Npre 402 Exams
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University of Illinois, Urbana Champaign *
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MISC
Subject
Electrical Engineering
Date
Dec 6, 2023
Type
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6
Uploaded by hhj1501
—
A
\
NPRE
402
Nuclear
Power
Engineering
Fall
2014,
First
Midterm
el
Please
answer
all
questions.
Use
the
back
of
the
answer
sheet
as
needed.
\
Name:
©\\e
oo
MeAcs
Question
1;
3
A
fusion
process
uses
the
;:B"
fusion
reaction
producing
a
C'?
nucleus
in
its
excited
state.
This
excited
C'?
nucleus
decays
to
Be®
and
He®.
Be®
within
10™
sec
further
decays
into
two
more
He
nuclei.
This
is
the
only
nuclear-energy
releasing
process
in
that
releases
fusion
energy
and
helium
nuclei,
but
no
initial
neutrons.
m(,H')
=1.0078250
amu,
m(,B")
=
11.0093055
amu,
m(,
He')
=
4.0026032
amu
1
amu
=931.481
MeV
]
t
v
et
98
o
Q=
93106
[(t
o5
oszosh)
Y
by
By
oC"
=
Rels,
Het
TS
es2
0
=
(3
0ot03n)]
ETBEE
T
et
ety
g
=
-
?
+
?
H
e
\
v
—
747
>
2
(,u
*6%”9\31\49.“-!
Question
2:
Compute
the
thicknesses
of
a
Pb
shield
that
would
attenuate
a
beam
of
1
MeV
gamma
rays
with
a
build-up
factor
of
B
=
2,
to
one
billionth
of
its
initial
strength,
given
that
its
linear
attenuation
coefficients
at
1
MeV
is
0.8
cm™.,
S
facenesS
=
Ux107!
e
|
Question
3:
The
isotope
g,
Thallium®®
has
a
half
life
@nd
c
b&ased-flman@;hnology
power
source
device.
It
decays
through
beta
emission
into
g,
with
a
ching
ratio
of
97.Dpercent
with
an
average
decay
energ
also
e_c_@&through
electron
capture
to
goHg™"*
with
a
branching
ratio
percent
with
a
decay
energy
0£-0.347
MeV.
N
Calculate
the
energy
release
per
decay
event
in
[MeV/disintegration]
Calculate
its
total
specific
activity
in
[Becquerels
/
gm].
Calculate
its
total
specific
activity
in
[Curies
/
gm].
Calculate
the
specific
power
generation
in
[Watts(th)
/
gm].
For
a
100
Watts
of
thermal
(Eower
in
a
Radioisotope
Heating
Unit
(RHU)
power
generator,
how
many
grams
of
g,
Thallium®*
are
needed?
6.
After
3.78
years
of
operation,
what
would
its
power
become?
Use:
1
MeV/sec
=
1.602x10™
Watts,
A,
=
0.602x10*
[nuclei/mole],
1
Curie
=
3.7x10'"°
Bq.
L
E
=
001
(p
16U
Mev)
+
6026
(0.
30
Mel)
40191007
MeV/dsimetiion
v
G
B9
(1)
N
-
g
S
G
ey
[
MW
\T\
0"
o
fi‘
\G
x\
%j@
31
NbxI10P
R
\
core.
|
X
=~
L\(O
\—\
\
l
q
3x1Q°
B
,
>Te
¢
m
—>
on
o\
N
2
N
.k\'w
,_’LX_‘\"\)
K
{q‘\
L
)
NPRE
402
Nuclear
Power
Engineering
Spring
2015,
First
Midterm
Please
answer
all
questions.
Show
details
of
your
calculations.
Use
the
back
of
the
answer
sheet
if
needed.
No
extra
sheets
are
{.
5-
Name;
Ta"}\o‘
427?5,
}
5
P,
P
/
v
Question
1
»\%
The
isotope
g
Thallium™
has
a
half-life
o{3.78
yearsyind
may
be
used
as
a
nanotechnology
and
Micro
Electro
NG
Mec?oa}nigal
Systems
(MEMS)
power
source.
T{i§@
pure
beta
emitter
without
gamma
rays
emission.
It
decays
into
N\“\
anb
witha
branchmgzgi\tio
of
97.1
percent
with
a
decay
energy
of
0.764
MeV/disintegration.
