CSU Lecture on Thorium –LFR NUCLEAR POWER PLANTS ... - NASA
Transcript of CSU Lecture on Thorium –LFR NUCLEAR POWER PLANTS ... - NASA
CSU Lecture on Thorium –LFR NUCLEAR POWER PLANTS
Space & Terrestrial Power System Integration Optimization Code BRMAPS for Gas Turbine Space Power Plants
With Nuclear Reactor Heat Sources
(Theme for Advanced Nuclear Power Plant Lectures at CSU–Spring ’07)
by Dr. Albert J. Juhasz
In view of the difficult times the US and global economies are experiencing today, funds for the development of advanced fission reactors nuclear power systems for space propulsion and planetary surface applications are currently not available. However, according to the Energy Policy Act of 2005 the U.S. needs to invest in developing fission reactor technology for ground based terrestrial power plants. Such plants would make a significant contribution toward drastic reduction of worldwide greenhouse gas emissions and associated global warming. To accomplish this goal the “Next Generation Nuclear Plant Project” (NGNP) has been established by DOE under the “Generation IV Nuclear Systems Initiative”. Idaho National Laboratory (INL) was designated as the lead in the development of VHTR (Very High Temperature Reactor) and HTGR (High Temperature Gas Reactor) technology to be integrated with MMW (multi-megawatt) helium gas turbine driven electric power AC generators. However, the advantages of transmitting power in high voltage DC form over large distances are also explored in the seminar lecture series.. As an attractive alternate heat source the “Liquid Fluoride Reactor” (LFR), pioneered at ORNL (Oak Ridge National Laboratory) in the mid 1960’s, would offer much higher energy yields than current nuclear plants by using an inherently safe energy conversion scheme based on the Thorium --> U233 fuel cycle and a fission process with a negative temperature coefficient of reactivity. The power plants are to be sized to meet electric power demand during peak periods and also for providing thermal energy for hydrogen (H2) production during "off peak" periods. This approach will both supply electric power by using environmentally clean nuclear heat which does not generate green house gases, and also provide a clean fuel H2 for the future, when, due to increased global demand and the decline in discovering new deposits, our supply of liquid fossil fuels will have been used up. This is expected within the next 30 to 50 years, as predicted by the Hubbert model and confirmed by other global energy consumption prognoses. Having invested national resources into the development of NGNP, the technology and experience accumulated during the project needs to be documented clearly and in sufficient detail for young engineers coming on-board at both DOE and NASA to acquire it. Hands on training on reactor operation, test rigs of turbomachinery, and heat exchanger components, as well as computational tools will be needed. Senior scientist/engineers involved with the development of NGNP should also be encouraged to participate as lecturers, instructors, or adjunct professors at local universities having engineering (mechanical, electrical, nuclear/chemical, and/or materials) as one of their fields of study.
Gle
nn R
esea
rch
Cen
ter a
t Lew
is F
ield
CSU
Lec
ture
on
Thor
ium
–LF
R N
UC
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R P
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tegr
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Opt
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ode
BR
MA
PS
for
Gas
Tur
bine
Spa
ce P
ower
Pla
nts
with
Nuc
lear
Rea
ctor
Hea
t Sou
rces
Dr.
Alb
ert
J. J
uh
asz
Feb
ruar
y 13
th, 2
007
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A fu
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()
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PC
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−−
⎟⎟ ⎠⎞⎜⎜ ⎝⎛
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=
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Isen
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for C
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nd T
urbi
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as a
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Pre
ssur
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atio
for v
ario
us In
finite
sim
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tage
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and
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ETA
PC=
.95 0.9
0.85
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0.75
ETA
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0.9 0.85 0.8
18G
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19G
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Influ
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of R
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ffect
iven
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(ER
G) o
n C
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Effi
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Cyc
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emp.
