Simulation of Uranium-235 Nuclear Fission Reactor Core

using quasi-Monte Carlo Techniques

 

 

 

with a special appendix

Chaos in the Computational Laboratory:

New Fractal Discovered while Simulating Uranium-235 Fission

 

 

Daniar Hussain

CSAP 415

Department of Mathematics

New Trier High School

Winnetka, Illinois

January 1999

Abstract

A computational model of uranium-235 fission was developed using certain simple physical assumptions. Experiments were performed on this model to determine how certain initial conditions (such as temperature) affect the reaction rate, final equilibrium position, and other properties in an effort to understand conditions that lead to a runaway meltdown. In addition, a new fractal was discovered while working with this model.

 

Table of Contents

Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

Introduction

Objective

The Reaction

Physical Assumptions

The Reactor

Reactor Simplifications

Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

Normal Operation

Catastrophic Conditions

Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .10

Appendix A: Source Code . . . . . . . . . . . . . . . . . . . . . .11

Appendix B: New Fractal . . . . . . . . . . . . . . . . . . . . . . 17

Introduction

Source Code

Initial Conditions

Sample Images

Appendix C: Data . . . . . . . . . . . . . . . . . . . . . . . . . . . .22

Normal Opeartion

Catastrophic Conditions

References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .24

Background

Introduction

In recent years, nuclear reactions have become an integral part of our lives, whether we realize it or not. The Cold War (1945-1990) between the United States and the former USSR was largely driven by the competition for nuclear weapons. And presently, 8% of American primary energy and as much as 19% of electrical energy comes from nuclear sources. There is still much basic science that needs to be understood before nuclear energy can replace conventional sources, and before nuclear reactors become safe and small enough for daily use.

 

Objective

To simulate the state of a uranium-235 nuclear fission reactor core under normal operation. To investigate the condition of a runaway reactor moments before meltdown, as occurred in Chernobyl, USSR in 1986.

 

The Reaction

Uranium undergoes fission if it collides with a neutron with sufficient kinetic energy. This energy is called the activation energy, and is required to attain the activated complex, or the state of highest energy. Energy must be supplied to overcome the large strong nuclear force that exists between the nucleotides (protons and neutrons). Once enough kinetic energy overcomes this strong force, the electrostatic repulsion between positive protons tears the nucleus apart. The precise reaction mechanism does not concern us, just the energy released and final products. The resulting products weight less than the initial reactants, and this mass is converted into energy in the manner described by Einstein’s reactions E = m∙c2. The products are also radioactive, and emit more energy through beta and gamma decay. The following is just one of the many ways in which uranium can undergo fission.

1 235 141 92 1

n + U à Ba + Kr + 3 n ∆H = -3.5 ∙ 10-11 J

0 92 56 36 0

Notice that three neutrons are released in this reaction; these neutrons continue the reaction by colliding with other uranium nuclei. In another variant of uranium fission, only two neutrons may be released. These neutrons make it possible to have a self-sustained fission process, or a chain reaction. In order for the fission process to be self-sustained, at least one neutron from each fission event must go on to split another nucleus. If, on average, less than one neutron causes another fission event, the reaction dies out, and the reaction is said to be subcritical. If exactly one neutron from each fission event causes another fission event, the process sustains itself at the same level and is said to be critical. If more than one neutron from each fission event causes another fission event, the process accelerates rapidly and the heat buildup causes a violent explosion. This happened in the Chernobyl nuclear disaster, and is described as supercritical. This number will be one of the variables that we will investigate.

Note also the large amount of energy released in this reaction (-3.5∙10-11 J/event, which translates to 2.1∙1013 J/mol U-235), compared to the combustion of methane, which releases only 8.0∙105 J/mol CH4.

 

Physical Assumptions

    1. Each particle is assumed to be a uniform, solid rectangle, to simplify the collision routines. This is reasonable since the nucleotides are highly tightly packed, and their small size allows for the rectangular approximation to be valid.
    2. It is further assumed that there are no attractive/repulsive forces between particles and that all non-effective collisions are elastic. Again this is reasonable since the fission reactions involve the collision of U-235 and a neutron, which is uncharged, so it does not participate in electrostatic interactions. The repulsion force that exists between U-235 nuclei is not critical for this simulation.
    3. The two products, Ba-141 and Kr-92, although radioactive, do not participate further in the reaction, so they will be tracked throughout the simulation, but will not undergo any reactions.
    4. It is also assumed that there are no electrons in the core, although not quite accurate, but since the electrons do not participate in the reaction, they can be safely ignored as spectators.
    5. We assume that the energy given off during the reaction is released as kinetic energy, i.e., as very fast products:
    6. KE = ½ * m * v2

      KEprod – KEreact = -∆H

    7. The temperature for the core is calculated as follows (derived from the Ideal Gas Law):
    8. KEave = NA ∙ (1/2 ∙ m ∙ uave2)

      where NA = Avagadro’s number = 6.022∙1023 particles/mole

      uave = average velocity of all particles

      m = mass of particle

      KEave = 3/2 ∙ R ∙ T

      T = 2/3 ∙ KEave ∙ 1/R

      where R = universal gas constant = 8.31451 J/(mol∙K)

      T = temperature of core in degrees Kelvin

    9. Further it is assumed that since all velocities are much smaller than the speed of light, Eistenian corrections to Newtonian mechanics are minor. This means that Newton’s Laws of Motion hold without significant error. This is enough to guarantee the Law of Reflection: angle of incidence equals the angle of reflection.