It
also
decays
through
N~
electron
capture
to
gHg™
with
a
branching
ratio
of
2.9
percent
with
a
decay
energy
of
0.347
MeV/disintegration.
%4
P
.
Calculate
the
average
energy
release
per
decay
event
in
[MeV/disintegration]
A
3.
Calculate
its
total
specific
activity
in
[Curies/gm).
1.
"
4
Calculate
the
specific
thermal
power
generation
in
[Watts(thygm].
Q“‘/
M
/8.
For
a
100
Watts
of
thermal
power
in
a
Radioisotope
Heating
Unit
(RHU)
power
generator,
how
many
grams
of
1e
nghalliumzo‘
are
needed?
A
\
/V
After
3.78
years
of
operation,
what
would
its
thermal
power
become?
By
7.
The
Cassini
space
probe
to
Saturn
needs
an
electrical
supply
of
1
kWe
(
kiloWatt(e))
of
power.
If
it
were
powered
2.
Calculate
its
total
specific
activity
in
[Becquerels/gm].
(
g
p-oe
by
a
Radioisotope
Thermoelectric
Generator
(RTG)
operating
at
a
conversion
efficiency
of
50
percent,
what
would
be
/PV
the
needed
amount
of 8,"I'ha1131ium2°4?
N
N
N
Use:
1
MeV/sec=1.602x10"
Watts,
A,=0.602x10*
[nuclei/mole],
1
Curie=3.7x10'°
Bq.
752
MeV/
45
tamtrer
{
M
1\a=
(
a7l5(o.7e‘{
Mev
/iy
aton)
x
(,024Y0-347
MV
/I;s:wkwi'?g)
=(¢=0.7>2
ol
j
v
R
23
3
'
¢
INT,
-3
P
A5
Mags|
2
v
Omf01C
180t
s
A=
o).
(6-0210
)
2\,
72
10
B¢/y™
f\
‘)
n-
Ve
Vdag
|
\ne
Lmin
(\.M?y\(fllg)
(20‘4
{))
M
33,
|
|
Gre
k
—>
‘/Q_‘EM
?))
.
72x0
m
{"‘3
740
0"
%T,
=
Lli_és
(uies
[om
fw
A
fusion
process
uses
the
gB“
fusion
reaction
producing
a
C'?
nucleus
in
its
excited
state.
This
excited
C'2
nucleus
decays
to
Be® and
He*.
Be®
within
10"
sec
further
decays
into
two
more
He®
nuclei.
This
is
the
only
known
nuclear-
energy
releasing
process
that
releases
fusion
energy
and
helium
nuclei,
but
no
initial
neutrons.
m(,H")
=1.0078250
amu,
m(,B")
=11.0093055amu,
m(,He")
=
4.0026032
amu
,
1
amu
=931
481
MeV
1.
Balance
the
nuclear
reactions.
_
lbbm{('
267$250,m,
¢
11:0043059
amu)
°<3
4.
00260R
"”)l
2.
Calculate
the
Q
value
of
thg
ggg@uggctinn.---
=
4
{
o
1
12¢
i
}
?
+.B">
C
'\&
W
;sl
',‘,"(d
.
‘5m:0.00“52°4
any
C"
-
B+
?
|
-
i
te
|
6
.
|
W&
Bty
L
Qeam
@5‘_'{%]
foev)
B
-
?
+
7
8@1
v
4
|
i
-
Ue
«
He
|
J
4
T
T
g
(oot
an¥asl
40K
<
5
i
.
R
7T
>
1
Wb
AN
Question
3
,\_
g
Write
down
the
units
of
the
following
radiological
quantities:
Radiological
Quantity
Conventional
System
Unit
SI
System
Unit
Activity
Ba
X
X
g
5=t
Absorbed
Dose
?
>
ke
=1
%
~
Using
the
law
of
radioactive
decay
calculate
the
fraction
of
the
tritium
isotépe
(No-K(t)/No
decaying
into
the
He
isotope.
The
half-life
of
tritum
is
12.33
years.
11121233
5
N
v
1
Y
al
A~
Within
1
year.
N
(_
(n(l)/
@0
D
<
Fo
,0,‘1‘\5
|-
0,055
W5
Muwye
N_
-7
_
L5
=
exp
2.3
9
~*e
2.
Within
12.33
years.