Rat
io o
f 3.0
and
4.0
0.00
0.05
0.10
0.15
0.20
0.25
0.30
0.35
0.40
0.45
0.50 1.0
2.03.0
4.05.0
6.07.0
8.0Cy
cle Pr
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Cycle Efficiency
ERG=
0.95;
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=4ER
G=.80
ERG=
0.50
ERG=
00.0
0
0.05
0.10
0.15
0.20
0.25
0.30
0.35
0.40 1.0
02.0
03.0
04.0
05.0
0Cy
cle Pr
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Cycle Efficiency
ERG=
.95; A
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0ER
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==
=γ
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1;9
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(a) T
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Reg
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s w
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as
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for H
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= 5
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=
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2 “
“◊◊
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Specific Mass –kg/(kg/sec)
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iow
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Tem
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IT a
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40.0
45.0
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55.0
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85.0
90.0
2.2
2.4
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Tem
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atio
Mass in TonnesTI
T=11
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0.20.2
50.3
0.35
0.40.4
5
Cycle
The
rmal
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Mass - Metric TonsTIT
= 1
100
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135
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TIT =
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0 K
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23G
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nn
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Bra
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26G
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Op
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Cod
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Cod
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27G
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per
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28G
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Sol
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nerg
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a P
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n-P
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hain
Rea
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1.1 1H
+ 1 1H
2 1H
+ e
++ ν(
neut
rino)
(0.4
2 M
eV)
2.e+
+ e
-γ
(rad
iatio
n)(1
.02
MeV
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1 1H +
2 1H
3 2H
e +
γ(5
.49
MeV
)4.
3 2He
+ 3 2H
e 4 2H
e +
1 1H +
1 1H
(1
2.86
MeV
)N
et E
ffect
: 4
1 1H
4 2He
+ 2
e++
2 ν
4*1.
0078
265
u =
4.0
0260
3 u
+ (2
e+
+ 2ν
+ 2 γ
+ 12
.86
MeV
)To
tal E
nerg
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ener
ated
–E
= m
*c2
Et=
(4.0
3130
08 –
4.00
2603
) u *
1.6
6*10
-27
kg/u
* (3
*108
m/s
ec)2
= 2
6.76
MeV
/p-p
cyc
lew
hich
che
cks Σ
reac
tion
step
ene
rgie
s, E
RS
ER
S=
2*(0
.42
MeV
+1.
02 M
eV +
5.4
9 M
eV) +
12.
86 M
eV =
26.
76 M
eV/p
-pS
olar
Lum
inos
ity, L
, is
due
to 9
*103
7 p-
p cy
c/se
cL
= 26
.76
MeV
*1.6
02*1
0-13
J/M
eV *
9*1
037 /s
ec =
3.8
6*10
26 W
atts
Sol
ar M
ass
Loss
(4.0
3130
08 –
4.00
2603
) u*1
.66*
10-2
7kg
/u *
9*10
37/s
ec =
4.3
*109
kg/s
ec=
4.3
Milli
on to
nnes
/sec
29G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Sol
ar a
nd A
rbitr
ary
Infra
red
Spe
ctra
05. 1
07
1. 1
06
1.5. 1
06
2. 1
06
0
2. 1
013
4. 1
013
6. 1
013
8. 1
013
1. 1
014
Wav
elen
gth
mu
- met
ers
Radiation Intensity - Watts/m*2 mu
Iλ
5780
,(
)
Iλ
3500
,(
)
410
7−
⋅7
107
−⋅
λ
Vis
ible
Ran
ge
Sola
r Spe
ctru
m
Infr
ared
Spe
ctru
m
30G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Equi
libriu
m T
empe
ratu
res,
TS(
K),
at V
ario
us A
U D
ista
nces
90.0
1
.0
.9
.9
2
1
.00
1
372.