 

The Reactor

To harbor the tremendous energies involved, reactors were designed in which controlled fission could occur. The captured energy is used to heat water to produce steam to run turbine generators, in much the same way that a coal-burning power plant, to generate electricity. In the reactor core, either uranium that has been enriched to approx. 3% U-235 (natural uranium occurs mostly as U-238) or pure uranium-235, is housed in cylinders. A moderator surrounds the cylinders to slow down the neutrons so that the uranium fuel can capture them more efficiently. Control rods, composed of substances that absorb neutrons, are used to regulate the power level of the reactor. The reactor is designed so that should a malfunction occur, the control rods are automatically inserted into the core to stop the reaction. A liquid (usually water) is circulated throughout the core to extract the heat generated by the energy of fission; the energy can then be passed via a heat exchanger to water in the turbine system. A layer of material called the reflector surrounds the core, which reflects escaping neutrons back into the core. In turn the reflector is surrounded by a thermal and biological shield. This extra layer absorbs stray neutrons and radiation to protect the personnel working around the reactor; it also functions to contain any radiation during an accidental core meltdown.

 

Reactor Simplifications

    1. The coolant system that removes heat from the core is modeled simply as a constant decrease in temperature per unit time. Only the reactore core is modeled; the heat distribution system and the electrical turbine is not.
    2. All uranium is assumbed to be 100% pure U-235.
    3. The moderator is modeled by controlling the velocities of nuetrons.
    4. The action of the control rods is simply integrated into the variable that represents the number of nuetrons that are released per fission event.
    5. We assume that all nuetrons are reflected by the reflector and thermal shield.

Results

Normal Operation

Since we are measuring the affect of a change, rather than absolute quantities, all units have been scaled up to allow easier manipulations. The following conditions were used as reasonable starting values:

Volume of reactor (Vr)

100 x 100 x 100

Volume of uranium (Vu)

2.35 x 2.35 x 2.35

Volume of neutron (Vn)

0.01 x 0.01 x 0.01

Mass of uranium (Mu)

0.235

Mass of neutron (Mn)

0.001

Total number of particles (Np)

10000

Ratio of uranium to neutrons (Ru:n)

99::1

Number of neutrons released per fission event (Nn)

2

Activation energy (Eact)

0

This simulation was started on Saturday, January 02, 1999 at approx. 10:44 pm, and was run overnight for 10 time units with a time step of 0.01. On Sunday, January 03, 1999 at approx. 10:46 am the simulation was prematurely halted at time unit 8.00. The graphed results can be seen below (for the full data set, see Appendix C).

Notice that the reactor core has reached a dynamic equilibrium state at approx. 9375 temperature units, and has maintained the equilibrium position for the duration of the simulation. To appreciate the true dynamic nature of this equilibrium, examine the zoomed -in view of the data. Note especially the dynamic hovering around 9375 during the last second of the simulation.

Catastrophic Conditions

The reactor has reached normal operating conditions under the estimated working values, and should maintain at equilibrium indefinitely. To investigate the condition of a runaway reactor, we can model the removal of all control rods by modifying the Nn (number of neutrons released per fission event) variable. By increasing this value from two to four, we see that the reactor temperature increases out of control.

Note that only after 1.2 time units, the temperature of the core has reached a celestial 250,000 temperature units, and no end is in sight. At that high a temperature, it is clear that a meltdown would occur. This is exactly what happened at Chernobyl. After fixing a problem with the coolant distribution system, the workers at Chernobyl decided to test the whole reactor during a short downtime period. The operators thought that the reactor temperature was not increasing fast enough, so they raised most of the rods, in an effort to increase energy output. When they lowered the last rod, the safety system activated, releasing the emergency rods, and the reaction halted. The operators decided to get the manager to shutdown the failsafe system, which he did. The operators proceeded to raise the rods once again. As soon as the last rod was raised, they realized that the temperature was increasing out of control, but it was too late… seconds later, the reactor exploded, sending the ten ton reactor lid five miles into the air, and spewing millions of tons of radioactive material from the core. This was a disaster that could have been avoided; this simulation gives us an insight into the kinds of core temperatures just before meltdown.

Conclusion

 

There is still much to be learned from simulations of this kind. An interesting direction is to investigate the affect of initial temperature, concentrations of reactants, ratio of neutrons to uranium nuclei, and activation energy on the properties of the reactor throughout time. Another possibility is to investigate a more general reactor – such as simulating more general chemical equations. This would involve assigning to each particle a representative Schrodinger equation, and following its eigenstate through time. Simulation of some large-scale structure in the universe, such as our Solar System, is another feasible direction with minor adjustments. Both of these extensions would involve the addition of inter-particle forces to account for the affect of gravity or electrostatic attraction and repulsion.

Simulation of all physical parameters would be difficult, however, and most likely impossible using current technology. Simulating only 10,000 particles took an entire day, and real reactions contain millions of billions of particles. Even using a Cray Supercomputer, a useful simulation would take years. For that reason, simulation as a means of predicting experimental values precisely remains a dream for the future.

The great velocity (pun intended) of computational improvement in recent years, as well as the development of the quantum computer (which can simulate 2N classical bits in just N quantum bits), may open new doors in physical simulation. I dream of a day when computer scientists (having become physicists!) will be able to predict the future states of our Universe. But until that day comes, chemists will have to continue to play with their test tubes, and physicists will not be able to abandon their particle accelerators just yet. But the day will come when humanity will ask of the greatest computer ever conceived the Ultimate Question of Life, the Universe, and Everything, and I can almost imagine what the answer several million years hence will be… 42.

Appendix A: Source Code

/* Fission.H */

#ifndef fission_h

#define fission_h

#include <math.h> // for sqrt()

#include <stdlib.h> // for rand(), srand()

#include <time.h> // for time()

#include <iostream.h>

#include <fstream.h>

template<class field>

struct vector3d

{

field x;

field y;

field z;

void operator=( const vector3d& v )

{

x = v.x;

y = v.y;

z = v.z;

};

vector3d operator*( double s )

{

x *= s;

y *= s;

z *= s;

return *this;

};

};

struct particle

{

char name; // identifier

double mass; // atomic mass

vector3d<double> size; // dimensions

vector3d<double> loc; // 3D coordinate location

vector3d<double> vel; // 3D velocity vector

double KE() const // kinetic energy

{

double norm = sqrt(vel.x*vel.x+vel.y*vel.y+vel.z*vel.z);

// |(x,y,z)| = sqrt(x^2+y^2+z^2)

return 0.5*mass*norm*norm;