**
M
"
\
N
E)
50
hes
J{,“V)“j
Ne
5
A
Wibin2466yers
o
()
anw)):
%05
1-%.-|0
:
N
N
B}
V
Question
4
>
%--‘”P(‘CP’\“)/D.SS\gf)éq.bé%')}ffu'0'25
|
No
~
0:75
s
deau
){l
1.
Assuming
that
heat
rejection
occurs
at
an
ambient
temperature
of
20
degrees
Celsius,
estimate
the
Carnot
cycle
thermal
efficiency
of
a
PWR
(Pressurized
Water
Reactor)
operating
at
an
average
heat
addition
temperatures
T,
of
168
°C.
2.
List
5
Engineered
Safety
Features
(ESFs
of
the
PWR
concept
2.
Conbol
colls,
cantmnmont
ok
+cotbnaunt
sprag)
WPCT
(hipresivd
caoban?
g,
LPCT
(tnw
pressume
calant
weet))
esidbal
bl
ool
gt
e
clamngpt
NPRE
402,
Nuclear
Power
Engineering
g
Spring
2015,
Second
Midterm
Afi
Please
answer
all
questions.
Show
or
derive
the
equations
that
you
use
in
your
calculations
and
reporffhe
units
and
the
details
of
your
calculations.
Name:
Td‘f)\o(
Saale
|
g
/Question
1
i
TRy
A
beam
of
neutrons
falls
on
a
slab
of
a
shiclding
material
whose
total
mean
free
path
is
1
cm.
I
1.
Calculate
the
thickness
of
material
that
will
attenuate
the
beam
to
one
half
of
its
initial
intensity:
X=
~Z
{n
o>
2.
Calculate
the
e-folding
distance
that
would
attenuate
the
beam
to
1/
¢
of
its
initial
intensity.
l
0]
(The
Euler’s
number
or
Napier’s
cons—m;t
¢
=
2.71828,
is
the
base
of the
natural
logarithm).
\,
¥=
-(lcmyfln(Ovs)
x=
0.69¢m
2,
%=
=(lem)n
(V1e)
_
\/
uestion
2
m
List
five
isotopic
enrichment
methods
used
in
the
enrichment
of
the
heavy
fissile
isotopes
such
as
U%:
1.
gaceas
Do
2.
Thecana
|
b
fs
om
3.
Cemb
bgak
4.
E,l((MYV\aa‘)ng
Scp,.
at
5.Nozzle
PRocess
Five
Engineered
Safety
Features
of
the
BWR
design
are:
LW
T
2.LPCT
3.¢
onhal
Rods
4,
Rovon
Tn
seckion
5.0
dual
bt
Romova]
beat
excinngps
Question
3
An
executive
at
an
electrical
utility
company
needs
to
order
natural
uranium
fuel
from
a
mine.
The
utility
operates
a
single
1,000
MWe
power
plant
of
the
CANDU
type
using
natural
uranium,
and
operating
at
an
overall
thermal
efficiency
of
1/3.
What
is
the
yearly
amount
M
ic
fonnes
of:
349103
““"vi,.__
=319
107
Mev/yc
#
235
235
Y10
=t
T
=
:
u
T
r
)
wilis
°3
L
1)
tom
wehi
a.
U™
burned
up
by
the
reactor?
comin
it
36548
4
D
S
st
M.”'.‘r’n
e
Pz
10D
UL
|
ygADA
W
T
DB
=
b
p
ey
¥
5
15
g0y,
285022
-
gfiws"ww
S
y
.
T
S
Timviitne
T
diy
1Y
Of
6a¥D?
ARV
\2
Y
b.
U™’
consumed
by
the
reactor?
\
.
3900
g
365drg]
K2
|
loane
__,qu
mefric
nnes
AN
VRO
MO
)
T
IV
O
e
e
e
.
’
[?
-
‘°°5°
-
3poomwe
|
12010
)(BomME)
i
|
1ye
fon
o
howiy
-
LA
¥}
-
¢.
Natural
uranium
metal
that
the
executive
has
to
contract
with
the
mine
per
year
as
feed
to
his
nuclear
unit?
LR
MM
e
e
e
~
T
=l
)
N7
Note:
1
metric tonne
=
1,000
kgs,
the
rate
=
1.112
(1+0.169)
P
[gm/day].
/Question
4
1.