5
386
M
oon
@ N
oon
Gle
nn R
esea
rch
Cen
ter a
t Lew
is F
ield
SUN
MER
CU
RY
9149
W /
m 2
448K
0.38
7 AU
EAR
TH13
71 W
/ m
2
279K
1 AU VE
NU
S26
20 W
/ m
2
328K
0.72
3 AU
MA
RS
591
W /
m 2
226K
1.53
AU
AS
TER
OID
S15
2 W
/ m
2
161K
~ 3
AU
JUP
ITE
R51
W /
m 2
122K
5.2
AU
SATU
RN
15 W
/ m
2
90K
9.54
AU
UR
ANU
S3.
7 W
/ m
2
64K
19.2
AU
NEP
TUN
E1.
5 W
/ m
2
51K
30.1
AU
PLU
TO0.
9 W
/ m
2
44K
39.4
4 A
U
Sola
r H
eat
Flu
x &
Sp
ace
Pro
be
Tem
per
atu
res
At
Var
iou
s O
rbit
al D
ista
nce
s (A
U)
A. J
uhas
z
NA
SA
GR
C.
10/3
1/03
32G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Rad
iato
r Are
a R
equi
rem
ent f
or 3
00 k
WtH
eat L
oad
at A
vg. R
adia
tor S
urfa
ce T
empe
ratu
re =
390
K(θ
= 25
°; F
V =
1; α
/εra
ngin
g 0.
1 to
1.0
)
5010
015
020
025
030
035
025
0
300
350
400
450
500
550
Spac
e Si
nk T
empe
ratu
re -
K
Radiator Area in Square meters
RdA
R
138
325
Tsin
k
Jupi
ter O
rbit
AU
Earth
Orb
it A
U
KK
33G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Spa
cecr
aft w
ith T
rape
zoid
al H
eat P
ipe
Rad
iato
r
Payl
oad
Rad
iato
r
Rea
ctor
Shie
ldTu
rbo-
Alte
rnat
ors
34G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Ther
mal
Ene
rgy
Tran
sfer
in a
Hea
t Pip
e R
adia
tor
35G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Rel
atio
nshi
ps R
esul
ting
from
Clo
sed
Bra
yton
Cyc
le A
naly
sis
()
()(
)(
)()
⎥⎥ ⎦⎤
⎢⎢ ⎣⎡
⎥⎥ ⎦⎤
⎢⎢ ⎣⎡⎟⎟ ⎠⎞
⎜⎜ ⎝⎛⋅
−⋅
⋅−
+⋅
−+
⋅−
⋅⋅
⋅⋅
+ ⎟⎟ ⎠⎞⎜⎜ ⎝⎛
−−⋅
⋅⋅
=−
−
swex
swin
sw
ins
wex
sw
exs
win
ss
wex
sw
in
rp
rTT
TTT
TT
TT
TT
T
TT
TT
Th
Cm
A1
1
34
4
44
tan
tan
2ln
4
1ln
1
εσ
()
()
RR
CC
CR
Tt
RR
CCt
C
Tb
th
εε
ηε
αη
εε
α
ηη
αη
η−
Θ+
Θ−
+−
+⎟⎟ ⎠⎞
⎜⎜ ⎝⎛Θ
−+
−
⎟⎟ ⎠⎞⎜⎜ ⎝⎛
Θ−
⎟⎟ ⎠⎞⎜⎜ ⎝⎛
Θ−
Θ
=1
11
11
1
1
Bray
ton
Cyc
le T
herm
al E
ffici
ency
whe
re
ΘC
= (P
OC
/ PIC
) (γ-1
)/γis
the
com
pres
sor p
ress
ure
ratio
par
amet
er
ΘT
= (P
IT/ P
OT)
(γ-1
)/γis
the
turb
ine
pres
sure
ratio
par
amet
er
Rad
iato
r Are
a
36G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Dua
l Loo
p 20
0 M
We
Clo
sed
Cyc
le (H
e) G
as T
urbi
ne (C
CG
T)Po
wer
Sys
tem
with
Nuc
lear
Fus
ion
Rea
ctor
Hea
t Sou
rce
Sam
ple
Pow
er P
lant
Ana
lyze
dfo
r Lar
ge In
ter-
plan
etar
y S
pace
craf
t