// KE = 1/2*m*u^2

};

 

void update(double dt)

// update coordinates based on velocity and elapsed time

{

loc.x += vel.x*dt;

loc.y += vel.y*dt;

loc.z += vel.z*dt;

};

void operator=( const particle& p )

{

name = p.name;

mass = p.mass;

size = p.size;

loc = p.loc;

vel = p.vel;

};

};

class reactor

{

public:

reactor( double w, double l, double h );

void configCore( particle* c, int length );

void configInjector( double x, double y, double z );

void configNuclearParam( double E_act, double num_nuetron );

void run( double length, double step );

// precondition: reactor has been configured

private:

particle* core; // reactor core

int num_part; // number of particles in core

vector3d<double> size; // dimensions of core

vector3d<double> injector; // location of nuetron injector

double temp; // core temperature

double press; // core pressure

double E_act; // activation energy (in joules)

double num_nuetron; // number of nuetrons released per fission event

bool test( double ax, double ay, double az, double w, double l, double h, double bx, double by, double bz );

bool collideParticle( particle& a, particle& b );

void reboundParticle( particle& a, particle& b);

bool collideContainer( particle& a );

void updateDisplay( double time );

};

 

 

inline double random( double lower, double upper )

// returns random decimal between lower and upper

{

return double(rand())/pow(2,15)*(upper-lower)+lower;

};

#endif

 

/* Fission.CPP */

#include "fission.h"

particle U, n; // global definitions of Uranium-235 and nuetron

ofstream fout("data.txt"); // output file

reactor::reactor( double w, double l, double h)

{

size.x = w;

size.y = l;

size.z = h;

num_part = 0;

srand( (unsigned) time(NULL) ); // seed random generator

}

void reactor::configCore( particle* c, int length )

{

num_part = length;

core = new particle[length];

for( int i=0; i<num_part; i++ )

core[i] = c[i];

}

void reactor::configInjector( double x, double y, double z )

{

injector.x = x;

injector.y = y;

injector.z = z;

}

void reactor::configNuclearParam( double Act_e, double N_n )

{

E_act = Act_e;

num_nuetron = N_n;

}

void reactor::run( double length, double step )

{

int i,j;

double time=0;

while( time<length )

{

time += step;

temp = 0;

press = 0;

for( i=0; i<num_part; i++ )

{

temp += core[i].KE();

core[i].update(step);

collideContainer(core[i]);

for( j=i+1; j<num_part; j++ )

{

if( collideParticle(core[i],core[j]) )

reboundParticle(core[i],core[j]);

}

}

temp = temp/num_part;

updateDisplay( time );

}

}

bool reactor::collideParticle( particle& a, particle& b )

// returns true if a collides with b

{

return(

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x,b.loc.y,b.loc.z) ||

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x+a.size.x,b.loc.y,b.loc.z) ||

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x,b.loc.y+a.size.y,b.loc.z) ||

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x,b.loc.y,b.loc.z+a.size.z) ||

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x+a.size.x,b.loc.y+a.size.y,b.loc.z) ||

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x+a.size.x,b.loc.y,b.loc.z+a.size.z) ||

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x,b.loc.y+a.size.y,b.loc.z+a.size.z) ||

test(a.loc.x,a.loc.y,a.loc.z,a.size.x,a.size.y,a.size.z,b.loc.x+a.size.x,b.loc.y+a.size.y,b.loc.z+a.size.z)

);

}

 

 

void reactor::reboundParticle( particle& a, particle& b)

{

if( (a.name=='n' && b.name=='U') ||

(a.name=='U' && b.name=='n') &&

a.KE()+b.KE() > E_act )

{

/* if collision of Uranium-235 and nuetron

and energy of collision greater than activation energy

then products created and energy released */

a = U;

a.name = 'X'; // Ba-141

a.mass = 0.141;

a.vel.x = random(a.vel.x*1.05,a.vel.x*1.1);

a.vel.y = random(a.vel.y*1.05,a.vel.y*1.1);

a.vel.z = random(a.vel.z*1.05,a.vel.z*1.1);

b = U;

b.name = 'Y'; // Kr-92

b.mass = 0.092;

b.vel.x = random(b.vel.x*1.05,b.vel.x*1.1);

b.vel.y = random(b.vel.y*1.05,b.vel.y*1.1);

b.vel.z = random(b.vel.z*1.05,b.vel.z*1.1);

while( num_nuetron>0 )

{

n.loc = a.loc;

n.vel.x = random(a.vel.x*1.05,a.vel.x*1.1);

n.vel.y = random(a.vel.y*1.05,a.vel.y*1.1);

n.vel.z = random(a.vel.z*1.05,a.vel.z*1.1);

core[num_part] = n;

num_part++;

num_nuetron--;

}

}

else

{

/* if collision ineffective, particles rebound elastically */

vector3d<double> temp;

temp = a.vel;

a.vel = b.vel;

b.vel = temp;

}

}

bool reactor::test( double ax, double ay, double az, double w, double l, double h, double bx, double by, double bz )

{

return((ax<=bx)&&(bx<=ax+w) && (ay<=by)&&(by<=ay+l) && (az<=bz)&&(bz<=az+h));

}

 

bool reactor::collideContainer( particle& a )

{

if( a.loc.x <= 0 || a.loc.x >= size.x )

a.vel.x = -a.vel.x;

else if( a.loc.y <= 0 || a.loc.y >= size.y )

a.vel.y = -a.vel.y;

else if( a.loc.z <= 0 || a.loc.z >= size.z )

a.vel.z = -a.vel.z;

else

return false;

press++;

return true;

}

void reactor::updateDisplay( double time )

{

cout << time << '\t' << temp << "\t\t" << press << endl;

fout << time << '\t' << temp << "\t\t" << press << endl;

}

void main( )

{

particle* C;

C = new particle[10000];

U.name = 'U';

U.mass = 0.235;

U.size.x = 2.35;

U.size.y = 2.35;

U.size.z = 2.35;

for( i=0; i<9900; i++ ) {

U.loc = random(0,100);

U.vel = random(90,110);

C[i] = U;

}

n.name = 'n';

n.mass = 0.001;

n.size.x = 0.01;

n.size.y = 0.01;

n.size.z = 0.01;

for( i=9900; i<10000; i++ ) {

n.loc = random(0,100);

n.vel = random(90,110);

C[i] = n;

}

reactor R(100,100,100);

R.configCore(C,10000);

R.configNuclearParam(0,2);

R.run(10,0.01);

}

Appendix B: New Fractal

Introduction

While simulating uranium-235 fission, I noticed strange behavior of the particles when I installed a force-field generator. I decided to plot the motion of just a single particle under the influence of this force. I coded this routine in Visual Basic because I thought I was only debugging my C++ program. I plotted just the two-dimentional cross-section where z=0, and I got something I did not quite expect!