In
neutron
cancer
therapy,
the
following
reaction
can
be
used
to
destroy
tumors
with
boron
brought
at
a
cancer
tumor’s
site:
.
1
10
4
»
ot
+sB°
=
,He'
+
?}Q
2.
If
the
neutron
density
is
n=10°[n/cm’],
and
the
neutron
speed
is
v=10’[cm/sec],
and
a
single
beam
of
neutrons
is
al
abundance
of
U
in
natural
uranium
is
0.72
percent.
U**
consumption
2
ki
%
perdve
Sem
15
%neutronflux
is:
1.0
«19”
MMA""L
i
s
=
(i
este
b=nv:=
10
T’Fkg\'
075
s
k0sid
oot
and
the
neutron
current
is;
|,
©
¥
1D
%
nevhaS
/0
e
)
o
ks
()
at
both
the
tumor
and
the
surrounding
tissue.
B
37
ook
(v
3.
A
better
alternative
is
to
use
two
opposing
beams
to
irradiate
the
tumor.
At
their
intersection,
ignoring
the
beams
attenuation,
>
pevhvons
/2
the
neutron
flux
at
the
tumor
will
be:
2:0¥
10
(in"istt
the
neutron
current
at
the
tumor
will
be
o)
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D
NPRE
402
Nuclear
Power
Engineering
Fall
2014,
Second
Midterm
Test
|
6
Please
answer
all
questions.
Show
or
derive
the
equations
that
you
use
in
your calculations and
report
the
units
and
the
detax}
your
calculations.
Name:
C1\©C
|
}\"‘C,erg
[
g
estion
1
!
W‘Q\’*&S
The
catalyzed
DD
reaction
would
occur
in
a
second
generation
fusion
reactor:
.
2
v
D'+
D'
>
24
H'+4.03
MeV
\D
=+
‘D
—
,2
4
UOShe
D+
D'
%4
0
+327
MeV
'D”+\Dl_.;7_),\€5
3
1Mev
D'+
I
5%
n'
+
17.6
MeV
D+
He*
>+
H'
+183
MeV
a.
A
reduction
of
the
initial
radius
r,
byafactq{
of
2.
Q
=
QQ
2
<
\y
1%
0:041
Al%M\/(n\q
b.
A
reduction
in
the
initial
radius'x,
by
a
fagtorof
10.
‘
=
0%
Q:DQZQW#
Question
2
1.
Therred
D@
ON
g'
E\etrao
CoOGineA
(C
SL
R
\om
QN
of
-
A
B
2
S05R0LS
SR
ON
5.
no2zie
e
e85
What
do
the
following
acronyms
stand
for?
PWR
-
D@
S0
20
bo(W
N
E
TG
ix—
N
BWR
-
Y\"z';/\
\WO
JOsT
e
<t
—
.V-T'
HTGR
—‘T\\Q\'f\‘\\'r;(\‘\\'}
w(*—(
Lce
UL
f.
r
-
\
\/
[
\
ANV
UV
N
1
Tl
B
LNIFBR
-
aungd
\—\»\e:.
Cui’\.
{
»:‘
N2
AN
)
-\
"
MSBI).\
!
1
SOy
3(\‘6\_‘4‘
VoW
Y
G
AT
D
e
Question
3
'
The
fuel
consumption
rate
in
a
thermal
reactor
operating
at
a
power
level
of
P
MWth
is
given
by:
consumption
rate=
1.299
P
[E—]
day
An
executive
at
an
electrical
utility
company
needs
to
order
n@q@;—g@)
fuel
from
a
mine.
The
utility
operates
a
1,000
MWe
power
plant
operating
at
an
overall
thermal
efficiency
of
1/3
of
the
CANDU
type
using
natural
uranium.
What
is
the ye‘grly
amount
in
metric
tonnes
of:
)
o
T
;
A
1.
U
consumed
by
the
reactor?
("2
-
|
20!
(3000)
=
3541
g/de
o
*
I
1122409
e
A
2.
Natural
uranium
metal
that
the
executive
has
to
contract
for
with
the
mine
in
metric
tonnes}er
year
as
feedfo
his
nuclear
unit?