37G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Inte
rpla
neta
ry C
rew
Tra
nspo
rt V
ehic
le
Art
ific
ial G
ravi
ty
Cre
w P
aylo
ad
Bra
yton
Cyc
le
Rad
iato
rs
Rea
ctor
Coo
lant
Rad
iato
rs
Prop
ella
nt
Cry
o-T
anka
ge
Bra
yton
Pow
er C
onve
rsio
n
Sphe
rica
l Tor
us
Fus
ion
Rea
ctor
Mag
neti
c N
ozzl
e
90 m
40 m
37 m
24 m
25 m
240
m
60 m
38G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Ad
van
ced
Pow
er S
yste
m A
pp
licat
ion
s
Luna
r Bas
e Po
wer
Sys
tem
Arti
ficia
l Gra
vity
Cr
ew P
aylo
ad
Bray
ton
Cycl
e Ra
diat
ors
Reac
tor C
oola
ntRa
diat
ors
Prop
ella
nt
Cryo
-Tan
kage
Bray
ton
Pow
er C
onve
rsio
n
Sphe
rical
Tor
us
Fus
ion
Reac
tor
Mag
netic
Noz
zle
90 m
40 m
37 m
24 m25 m
240
m
60 m
Inte
rplan
etar
y Fu
sion
Prop
ulsio
n Sp
ace
Veh
icle
39G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
For S
pace
Nuc
lear
Pow
ered
Mul
ti-M
egaw
att C
lose
d C
ycle
Gas
Tur
bine
(C
CG
T) S
yste
ms
with
Nuc
lear
can
ach
ieve
Spe
cific
Mas
s (S
PM
) < 5
kg/k
w
•B
y ut
ilizi
ng a
ircra
ft en
gine
axi
al c
ompr
esso
r/tur
bine
tech
nolo
gy–
Hig
her p
ress
ure
ratio
s al
low
rem
ovin
g he
avy
rege
nera
tor
–A
xial
turb
o-m
achi
nery
has
hig
her e
ffici
ency
than
radi
al–
Turb
ine
Inle
t tem
pera
ture
s (T
IT) c
an b
e in
crea
sed
to ~
1600
K u
sing
He
wor
king
flui
d an
d ce
ram
ic tu
rbin
e te
chno
logy
•U
sing
Hig
h Te
mpe
ratu
re G
as R
eact
ors
(HTG
R-V
HTR
) –
Dire
ct h
eatin
g of
He
wor
king
flui
d m
akes
hea
vy h
eat s
ourc
e liq
uid/
gas
heat
exc
hang
er a
nd li
quid
circ
ulat
ing
pum
p un
nece
ssar
y–
Hig
h TI
T pe
rmits
hig
h cy
cle
effic
ienc
y w
hile
per
mitt
ing
elev
ated
heat
re
ject
ion
tem
pera
ture
s, th
us re
duci
ng ra
diat
or a
rea
•B
y di
rect
coo
ling
of tu
rbin
e ex
haus
t gas
via
Hea
t Pip
e (H
P) R
adia
tor
–D
irect
coo
ling
of H
e w
orki
ng fl
uid
mak
es h
eavy
hea
t sin
k ga
s/liq
uid
heat
ex
chan
ger a
nd li
quid
circ
ulat
ing
pum
p un
nece
ssar
y–
Inhe
rent
redu
ndan
cy o
f HP
radi
ator
per
mits
redu
cing
radi
ator
spec
ific
mas
s w
hile
incr
easi
ng o
vera
ll sy
stem
relia
bilit
y•
Use
of a
ircra
ft en
gine
tech
nolo
gy (m
odifi
ed fo
r He
wor
king
flui
das
pe
r CFD
cod
es) l
ower
s de
velo
pmen
t cos
ts.
