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Critical Mass of AGN-201K

Shim, Hyung Jin

Nuclear Engineering Department,

Seoul National University

(2)

 With the time dependence of L and the

b

i,eff of negligible significance, the reactivity

r

(t) and the effective source Q(t) become the driving terms of the point kinetics equations.

where n(t) = neutron density or total neutron population, Ci(t) = i-th group delayed neutron precursor density,

l

i = decay constant of the i-th group delayed neutron precursor,

L = prompt neutron generation time, which is the prompt neutron lifetime l divided by keff,

b

eff = effective delayed neutron fraction

b

i,eff = effective delayed neutron fraction of i-th delayed neutron precursor

group

Point Kinetics Equation with External Source

6

1 ,

( ) ( ) ( ) ( )

( ) ( ) ( ) ( 1, 2, ,6)

eff

i i

i i eff

i

i i

dn t n t C t Q t

dt

dC t n t C t i

dt

r b l

b l

   

L

  

L

(1a) (1b)

(3)

 When there are no external neutron sources,

 When there is an external source,

Time-Dependent Behavior at Critical Condition

Myung Hyun Kim, Reactor Experiment, Reactor Research & Education Center, Kyung Hee University (2018).

(4)

 For a subcritical system without any external source, the neutron population becomes negligible after long time as

 When there is an external source, Q(t), its steady-state solution can be written as

 From Eq. (3b), the following relationship is obtained

 By inserting Eq. (4) into Eq. (3a), one can obtain

Steady-State Solution of a Subcritical System

1 1

( ) exp( ) 0 ( 0)

n t  A  t  t 

(2)

( ) dn t

dt

6

1

( ) ( ) ( )

( )

eff

i i

i i

n t C t Q t dC t

dt

r b l

   

L 

,

( ) ( ) ( 1, 2, ,6)

i eff

i i

n t C t i

b l

  

L

(3a) (3b)

=0

=0

( )

i eff,

( ) ( 1, 2, ,6)

i

i

C t b n t i

 l 

L

(4)

0 r b

eff

n t ( )

i

 l

 

L

, i eff

i

b l L

6

1

( ) ( )

i

n t Q t

 

eff

( ) b n t

( ) ( )

n t Q t r

  L

(5)
(5)

 For a fixed strength of the external source, Q0, one can find that the neutron population at steady-state, denoted by n(∞), becomes inversely proportional to reactivity as

 Because every detector signal located at the critical assembly is proportional to n(t), Eq. (6a) can be written for its detector signal or count rate A as

Steady-State Solution of Sub. Sys. (Contd.)

( )

0

n Q

r

   L

(6a)

( )

0

A Q

r

   L

(6b)
(6)

Physical Interpretation

of the Critical Approach Equation

( )

0

n Q

r

   L

(6a)

( )

0

A Q

r

   L

(6b)
(7)

Number of Neutrons Existing in Subcritical System

0 g

1 g

g i

2 g

k

i

·S

 When the external source strength is given as Q0 [#/sec], it means that Q0lp neutrons are produced during this prompt neutron lifetime, lp.

 Then, how many numbers of neutrons exist in this subcritical system after a considerable time?

S=Q

0

l

p

k·S k

2

·S

0

  

2 3

1

0 0

( ) 1 1 1

p

Q l k

p

Q l Q

n S kS k S k S S

k k k k r

          L

   

=M

=source multiplication factor

(8)

Detector Signal vs. Reactivity

Approaching to the criticality,

ramp rate becomes low and takes more time to equilibrium.

( ) Q

0

n r

  L

(9)

 Why does it take longer time when the reactor approaches to the criticality compared with an initial deep subcritical state?

Question #1

Myung Hyun Kim, Reactor Experiment, Reactor Research & Education Center, Kyung Hee University (2018).

(10)

Example of Detector Signal vs. Reactivity

( )

0

A Q

r

   L

(6b)

Myung Hyun Kim, Reactor Experiment, Reactor Research & Education Center, Kyung Hee University (2018).

(11)

Inverse Count Rate vs. Reactivity

1 i

A A

1 i

A A

1 i

A A A A

1 i

0 0

0 i

1

i i i

A M

A M M

r

 r   ( )

0

A Q

r

   L

(6b)

0 0 i

i

A r  r A

Called 1/MExperiment and

(12)

Critical Mass Measurement

(1/M Experiment)

(13)

Critical Mass Approach

Myung Hyun Kim, Reactor Experiment, Reactor Research & Education Center, Kyung Hee University (2018).