I was thinking… "bug in program while simulating particle in force-field!" That reminded me of the fractal that the mathematician Mandelbrot discovered when he thought he found a bug in his program. After checking his calculations by hand, he realized it was not a bug, but a fractal! That also brought to mind the work of the physicist Lorenz who discovered another fractal while working with thermodynamics data. It was too much of a coincidence that the image that I saw reminded me of a fractal, that I thought it was only a bug, and that I was working with physical data! I decided to investigate further…

Even though Mandelbrot and Lorenz’ fractals were in full color, the one I saw was only in black and white. I thought about how Newton’s fractal generates its color – by mapping the number of iterations to reach a root to a color. This gave me an idea – I decided to plot the course of the particle, and to color any single location with the kinetic energy of the particle at that moment in time. (Kinetic energy is the energy of motion and is defined as ½*mass*velocity2.)

The results I got really surprised me – I was looking at a full color fractal! The image was highly sensitive to initial conditions, a property all fractals share. It was also self-contained, in that any section exactly replicated the whole, another property of fractals. I think some of the images make wonderful wallpaper, a third property many fractals share.

Source Code

Sub Main

' Randomize

' random "data.txt", num_par, picMain

load "data.txt", txtNum.Text

run picMain

End Sub

Public Const num_par = 1

Public par(1 To num_par) As Particle

Type Particle

pos_x As Double

pos_y As Double

vel_x As Double

vel_y As Double

force_x As Double

force_y As Double

radius As Double

mass As Double

End Type

Sub draw(par As Particle, pic As PictureBox)

Dim color As Double

color = 1 / 2 * par.mass * (par.vel_x ^ 2 + par.vel_y ^ 2) * &HFFFFFF

pic.FillColor = color

pic.Circle (par.pos_x, par.pos_y), par.radius, color

End Sub

Sub load(filename As String, num_loc As Integer)

Dim i As Integer, j As Integer

Dim blank As Double

Open filename For Input As #1

For j = 1 To num_loc

For i = 1 To num_par

Input #1, par(i).pos_x

Input #1, par(i).pos_y

Input #1, par(i).vel_x

Input #1, par(i).vel_y

Input #1, par(i).force_x

Input #1, par(i).force_y

Input #1, par(i).radius

Input #1, par(i).mass

Next i

Input #1, blank

Next j

Close #1

End Sub

Sub random(filename As String, num_par As Integer, pic As PictureBox)

Dim i As Integer

Open filename For Output As #1

For i = 1 To num_par

Print #1, Rnd * pic.Width 'pos_x

Print #1, Rnd * pic.Height 'pos_y

Print #1, Rnd * 100 'vel_x

Print #1, Rnd * 100 'vel_y

Print #1, Rnd * 0.000001 'force_x

Print #1, Rnd * 0.000001 'force_y

Print #1, 10 'radius

Print #1, 0.0000005 'mass

Next i

Close #1

End Sub

Sub run(pic As PictureBox)

Dim color As Double

color = &HFFFFFF

Do

For i = 1 To num_par

draw par(i), pic

update par(i), pic

Next i

Loop

End Sub

Sub update(ByRef par As Particle, pic As PictureBox)

par.pos_x = par.pos_x + par.vel_x

par.pos_y = par.pos_y + par.vel_y

If par.pos_x - par.radius < 0 Or par.pos_x + par.radius > pic.Width Then

par.vel_x = -par.vel_x

End If

If par.pos_y - par.radius < 0 Or par.pos_y + par.radius > pic.Height Then

par.vel_y = -par.vel_y

End If

par.vel_x = par.vel_x + par.force_x

par.vel_y = par.vel_y + par.force_y

End Sub

Initial Conditions

Initial conditions can be generated randomly by a call to random() or entered manually into ‘data.txt’. Here are some interesting initial conditions that produce wonderful fractals.

 

98.12349

5325.065

40.7245

35.4519

4.53527569770813E-06

4.14032697677612E-05

10

0.00005

6646.896

2548.131

26.24342

38.35558

5.35045266151428E-06

5.92458248138428E-05

10

0.00005

4938.833

3733.968

28.97593

14.47812

3.01948010921478E-05

7.74740099906921E-05

10

0.00005

2913.152

5764.135

22.19111

24.67633

2.99430310726166E-05

9.54168200492859E-05

10

0.00005

6720.758

3285.285

2.402815

46.5107

6.16199314594269E-05

9.9836802482605E-05

10

0.00005

1532.918

2752.736

27.48037

24.03073

1.74836337566376E-05

5.67940354347229E-05

10

0.00005

5100

3991.31

26.33623

7.52297

9.86713230609894E-05

7.93076276779175E-05

10

0.00005

2913.152

5764.135

22.19111

24.67633

2.99430310726166E-05

9.54168200492859E-05

10

0.00005

6981.496

3293.477

16.54002

17.41086

1.88483655452728E-05

9.27633166313171E-07

10

0.00000005

373.9109

3403.953

5.328688

21.32683

1.11606419086456E-06

2.79510855674744E-05

10

0.0000005

154.3172

1243.764

43.27494

38.76859

8.13270032405853E-06

1.67262017726898E-05

10

0.0000005

6601.022

5285.118

73.17905

36.00884

9.18186008930206E-05

3.83914709091187E-06

10

0.0000005

6404.5

5680.715

3.967282

5.251133

3.86817395687103E-05

4.63190972805023E-05

10

0.0000005

1861.048

1020.668

35.60353

35.30312

2.57404148578644E-05

8.42517614364624E-06

10

0.0000005

Sample Images

 