40G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Terr
estri
al N
ucle
ar P
ower
Pla
nt w
. LFR
and
HP,
MP,
LP
Hea
t Exc
hang
ers
for R
ehea
t/Int
erco
ol B
rayt
on C
ycle
41G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
42G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
43G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Thre
e S
tage
Reh
eat &
Inte
rcoo
l Bra
yton
Cyc
leTe
mpe
ratu
re –
Ent
ropy
Dia
gram
Entro
py –
J/kg
-K
Temp -K
Turb
ine
Out
let
Tem
p.
Turb
ine
Inle
t Tem
p
Com
pres
sor I
nlet
Tem
p.
Com
pres
sor O
utle
t Tem
p.
44G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Pow
er C
ycle
Sch
emat
ic a
nd T
-S D
iagr
am fo
r Sin
gle
Exp
ansi
onIn
ter-
Coo
led
Trip
le C
ompr
essi
on S
yste
m
(Fru
tsch
i)
45G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Typi
cal M
achi
ne S
izes
for 1
000
MW
e H
e P
lant
•S
ingl
e Tu
rbo-
Alt
at 1
0 M
P a
and
Pr=
2; (T
IT=1
200K
; TR
=4)
–M
ass
Flow
rate
~ 1
420
kg/s
ec–
Dia
. = 6
.5 m
; L =
~20
m; S
peed
= 1
800
rpm
–R
ecup
erat
or V
olum
e ~
360
m3
–Th
erm
al E
ff. =
48%
•Th
ree
Reh
eat/I
nter
cool
edTu
rbo-
Alt’
s–
Mas
s Fl
owra
te ~
474
kg/
sec
–P
=20
Mpa
(Pr=
2); D
ia=
1.9
m, L
= 4
.5m
, Spe
ed =
800
0 rp
m–
P=1
0 M
pa (P
r=2)
; Dia
= 2.
7 m
, L =
6.3
m, S
peed
= 5
670
rpm
–P
= 5
Mpa
(Pr=
2); D
ia=
3.8
m,
L =
8.5m
, Spe
ed =
400
0 rp
m–
Rec
uper
ator
Vol
ume
~ 12
0 m
3
–Th
erm
al E
ff. =
51.
5%
46G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Typi
cal M
achi
ne S
izes
for 3
00 M
We
He
Pla
nt
•S
ingl
e Tu
rbo-
Alt
at 1
0 M
P a
and
Pr=
2; (T
IT=1
200K
; TR
=4)
–M
ass
Flow
rate
~ 4
34 k
g/se
c (O
ne 3
00 M
We
Turb
o-G
en.)
–D
ia. =
3.8
m; L
= ~
8.8
m; S
peed
= 3
600
rpm
–R
ecup
erat
or V
olum
e ~
96 m
3
–Th
erm
al E
ff. =
48%
•Th
ree
Reh
eat/I
nter
cool
edTu
rbo-
Alt’
s (T
IT=1
200K
; TR
=4)
–M
ass
Flow
rate
~ 1
42 k
g/se
c (T
hree
100
MW
e Tu
rbo-
Gen
s.)
–P
=20
Mpa
(Pr=
2); D
ia=
1.4
m, L
= 3
.3 m
, Spe
ed =
870
0 rp
m–
P=1
0 M
pa (P
r=2)
; Dia
= 1.
9 m
, L =
4.4
m, S
peed
= 6
200
rpm
–P
= 5
Mpa
(Pr=
2); D
ia=
2.7
m, L
= 6
.3 m
, Spe
ed =
436
0 rp
m–
Rec
uper
ator
Vol
ume
~ 34
m3
–Th
erm
al E
ff. =
51.
6%
47G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Typi
cal M
achi
ne S
izes
for 1
50 M
We
He
Pla
nt
•S
ingl
e Tu
rbo-
Alt
at 1
0 M
Pa
and
Pr=
2; (T
IT=1
200K
; TR
=4)
–M
ass
Flow
rate
~ 2
17 k
g/se
c (O
ne 1
50 M
We
Turb
o-G
en.)
–D
ia. =
2.3
m; L
= ~
5.3
m; S
peed
= 5
040
rpm
–R
ecup
erat
or V
olum
e ~
48 m
3
–Th
erm
al E
ff. =
48.