(14)

Fuel Disks Making Core

Part Height Weight of 235U Function Fuel disk 1, 2, 3, 4 4×4[cm/disk] 4×102[g/disk]

Core Fuel disk 5, 6, 7 3×2[cm/disk] 3×58[g/disk]

Fuel disk 8, 9 2×1[cm/disk] 2×29[g/disk]

Thermal fuse* 2.2D×0.9H [cm]

4 g (double density fuel)

Safe shutdown Safety rod 1 & 2 4 fuel pieces

(16 cm) 2×14.5[g/rod] Shutdown Coarse control rod 4 fuel pieces

(16 cm) 14.5 g Control

Fine control rod 3 fuel pieces

(12 cm) 2.5 g Control

Totol 235U mass 690 g

23cm

* Melting point of U+polystyrene = 100ºC cf. Melting point of U+polyethylene = 200ºC

644g

(15)

Experimental Procedure

644.0g 658.5g 673.0g 675.5g

Myung Hyun Kim, Reactor Experiment, Reactor Research & Education Center, Kyung Hee University (2018).

(16)

Drawing of Count Ratio and Extrapolation

Myung Hyun Kim, Reactor Experiment, Reactor Research & Education Center, Kyung Hee University (2018).

(17)

0. Student operator should read all reactor conditions and write down at the worksheet first. They are temperatures at various locations, source position, neutron and

gamma radiation dose in the reactor hall. All students should confirm that neutron source is inserted inside of the reactor and all control rods are out. At this moment, there are no significant counts from all channels except two; channel #1 and #5.

Experimental Procedure

(18)

1. As the first step, two students should read cpm from channel #1 and #5 repeatedly to have a saturated values.

2. As the second step, one safety rod SR#1 is inserted as an addition of U-235 by

14.5g. Channel #1 & 5 is monitored to read saturated cpm. These records are sent to the working table to log on the spread sheet and make a graph.

Experimental Procedure (Contd.)

fuel region 16cm, 14.5g fuel

region 12cm, 2.5g

644.0g 658.5g

Myung Hyun Kim, Reactor Experiment, Reactor Research &

Education Center, Kyung Hee University (2018).

(19)

3. As the third step, another safety rod SR#2 is inserted as an addition of U-235 by 14.5g. Channel #1 & 5 is monitored again to read saturated cpm. These records are sent to the working table to log on the spread sheet and make two dots on the graph.

4. As the 4th step, a fine control rod FR is inserted as an addition of U-235 by 2.5g.

Channel #1 & 5 is monitored again to read saturated cpm. These records are sent to the working table to log on the spread sheet and make two dots on the graph.

5. As the 5th step, a coarse control rod CR is inserted by 4cm as an addition of U-235 by 2.52g (14.5g×4/23=2.52g). Channel #1 & 5 is monitored again to read saturated cpm. These records are sent to the working table to log on the spread sheet and

make two dots on the graph.

6. As the 6th step, a coarse control rod CR is inserted more by 4cm as an addition of U-235 by 2.52g (14.5g×4/23=2.52g). Channel #1 & 5 is monitored again to read saturated cpm. These records are sent to the working table to log on the spread sheet and make two dots on the graph.

7. As the 7th step, a coarse control rod CR is inserted more by 4cm as an addition of U-235 by 2.52g (14.5g×4/23=2.52g). Channel #1 & 5 is monitored again to read saturated cpm. These records are sent to the working table to log on the spread sheet and make two dots on the graph. From now on, all students should discuss whether experiment may proceed or not. Decision should be made based on the extrapolation prediction on the graph.

Experimental Procedure (Contd.)

673.0g

675.5g

Standard Procedure

(20)

 Students are asked to make a table for A0/Ai at each step-i. X-axis for a plot should be a mass of U-235. Mass of U-235 should be also calculated for each step-i.

Search for the Critical Mass

(21)

Different Searching Scenarios

(22)

Video for Exp. #3

(23)

Static State w/ Source → Source Out → Source In

Source Out

Source In

(24)

Discussion Points

(25)

Discussion Points (Contd.)

(26)

Consider Detector Positions for Question #2

Myung Hyun Kim, Reactor Experiment, Reactor Research & Education Center, Kyung Hee University (2018).

Referensi

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