Appendix C: Data

Normal Operation

(time, temperature)

0.01, 3508.92

0.02, 6283.89

0.03, 6195.85

0.04, 6183.65

0.05, 6395.21

0.06, 6542.14

0.07, 6653.35

0.08, 7050.34

0.09, 7086.44

0.1, 6938.86

0.11, 7328.89

0.12, 7484.74

0.13, 7728.36

0.14, 7631.29

0.15, 7675.44

0.16, 7952.15

0.17, 8345.08

0.18, 8034.85

0.19, 8077.46

0.2, 8497.84

0.21, 8386.79

0.22, 8669.32

0.23, 8402.69

0.24, 8606.12

0.25, 8711.55

0.26, 9021.29

0.27, 8829.74

0.28, 8851.72

0.29, 8806.3

0.3, 8925.08

0.31, 8798.5

0.32, 8984.9

0.33, 9080.31

0.34, 9150.35

0.35, 8947.18

0.36, 9252.83

0.37, 9002.4

0.38, 9135.5

0.39, 9134.15

0.4, 9180.44

0.41, 9110.67

0.42, 9289.74

0.43, 9242.41

0.44, 9133.39

0.45, 9262.61

0.46, 9000.99

0.47, 9200.97

0.48, 9063.71

0.49, 9273.15

0.5, 9235.52

0.51, 9309.81

0.52, 9310.72

0.53, 9267.76

0.54, 9232.68

0.55, 9281.8

0.56, 9485.15

0.57, 9298.51

0.58, 9256.91

0.59, 9433.94

0.6, 9188.18

0.61, 9630.65

0.62, 9277.19

0.63, 9270.53

0.64, 9390.12

0.65, 9268.53

0.66, 9563.56

0.67, 9444.23

0.68, 9218.11

0.69, 9332.75

0.7, 9381.9

0.71, 9338.15

0.72, 9232.68

0.73, 9381.73

0.74, 9223.74

0.75, 9367.51

0.76, 9000.39

0.77, 9206.23

0.78, 9398.03

0.79, 9319.96

0.8, 9334.31

0.81, 9273.6

0.82, 9097.87

0.83, 9241.14

0.84, 9236.6

0.85, 9272.18

0.86, 9180.06

0.87, 9382.34

0.88, 9178.52

0.89, 9398.3

0.9, 9163.89

0.91, 9164.42

0.92, 9077.98

0.93, 9192.16

0.94, 9532.71

0.95, 9549.43

0.96, 9192.06

0.97, 9545.76

0.98, 9488.36

0.99, 9267.78

1, 9192.68

1.01, 9476.69

1.02, 9257.37

1.03, 9256.65

1.04, 9512.48

1.05, 9317.6

1.06, 9352.45

1.07, 9510.28

1.08, 9334.53

1.09, 9220.17

1.1, 9428.79

1.11, 9385.46

1.12, 9073.44

1.13, 9564.1

1.14, 9366.04

1.15, 9321.2

1.16, 9449.63

1.17, 9538.38

1.18, 9488.96

1.19, 9344.95

1.2, 9365.96

1.21, 9301.63

1.22, 9261.71

1.23, 9232.84

1.24, 9523.2

1.25, 9311.69

1.26, 9430.34

1.27, 9264.38

1.28, 9363.13

1.29, 9369.3

1.3, 9349.58

1.31, 9489.07

1.32, 9406.83

1.33, 9454.54

1.34, 9302.6

1.35, 9516.42

1.36, 9350.76

1.37, 9197.83

1.38, 9515.38

1.39, 9627.62

1.4, 9403.47

1.41, 9311.98

1.42, 9303.44

1.43, 9424.92

1.44, 9419.46

1.45, 9340.45

1.46, 9341.93

1.47, 9501.34

1.48, 9431.3

1.49, 9376.04

1.5, 9448.08

1.51, 9249.12

1.52, 9179.99

1.53, 9379.22

1.54, 9211.52

1.55, 9521.79

1.56, 9311.94

1.57, 9340.79

1.58, 9290.74

1.59, 9608.71

1.6, 9286.05

1.61, 9528.73

1.62, 9492.6

1.63, 9456.25

1.64, 9388.25

1.65, 9340.43

1.66, 9501.64

1.67, 9359.51

1.68, 9379.92

1.69, 9428.98

1.7, 9382.5

1.71, 9429.75

1.72, 9613.52

1.73, 9274.84

1.74, 9411.09

1.75, 9420.43

1.76, 9124.85

1.77, 9525.1

1.78, 9317.19

1.79, 9392.07

1.8, 9413.63

1.81, 9316.01

1.82, 9361.48

1.83, 9459

1.84, 9449.89

1.85, 9453.5

1.86, 9336.55

1.87, 9355.44

1.88, 9367.03

1.89, 9463.35

1.9, 9457.09

1.91, 9381.05

1.92, 9449.51

1.93, 9317.03

1.94, 9279.21

1.95, 9332.31

1.96, 9423.03

1.97, 9423.16

1.98, 9399.12

1.99, 9388

2, 9457.96

2.01, 9470.19

2.02, 9305.61

2.03, 9415.35

2.04, 9332.25

2.05, 9520.23

2.06, 9363.22

2.07, 9380.19

2.08, 9331.67

2.09, 9449.25

2.1, 9343.84

2.11, 9252.56

2.12, 9355.06

2.13, 9612.21

2.14, 9321.37

2.15, 9376.91

2.16, 9392.55

2.17, 9273.38

2.18, 9416.45

2.19, 9446.44

2.2, 9436.77

2.21, 9304.87

2.22, 9315.47

2.23, 9557.6

2.24, 9364.54

2.25, 9478.66

2.26, 9359.37

2.27, 9438.36

2.28, 9316.5

2.29, 9449.9

2.3, 9312.42

2.31, 9360.41

2.32, 9347.35

2.33, 9639.16

2.34, 9321.01

2.35, 9490.66

2.36, 9351.37

2.37, 9358.05

2.38, 9416.89

2.39, 9322.4

2.4, 9376.91

2.41, 9576.83