Note:
1
metric
tonne
=
1,000
kgs,
the
natural
abundance
of
U**
in
natural
uranium
is
0.72
percent,
'
)
O)
C
,'
'2"1‘1
<
TN
"
fn
=
1000,/
/3
=
3000
M
Wi
Mp=CR
|
W22405aiie
10188
24
g/
|
X2
S
:
XC\TCDQ}(OM—%
‘(‘
\
A
Stirling
cycle
engine
using
a
radioactive
isotope
for
space
power
applications
operates
at
a
hot
end
temperature
of
LA
650
°C
and
rejects
heat
through
a
radiator
to
the
vacuum
of
space
with
a
cold
end
temperature
at
120
°C.
Calculate
its
ideal
Stirling
cycle
efficiency.
’ZOf“.
RS
o
10914
I
T\—k
‘OLJO‘V'L"&
ki
\
"
Hefl.\«{g
~
12’/)
L
5{}
"
’I/U
f«gs
(s
(M
)
g
NPRE
402/ME
405,
Nuclear
Power
Engineering
5
Spring
2012,
Second
Midterm
Test
Please
answer
all
questions.
Show
or
derive
the
equations
that
you
use
in
your
calculations
and
report
the
units
and
the
details
og
calculati
Nae
&M}M
i,
o
etion
,\[)
uestion
1
Draw
a
line
to
match
the
following
radiological
quantities
to
their
respective
units
on
the
right
and
left:
Conventional
System
Radiological
quantity
SI
System
Unit
L
A
Curie
(Ci)
~
=3
Effective
dose
(dose
equivalent)
§<|
~Becquerel
Bq)
ey
Zf#ing
rem
|~
Absorbed
dose
~
Sievert
(Sv)
b
e,
l
Aepted
_rad
Activity
—
£—
—
y
(Gy)
Apeprbed
|
Question
2
A
sample
of
U™
is
subjected
to
a
neutron
flux
¢
of
10"
[neutrons
/(cm?.sec)].
The
microscopic
scattering
cross
section
o,
for
U™
with
a
density
of
p=19
[gm/cm’]
is
8.9
barns.
Avogadro’s
number
is
0.6
x
10**
[nuclei/mole],
1
barn
=10
cm
o8
;
-
:
staw
N
=2
14
40,
022103l
1.
Calculate
the
U™®
number
density,
N,
using
the
modified
form
of
Avogadro’s
law
N
=
I;
=
s
.
(o.
/b
2.
Calculate
the
mgg)scoplc
scattering
CIOss
s
section
Zg
a3
3.
Calculate
the
scattering
mean
free
path
As
vad
4.
Calculate
the
scattering
reaction
rate
density
R
in
[scattenngs
(cm®
=
©
N
=/490e1?
T
B
Question
3
O
>\S
-
\{’L"l
=
7’%31
i
~U}
List
3
main
processes
for
the
isotopic
separation
and
the
enrichment
of
the
uranium
isotopes:
q
-
1.
Zledeo
Magn
B
SEpatton
@
Q
9/<
=
0
2.
(&"\H
\
i’@s’\
Lo
“.—l.
3.
Noat
Pfoamé
The
fuel
consumptlon
in
a
thermal
reactor
operating
at
a
power
level
of
P
MWth
is
given
by:
consumption
rate=
1.299
P
[;]
Qura
o
VS
(Engap
fon
-
uln
i
An
executive
at
an
electrical
utility
company
needs
to
order
natural
uranium
fuel
from
a
mine.
The
utility
operates
a
1,000
MWe
pov
plant
operating
at
an
overall
thermal
eflimency
of
1/3
of
the
CANDU
type
using
natural
uranium.
What
is
the
yearly
amount
in
me
tonnes
of:
7
ng
f\
z
MWl
=
(000
/"/3
=
“Z3009
/‘/’WTH
1.
U**
consumed
by
the
reactor?
ZWetal
that
the
executive
has
to
contract
for
with
the
mine
in
metric
tonnes
per
year
as
feed
to
his
nuclear
unit?
Note:
1
metric
tonne
=
1,000
kgs,
the
natural
abundance
of
U*®
in
natural
uranium
is
0.72
percent.
O
’Y/'
I.MK{
j
MU/\(\
.
‘Lf/’m?’
-~
\‘uI
1
’oq.‘dvv
:\i\‘
r
7
Question
4
'
”;‘
i
N
fowne
List
3
ma%l
processes
of
gamma
rays
interaction
with
matter:
(Bfl'\
\)
N
AT\
’\
}
=
|
M’—\
;
7
1.
