
||||
<scores>flux fission nu-fission</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
|
|
@ -1,10 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="1" material="1" name="cell 1" region="-1" universe="0" />
|
||||
<cell id="2" material="2" name="cell 2" region="1 4 -5 6 -7" universe="0" />
|
||||
<surface coeffs="0 0 0.54" id="1" name="Fuel OR" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="4" name="left" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.63" id="5" name="right" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="6" name="bottom" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs="0.63" id="7" name="top" type="y-plane" />
|
||||
</geometry>
|
||||
|
|
@ -1,12 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<cross_sections>./mgxs.h5</cross_sections>
|
||||
<material id="1" name="UO2 fuel">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="UO2" />
|
||||
</material>
|
||||
<material id="2" name="Water">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="LWTR" />
|
||||
</material>
|
||||
</materials>
|
||||
Binary file not shown.
|
|
@ -1,28 +0,0 @@
|
|||
<?xml version="1.0"?>
|
||||
<plots>
|
||||
|
||||
<plot>
|
||||
<id>1</id>
|
||||
<filename>mat</filename>
|
||||
<color_by>material</color_by>
|
||||
<origin>0 0 0</origin>
|
||||
<width>1.26 1.26</width>
|
||||
<type>slice</type>
|
||||
<pixels>1000 1000 </pixels>
|
||||
<color id="1" rgb="255 0 0" />
|
||||
<color id="2" rgb="0 0 0" />
|
||||
<color id="3" rgb="0 255 0" />
|
||||
<color id="4" rgb="0 0 255" />
|
||||
</plot>
|
||||
|
||||
<plot>
|
||||
<id>2</id>
|
||||
<filename>cell</filename>
|
||||
<color_by>cell</color_by>
|
||||
<origin>0 0 0</origin>
|
||||
<width>1.26 1.26</width>
|
||||
<type>slice</type>
|
||||
<pixels>1000 1000 </pixels>
|
||||
</plot>
|
||||
|
||||
</plots>
|
||||
|
|
@ -1,13 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<settings>
|
||||
<run_mode>eigenvalue</run_mode>
|
||||
<particles>1000</particles>
|
||||
<batches>100</batches>
|
||||
<inactive>10</inactive>
|
||||
<source strength="1.0">
|
||||
<space type="box">
|
||||
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<energy_mode>multi-group</energy_mode>
|
||||
</settings>
|
||||
|
|
@ -1,18 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
<mesh id="1" type="regular">
|
||||
<dimension>100 100 1</dimension>
|
||||
<lower_left>-0.63 -0.63 -1e+50</lower_left>
|
||||
<upper_right>0.63 0.63 1e+50</upper_right>
|
||||
</mesh>
|
||||
<filter id="1" type="energy">
|
||||
<bins>1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0</bins>
|
||||
</filter>
|
||||
<filter id="2" type="mesh">
|
||||
<bins>1</bins>
|
||||
</filter>
|
||||
<tally id="1" name="tally 1">
|
||||
<filters>1 2</filters>
|
||||
<scores>flux fission nu-fission</scores>
|
||||
</tally>
|
||||
</tallies>
|
||||
Loading…
Add table
Add a link
Reference in a new issue