2.42, 9318.43

2.43, 9294.94

2.44, 9478.13

2.45, 9332

2.46, 9352.61

2.47, 9445.21

2.48, 9367.03

2.49, 9382.93

2.5, 9449.78

2.51, 9342.73

2.52, 9342.27

2.53, 9466.2

2.54, 9418.14

2.55, 9352.03

2.56, 9336.67

2.57, 9432.43

2.58, 9415.18

2.59, 9345.06

2.6, 9298.15

2.61, 9472.01

2.62, 9380.06

2.63, 9486.79

2.64, 9484.58

2.65, 9395.22

2.66, 9414.92

2.67, 9475.95

2.68, 9490.97

2.69, 9365.55

2.7, 9349.04

2.71, 9451.92

2.72, 9430.1

2.73, 9286.76

2.74, 9406.25

2.75, 9398.07

2.76, 9389.99

2.77, 9360.06

2.78, 9353.18

2.79, 9450.17

2.8, 9465.57

2.81, 9368.44

2.82, 9420.98

2.83, 9405.08

2.84, 9350.29

2.85, 9347.79

2.86, 9399.11

2.87, 9600.18

2.88, 9309.6

2.89, 9350.24

2.9, 9389.24

2.91, 9440.65

2.92, 9483.18

2.93, 9415.02

2.94, 9348.89

2.95, 9407.1

2.96, 9479.69

2.97, 9410.83

2.98, 9435.17

2.99, 9461.15

3, 9460.95

3.01, 9367.06

3.02, 9367.72

3.03, 9335.13

3.04, 9424.97

3.05, 9360.19

3.06, 9477

3.07, 9487.77

3.08, 9337.84

3.09, 9344.98

3.1, 9295.89

3.11, 9539.6

3.12, 9473.33

3.13, 9313.33

3.14, 9284.98

3.15, 9364.12

3.16, 9367.57

3.17, 9408.33

3.18, 9279.58

3.19, 9329.17

3.2, 9202.95

3.21, 9419.9

3.22, 9473.54

3.23, 9406.11

3.24, 9494.96

3.25, 9381.61

3.26, 9419.93

3.27, 9263.34

3.28, 9434.96

3.29, 9363.25

3.3, 9396.25

3.31, 9525.6

3.32, 9414.49

3.33, 9223.5

3.34, 9471.17

3.35, 9361.5

3.36, 9380.67

3.37, 9353.45

3.38, 9368.47

3.39, 9417.47

3.4, 9405.78

3.41, 9377.7

3.42, 9364.24

3.43, 9375.1

3.44, 9363.97

3.45, 9359.58

3.46, 9380.52

3.47, 9280.45

3.48, 9386.79

3.49, 9377.34

3.5, 9398.28

3.51, 9347.39

3.52, 9279.7

3.53, 9427.76

3.54, 9409.99

3.55, 9431.59

3.56, 9435.06

3.57, 9355.43

3.58, 9403.61

3.59, 9435.78

3.6, 9341.63

3.61, 9433.67

3.62, 9426.94

3.63, 9479.59

3.64, 9422.97

3.65, 9349.48

3.66, 9466.46

3.67, 9348

3.68, 9383.86

3.69, 9492.16

3.7, 9387.33

3.71, 9348.96

3.72, 9382.12

3.73, 9327.01

3.74, 9297.18

3.75, 9520.77

3.76, 9382.39

3.77, 9350.35

3.78, 9454.42

3.79, 9398.29

3.8, 9363.53

3.81, 9372.67

3.82, 9469.05

3.83, 9362.23

3.84, 9382.79

3.85, 9391.67

3.86, 9466.33

3.87, 9393.87

3.88, 9312.56

3.89, 9436.22

3.9, 9382.28

3.91, 9350.39

3.92, 9353.1

3.93, 9435.91

3.94, 9383.38

3.95, 9435.56

3.96, 9396.23

3.97, 9344.13

3.98, 9382.36

3.99, 9309.08

4, 9337.99

4.01, 9443.8

4.02, 9399.12

4.03, 9377.92

4.04, 9273.81

4.05, 9332.23

4.06, 9363.81

4.07, 9444.13

4.08, 9365.61

4.09, 9409.06

4.1, 9380.39

4.11, 9362.44

4.12, 9384.97

4.13, 9434.18

4.14, 9434.47

4.15, 9391.16

4.16, 9423.24

4.17, 9465.15

4.18, 9424.7

4.19, 9431.83

4.2, 9311.21

4.21, 9301.87

4.22, 9382.71

4.23, 9332.93

4.24, 9431.74

4.25, 9389.42

4.26, 9370.85

4.27, 9379.55

4.28, 9345.6

4.29, 9515.23

4.3, 9342.09

4.31, 9390.46

4.32, 9467.96

4.33, 9419.95

4.34, 9359.63

4.35, 9364.59

4.36, 9408.7

4.37, 9393.04

4.38, 9433.81

4.39, 9419.47

4.4, 9381.89

4.41, 9363.2

4.42, 9379.65

4.43, 9379.36

4.44, 9366.83

4.45, 9349.82

4.46, 9380.75

4.47, 9392.9

4.48, 9308.17

4.49, 9346.52

4.5, 9409.26

4.51, 9392.79

4.52, 9397.56

4.53, 9395.4

4.54, 9427.85

4.55, 9392.4

4.56, 9423.2

4.57, 9359.29

4.58, 9381.36

4.59, 9395.54

4.6, 9422.24

4.61, 9352.18

4.62, 9421.86

4.63, 9352.77

4.64, 9467

4.65, 9348.72

4.66, 9422.96

4.67, 9408.74

4.68, 9378.8

4.69, 9347.39

4.7, 9377.38

4.71, 9393.46

4.72, 9379.9

4.73, 9387.3

4.74, 9383

4.75, 9391.07

4.76, 9342.12

4.77, 9420.99

4.78, 9458.38

4.79, 9362.75

4.8, 9380.95

4.81, 9389.88

4.82, 9384.16

4.83, 9366.02

4.84, 9380.93

4.85, 9398.09

4.86, 9407.88