Photy
elechmt
x
00072
2.
fhoto
nicldr
e
0
3.
(qmplon
Ccaflenny
.
A
radiation
shield
is
used
to
attenuate
a
gamma
rays
beam
of
initial
mtens1ty
I
=
10°
[photons/(cm”
.sec)].
If
the
shield
is
made
lead
with
a
total
attenuation
coefficient
at
1
MeV
of
Zt
0.771
cm™,
what
would
be
the
‘thickness,
of
the
shield
for
attenuating
tt
gamma
rays
beam’s
intensity
to
I(x)
=
1
[photon/(cm”
sec)]
,
cons1dermg
an
E_ponentufl
attenuation
of
the
beam,
and
a
buildy
factor
of
B=2?
/(?\5
j
5
S C
,é_r
x
1)
-irx
>
K
n
S
W2
1S,
]‘,b.g
‘yoS
X
=
’:O/,n\
3.5
@S
NPRE
402/ME
405,
Nuclear
Power
Engineering
Fall
2010,
Second
Midterm
Pleasc
answer
all
questions.
Show
or
derive
the
equations
that
you
use
in
your
calculations
and
report
the
units
and
the
dfiai.l?(
vour
calculations.
Name'
Mosre,s
R,
Neel
g
Question
1
=
Using
the
exponential
attenuation
law,
calculate
the
thickness
of
a
slab
shicld
made
out
of
a
shiclding
material
whoguoa(
absorption
cross
section
Z,
is
1
cm.
that
would
attenuate
a
beam
of
neutrons
by
a
factor
of:
ow
a)
One
million
times
(10°)
Tex)
~E¢
X
6y
T——
vl
e
*‘)“‘(“’
)
.
,X
a
13,14“"*\}
-
’?:4
\
-~
b)
—
its
initial
intensity
or
the
c-folding
distance
-
e
’
,
.
]
l
(s
L.
=
=
Pow
S'c
:
X
=,
PN
B
Question
2
G
1™
A
fission
reactor
of
Wl
shape
has
the
following
parameters:
@
n:
VE
ol87,
hfi%{';}
Diffusion
coeflicient.
D=
9
21
[em].
o
.
fiu
as
5:":;‘1:}
-
3
-]
Ov
~
ahe
)
T
1%
1
e
“
T
d:d
;
verall
macroscopic
absorption
cross
section:
E‘,
0.153
[em™],
Q)
o=
mfpBNE
(e
&)
:{,‘
;
é
g
L
Coleulot
|
Fuel
macroscopic
absorption
cross
section:
Za
=0.140
[cm"],
e
=
M
ot
Yo
.
s
B
mad,
Vz.f=
0.157
[neutronscm’|,
£
=
p
=
1,
f
=0.99.
3
Lz-f‘
Zz
/o,ls;'!..@"q"
Gor
7Y
“
+‘
:
L
\
lfiov
3&‘\'
-‘
0.5¢
Density’
p
=
10
[gm/em’)
L’L’:?ECM
\
(s
Does
wol
Calculate
the
following
reactor
parameters
using
the
one-group
ditfusion
R
oevee
WML
theory,
1
lgnogxng
l‘hv..
x.\1rapolzm<n1
length.
@
&2
[,.
A
Loisg
.y
_
1
2‘43«"1
1:':
ejtven
1.
Regeneration
factor
1)
:
xS
e
L
Couat
Nealbue
2
Infinite
medium
multiplication
factor
&
.
@
Re:
"’F|‘
]
X
bodib
e
i
Loui
|
s
}lqsqlzc‘ij)(
3.
Diftusion
length,
L.
S
4
Material
buckling,
B,
.
<
X&'
@v,:
dwds
m
o
X
5.
The
critical
radius,
R
.
s
R
N
i
.
6.
The
critical
volume
V.
D
Me
\C?
fiwm
€3
IL‘)
-
._Izef'
gq
M"m‘j
7.
The
critical
mass.
M.
in
kgs
and
metric
tonnes
2
Question
3
An
exccutive
at
an
electrical
utility
company
needs
to
order
natural
uranium
fuel
from
a
mine.
The
utility
operates
a
single
1.000
MWe
power
plant
of
the
CANDU
type
using
natural
uranium,
and
operating
at
an
overall
thermal
efficiency
of
1/3.
What
1s
the
yearly
amount
of:
a0
Mg
"
a.