4%
•Th
ree
Reh
eat/I
nter
cool
edTu
rbo-
Alt’
s (T
IT=1
200K
; TR
=4)
–M
ass
Flow
rate
~ 7
2 kg
/sec
(Thr
ee 5
0 M
We
Turb
o-G
ens.
)–
P=2
0 M
pa (P
r=2)
; Dia
= 0.
92 m
, L =
2.2
m, S
peed
= 1
2,50
0 rp
m–
P=1
0 M
pa (P
r=2)
; Dia
= 1.
30 m
, L =
3.0
m, S
peed
= 8
800
rpm
–P
= 5
Mpa
(Pr=
2); D
ia=
1.80
m, L
= 4
.2 m
, Spe
ed =
620
0 rp
m–
Rec
uper
ator
Vol
ume
~ 16
m3
–Th
erm
al E
ff. =
51.
6%
48G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Typi
cal M
achi
ne S
izes
for 1
50 M
We
He
Pla
nt
•S
ingl
e Tu
rbo-
Alt
at 1
0 M
Pa
and
Pr=
2; (T
IT=1
300K
; TR
=4.3
33)
–M
ass
Flow
rate
~ 1
78 k
g/se
c (O
ne 1
50 M
We
Turb
o-G
en.)
–D
ia. =
2.2
m; L
= ~
5.1
m; S
peed
= 5
240
rpm
–R
ecup
erat
or V
olum
e ~
38 m
3
–Th
erm
al E
ff. =
51.
4%
•Th
ree
Reh
eat/I
nter
cool
edTu
rbo-
Alt’
s (T
IT=1
300K
; TR
=4.3
33)
–M
ass
Flow
rate
~ 5
9.5
kg/s
ec (T
hree
50
MW
e Tu
rbo-
Gen
s.)
–P
=20
Mpa
(Pr=
2); D
ia=
0.87
m, L
= 2
.0 m
, Spe
ed =
13,
150
rpm
–P
=10
Mpa
(Pr=
2); D
ia=
1.23
m, L
= 2
.9 m
, Spe
ed =
930
0 rp
m–
P=
5 M
pa (P
r=2)
; Dia
= 1.
74 m
, L =
4.0
m, S
peed
= 6
600
rpm
–R
ecup
erat
or V
olum
e ~
13.5
m3
–Th
erm
al E
ff. =
53.
7%
49G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Ene
rgy
Ext
ract
ion
Com
paris
on fo
r U23
8an
d Th
232
Ura
nium
-fuel
ed li
ght-w
ater
reac
tor:
35
GW
*hr/M
T of
nat
ural
ura
nium
1000
MW
*yr
of e
lect
ricity
33%
con
vers
ion
effic
ienc
y (ty
pica
l st
eam
turb
ine)
3000
MW
*yr o
f th
erm
al e
nerg
y
32,0
00 M
W*d
ays/
MT
heav
y m
etal
(typ
ical
LW
R fu
el b
urnu
p)
39 M
T of
enr
iche
d (1
4.2%
) UO
2(3
5 M
T U
)
Con
vers
ion
and
fabr
icat
ion
365
MT
of n
atur
al
UF 6
(247
MT
U)
293
MT
of
natu
ral U
3O8
(248
MT
U)
Thor
ium
-fuel
ed li
quid
-fluo
ride
reac
tor:
11,
000
GW
*hr/M
T of
nat
ural
thor
ium
Con
vers
ion
to U
F6
1000
MW
*yr
of e
lect
ricity
50%
con
vers
ion
effic
ienc
y (tr
iple
-re
heat
clo
sed-
cycl
e he
lium
gas
-turb
ine)
2000
MW
*yr
of th
erm
al
ener
gy
914,
000
MW
*day
s/M
T 23
3 U (c
ompl
ete
burn
up)
0.8
MT
of 23
3 Pa
form
ed in
re
acto
r bla
nket
from
th
oriu
m (d
ecay
s to
233 U
)
Thor
ium
met
al a
dded
to
bla
nket
sal
t thr
ough
ex
chan
ge w
ith
prot
actin
ium
0.8
MT
of th
oriu
m
met
al0.