4.87, 9316.52

4.88, 9426.88

4.89, 9406.94

4.9, 9411.78

4.91, 9390.67

4.92, 9441.63

4.93, 9446.66

4.94, 9396.65

4.95, 9503.84

4.96, 9355.46

4.97, 9404.45

4.98, 9397.72

4.99, 9402.36

5, 9312.65

5.01, 9405.89

5.02, 9395.53

5.03, 9499.05

5.04, 9436.3

5.05, 9405.25

5.06, 9460.8

5.07, 9388.52

5.08, 9350.4

5.09, 9389.28

5.1, 9378.75

5.11, 9390.94

5.12, 9369.33

5.13, 9495.19

5.14, 9388.28

5.15, 9406.72

5.16, 9426.29

5.17, 9404.18

5.18, 9482.02

5.19, 9365.5

5.2, 9397.04

5.21, 9362.17

5.22, 9397.55

5.23, 9347.99

5.24, 9425.98

5.25, 9403.29

5.26, 9435.99

5.27, 9437.11

5.28, 9397.27

5.29, 9406.67

5.3, 9369.72

5.31, 9408.16

5.32, 9357.17

5.33, 9404.34

5.34, 9398.59

5.35, 9373.88

5.36, 9398.38

5.37, 9404.33

5.38, 9386.49

5.39, 9404.46

5.4, 9499.21

5.41, 9397.8

5.42, 9355.6

5.43, 9405.84

5.44, 9397.83

5.45, 9473.34

5.46, 9396.92

5.47, 9346.48

5.48, 9417.44

5.49, 9404.98

5.5, 9357.39

5.51, 9404.32

5.52, 9395.46

5.53, 9407.71

5.54, 9371.73

5.55, 9381.83

5.56, 9372.17

5.57, 9365.8

5.58, 9395.11

5.59, 9405.26

5.6, 9381.08

5.61, 9352.17

5.62, 9353.06

5.63, 9404.73

5.64, 9481.81

5.65, 9437.88

5.66, 9397.65

5.67, 9404.56

5.68, 9398.83

5.69, 9405.79

5.7, 9395.76

5.71, 9403.55

5.72, 9397.31

5.73, 9405.37

5.74, 9397.39

5.75, 9406.56

5.76, 9396.66

5.77, 9448.54

5.78, 9366.27

5.79, 9406.63

5.8, 9393.97

5.81, 9435.13

5.82, 9394.92

5.83, 9376.8

5.84, 9396.8

5.85, 9405.22

5.86, 9396.84

5.87, 9436.35

5.88, 9397.26

5.89, 9406.07

5.9, 9397.77

5.91, 9406.3

5.92, 9395.48

5.93, 9380.39

5.94, 9395.58

5.95, 9408.43

5.96, 9451.51

5.97, 9384.44

5.98, 9343.66

5.99, 9384.6

6, 9301.61

6.01, 9382.42

6.02, 9374.45

6.03, 9382.08

6.04, 9373.06

6.05, 9383.65

6.06, 9372.99

6.07, 9381.95

6.08, 9376.65

6.09, 9383.36

6.1, 9373.87

6.11, 9383.06

6.12, 9370.91

6.13, 9413.41

6.14, 9373.95

6.15, 9385.33

6.16, 9342.52

6.17, 9336.98

6.18, 9372.19

6.19, 9384.98

6.2, 9400.74

6.21, 9353.9

6.22, 9341.58

6.23, 9384.74

6.24, 9372.2

6.25, 9384.73

6.26, 9341.63

6.27, 9384.31

6.28, 9372.28

6.29, 9382.52

6.3, 9402.34

6.31, 9383.93

6.32, 9372.1

6.33, 9413.65

6.34, 9372.62

6.35, 9382.68

6.36, 9343.6

6.37, 9380.5

6.38, 9374.4

6.39, 9384.16

6.4, 9372.44

6.41, 9383.32

6.42, 9372.97

6.43, 9381.21

6.44, 9373.59

6.45, 9385.54

6.46, 9372.11

6.47, 9382.09

6.48, 9373.21

6.49, 9384.76

6.5, 9373.32

6.51, 9408.72

6.52, 9373.34

6.53, 9384.2

6.54, 9326.61

6.55, 9386.42

6.56, 9371.51

6.57, 9385.14

6.58, 9372.42

6.59, 9382.93

6.6, 9371.77

6.61, 9348.46

6.62, 9342.94

6.63, 9382.8

6.64, 9375.09

6.65, 9382.25

6.66, 9372.19

6.67, 9385.98

6.68, 9402.22

6.69, 9352.38

6.7, 9373.06

6.71, 9384.93

6.72, 9371.44

6.73, 9385.49

6.74, 9371.5

6.75, 9382.73

6.76, 9412.76

6.77, 9341.27

6.78, 9461.98

6.79, 9384.77

6.8, 9412.55

6.81, 9384.9

6.82, 9331.95

6.83, 9386.01

6.84, 9331.12

6.85, 9385.99

6.86, 9371.65

6.87, 9385.11

6.88, 9372.52

6.89, 9382.67

6.9, 9372.01

6.91, 9383.33

6.92, 9373.52

6.93, 9422.7

6.94, 9370.82

6.95, 9384.96

6.96, 9372.04

6.97, 9383.16

6.98, 9372.09

6.99, 9382.8

7, 9375.49

7.01, 9428.89

7.02, 9334.94

7.03, 9383.06

7.04, 9411.64

7.05, 9384.72

7.06, 9374.04

7.07, 9344.65

7.08, 9412.61

7.09, 9346.04

7.1, 9331.62

7.11, 9346.18

7.12, 9372.54

7.13, 9384.79

7.14, 9370.74

7.15, 9346.68

7.16, 9413.71

7.17, 9387.7

7.18, 9370.63

7.19, 9384.31

7.2, 9410.6

7.21, 9382.63

7.22, 9372.37

7.23, 9382.76

7.24, 9374.53

7.25, 9383.4

7.26, 9371.23

7.27, 9385.4

7.28, 9374.4

7.29, 9384.84

7.3, 9372.51

7.31, 9386.73