U™
burned
up
by
the
reactor?
Pe
L
%00
MW
b.
U™*
consumed
by
the
reactor?
Mot
‘-—-”/
h‘
¢.
Natural
uranium
that
the
executive
has
to
contract
with
lpe
mine
per
year
as
feed
to
his
nuclear
unit?
p:
2006
Mh
6v
(
2
(h}o
\
?36
’M/
=y
,!2
7,
é
l”‘/wl\y}
)
Rap
=
€_§
-
Hw
b
’qu‘\zr
[5
o
@
Mp
o
lon
wr
(1269)(3000)
=
3891
77
D
|
1922
4sg
}(1{2’
:
.
7
—_————
Question
4
List
five
isotopic
enrichment
methods:
Twavmg
|
D
Hosion
Flu-lvomo\‘}w'lit
ggw,
C’fi«&ué
b[#us.‘-m
Con
+r',£u°)°d.;q.
2ac
Noz3
procass
s
Question”s
;
_
s
Consider
two
neutron
sources
of
strength
S
=
10'’[n/sec]
each
separated
by
a
distance
of
200
cm
in
a
vacuum.
9("’\
2
T
1.
Calculate
the
values
of
the
flux
and
he
cux:nenfat“tlw
midpoint
between
them
4Ty
S
-
206"
L
sasd
/
Fi=
TR
T
o
ke
|
Tuv)=
T
e
2.
Calculate
the
flux
and
current
at
a
distance
of
100
cm
above
the
rrudpom
3
-..___\____\
{
Ut
e
o
b
—
Sialds)
24
10"
10
2¢)0
i
"
!
.
T
245
U7
Te)
=
<
Slaeae
2
(§)
¢“)'
J%
M2
‘__._.__t'.‘.f
4
Wt
St
ve
‘L}
X
PR
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Ta
Remaining Time: 46 minutes, 48 seconds.
Question Completion Status:
-30V-
QUESTION 6
Determine whether each silicon diode in the following figure is forward biased (fb) or reversed biased (rb)
Using the practical model, the voltage across the diode is
V.
10 N
5V
5V
Click Save and Submit to save and submit. Click Save All Answers to save all answers.
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At 305 °K temperature, the voltage equivalent of temperature of diode is ______________________V. Assume the Boltzmann's constant is 8.62*10-5 eV / K
Answer:
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Fifty years into the future, the way we will probably make base load energy include(s)
Select one:
A. Solar
B.Fission
C.Fusion, fission and solar
D.Fusion
arrow_forward
Answer a,b,c,d
arrow_forward
Q4. Why thermalizing neutrons in a fission reactor is important? Present a mathematical derivation
supporting the claim that water is an effective moderator for a fission reactor.
arrow_forward
A charged capacitor could be connected to two identical resistors in either of the two ways shown. Which configuration will discharge the capacitor in the shortest time once the switch is closed? Explain.
arrow_forward
Q1. Determine the class of mater ial based on relative comparison for each energy diagram.
Energy
Energy
Energy
Conduction bund
Energs gap
Conduction band
Energy gap
Conduction band
Overlap
Valence band
Valence bund
Valence band
(b)
Assignment1- (ENEL2104)
Page 1
Q2. What are the major carriers in the depletion region? Explain.
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assessment/take/launch.jsp?course_assessment_id%3_34730 18course_id%3_56188_1&content id%3 1713242 18step
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Path: p
Words:0
QUESTION 2
2 poin
Assuming the practical model of the diode, what is the output waveform for the circuit shown
below.
+30 V
5V
Vin
OV
1.0 kN
Vout
-30 V
Click Save and Submit to save and submit. Click Save All Answers to save all answers.
Save All Answers
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InP is composed of equal atoms of indium and phosphorus in a lattice similar to that of silicon. (a) Suppose a germanium atom replaces an indium atom in the lattice. Do you expect the germanium atom to behave as a donor or acceptor impurity? Why? (b) Suppose a germanium atom replaces a phosphorus atom in the lattice. Do you expect the germanium atom to behave as a donor or acceptor impurity? Explain.
arrow_forward
4
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A. Explain the difference between charging current andfaradaic current.
B. What is the purpose of waiting 1s after a voltage pulse before measuring current in sampled current voltammetry?
C. Why is square wave voltammetry more sensitive than sampled current voltammetry?
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