9 M
T of
na
tura
l ThO
2
Con
vers
ion
to m
etal
Ura
nium
fuel
cyc
le c
alcu
latio
ns d
one
usin
g W
ISE
nucl
ear f
uel m
ater
ial c
alcu
lato
r: h
ttp://
ww
w.w
ise-
uran
ium
.org
/nfc
m.h
tml
50G
lenn
Res
earc
h C
ente
r at L
ewis
Fie
ld
Sum
mar
y of
MM
W -
CC
GT
Pow
er S
yste
ms
& B
RM
AP
S P
oten
tial
•C
ode
can
be u
sed
for a
naly
sis
and
optim
izat
ion
of m
inim
um m
ass
spac
e po
wer
sys
tem
s (1
0 M
We)
and
als
o ~
1000
MW
e gr
ound
bas
ed p
ower
pla
nts.
•U
tiliz
ing
airc
raft
pow
er p
lant
tech
nolo
gyle
ads
to li
ght w
eigh
t and
hig
h ef
ficie
ncy
turb
o-m
achi
nery
•U
se o
f He
wor
king
flui
d re
duce
s H
eat e
xcha
nger
siz
e&
turb
o-m
achi
nery
di
amet
er, b
ut in
crea
ses
num
ber o
f axi
al s
tage
sfo
r a s
peci
fied
pres
sure
ratio
.Fo
r Spa
ce A
pplic
atio
ns•
Hig
h Te
mpe
ratu
re G
as R
eact
or(H
TGR
) allo
ws
a re
lativ
ely
high
cyc
le
tem
pera
ture
ratio
, but
indi
rect
hea
ting
as w
ith L
FR a
nd s
ever
al H
S he
at
exch
ange
rs is
nee
ded
to p
erm
it tu
rbin
e re
heat
cyc
le o
f ~50
% th
erm
al
effic
ienc
y at
low
mas
s flo
w ra
te.
•Fo
r spa
ce a
pplic
atio
ns h
ighe
r hea
t rej
ectio
n te
mpe
ratu
res
and
dire
ct c
oolin
g of
turb
ine
gas
stre
am p
erm
its lo
wer
ing
of ra
diat
or a
rea
and
mas
sre
quire
men
t•
Hea
t Pip
e R
adia
tor w
ith h
igh
inhe
rent
redu
ndan
cy p
erm
its re
duct
ion
of
radi
ator
spe
cific
mas
s w
ith in
crea
sed
radi
ator
sur
viva
bilit
yto
mic
ro-m
eteo
roid
pu
nctu
res,
thus
enh
anci
ng o
vera
ll sy
stem
relia
bilit
y•
BR
MA
PS C
ode
Enab
les
Pow
er S
yste
m O
ptim
izat
ion
Stud
ies
to b
e C
ondu
cted
O
rder
s of
Mag
nitu
de F
aste
r tha
n w
ith C
ase
by C
ase
Cod
es.
For G
roun
d B
ased
App
licat
ions
•Li
quid
Flu
orid
e R
eact
orca
n tr
ansf
er h
eat t
o se
vera
l CB
C c
onne
cted
in s
erie
s (T
urbi
ne R
ehea
t con
figur
atio
n) v
ia H
SHX
(Hea
t Sou
rce
heat
Exc
hang
ers)
. Th
erm
odyn
amic
per
form
ance
can
be
anal
yzed
via
BR
MA
PS(b
ut n
ot N
PSS)
Cod
e. A
ltern
ator
win
dage
and
bea
ring
cool
ing
loss
es a
t spe
cifie
dop
erat
ing
cond
ition
s ca
n be
add
ed a
s co
mpu
tatio
nal r
efin
emen
ts.