7.32, 9330.46

7.33, 9430.79

7.34, 9371.42

7.35, 9381.95

7.36, 9371.41

7.37, 9345.17

7.38, 9410.75

7.39, 9384.27

7.4, 9330.73

7.41, 9384.45

7.42, 9372.37

7.43, 9383.44

7.44, 9333.73

7.45, 9423.24

7.46, 9334.31

7.47, 9422.16

7.48, 9373.09

7.49, 9422.73

7.5, 9373.37

7.51, 9382.93

7.52, 9372.54

7.53, 9383.95

7.54, 9372.25

7.55, 9383.69

7.56, 9372.45

7.57, 9383.05

7.58, 9373.95

7.59, 9336.44

7.6, 9411.59

7.61, 9414.24

7.62, 9334.84

7.63, 9383.34

7.64, 9412.92

7.65, 9383.7

7.66, 9372.62

7.67, 9383.91

7.68, 9341.68

7.69, 9384.18

7.7, 9373.98

7.71, 9384.61

7.72, 9372.07

7.73, 9383.99

7.74, 9372.2

7.75, 9384.55

7.76, 9373.03

7.77, 9343.96

7.78, 9413.46

7.79, 9383.63

7.8, 9372.65

7.81, 9383.67

7.82, 9372.27

7.83, 9383.5

7.84, 9372.26

7.85, 9384.65

7.86, 9371.45

7.87, 9385.05

7.88, 9372.84

7.89, 9384.76

7.9, 9370.98

7.91, 9385.34

7.92, 9371.17

7.93, 9385.94

7.94, 9373.38

7.95, 9354.51

7.96, 9347.24

7.97, 9383.2

7.98, 9371.76

7.99, 9382.22

8, 9373.58

 

 

Catastrophic Conditions

(time, temperature)

0.01, 3508.95

0.02, 143484

0.03, 143649

0.04, 143699

0.05, 143880

0.06, 144055

0.07, 144334

0.08, 144436

0.09, 264942

0.1, 128980

0.11, 129286

0.12, 129932

0.13, 130043

0.14, 165339

0.15, 165843

0.16, 257079

0.17, 137927

0.18, 137866

0.19, 138187

0.2, 139222

0.21, 173568

0.22, 139848

0.23, 229937

0.24, 140155

0.25, 140334

0.26, 140623

0.27, 140945

0.28, 163513

0.29, 129274

0.3, 219526

0.31, 129685

0.32, 188211

0.33, 189886

0.34, 189915

0.35, 212206

0.36, 189910

0.37, 266239

0.38, 176069

0.39, 210850

0.4, 212170

0.41, 211355

0.42, 211573

0.43, 188978

0.44, 246744

0.45, 216223

0.46, 216475

0.47, 215757

0.48, 216771

0.49, 216886

0.5, 216927

0.51, 274060

0.52, 292810

0.53, 247333

0.54, 282784

0.55, 247387

0.56, 188924

0.57, 248186

0.58, 247432

0.59, 323268

0.6, 247332

0.61, 283281

0.62, 247945

0.63, 248201

0.64, 306452

0.65, 247570

0.66, 248033

0.67, 171634

0.68, 282568

0.69, 247125

0.7, 247958

0.71, 306365

0.72, 247925

0.73, 248162

0.74, 247202

0.75, 190459

0.76, 155689

0.77, 190586

0.78, 306222

0.79, 247879

0.8, 247789

0.81, 248187

0.82, 248197

0.83, 248788

0.84, 247971

0.85, 270278

0.86, 189583

0.87, 247807

0.88, 248223

0.89, 248034

0.9, 248071

0.91, 247946

0.92, 247745

0.93, 190504

0.94, 270942

0.95, 248084

0.96, 247653

0.97, 248104

0.98, 248217

0.99, 324580

1, 247587

1.01, 305750

1.02, 249207

1.03, 248451

1.04, 248778

1.05, 248503

1.06, 248228

1.07, 248120

1.08, 248127

1.09, 248043

1.1, 247319

1.11, 248405

1.12, 247887

1.13, 248094

1.14, 248137

1.15, 248427

1.16, 248352

1.17, 248030

1.18, 248272

1.19, 248168

1.2, 248149

1.21, 247607

1.22, 248159

1.23, 248558

1.24, 248314

1.25, 248484

 

References

 

Adams, Douglas. A hitchhiker’s guide to the galaxy.

Gale, Dr. Robert Peter, 1988. Final Warning: The Legacy of Chernobyl, Warner Books, Inc.

Kauzmann, Walter, 1957. Quantum Chemistry: An Introduction, Academic Press Inc.

Read, Piers Paul, 1993. The Story of the Heroes and Victims of Chernobyl, Random House, Inc.

Rickard, Graham, 1989. The Chernobyl Catastrophe, The Bookwright Press

Schichtel, Bret A., Husar, Rudolf B., 1995. Regional simulation of atmospheric pollutants with the capita monte carlo model. Center for air pollution and trend analysis, Washington University, St. Louis, Montana.

Zumdahl, Steven S., 1993. Chemistry, 3rd ed. D.C. Heath and Co., Massachusetts. pp. 995-996, 1016-1023.

Compton’s Interactive Encyclopedia, 1995. Compton’s NewMedia, Inc.