n m u m npfi - International Nuclear Information System (INIS)

JAERI-Research—97-022 JP9704010

JAERI-Research97-022

JP9704010

n *m * u m npfiJapan Atomic Energy Research Institute

VOL 'i 3 k 1

Ar-WlBJftiHi-li. ll««VJj«mW:fttfi# lW:ftM«.S (T319-11 4«JWtftt-fl|5MH) fox, fcf1iLSL</i'^iv, ftfc

This report is issued irregularly.

Inquiries about availability of the reports should be addressed to Research Information

Division, Department of Intellectual Resources, Japan Atomic Energy Research Institute,

Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan.

©Japan Atomic Energy Research Institute, 1997

JABRI-Research 97-022

fctzz.t\z

L fco

fc/f U

As fc L < (i C(S2)

Mfti^ x

(^. SfM9 y

311

JAERI-Research 97-022

Proposal of Safety Design Methodologies for an HTGR-hydrogen Production System

(Mainly on Countermeasures against Fire and Explosion)

Tetsuo NISHIHARA, Kazuhiko HADA and Syusaku SHIOZAWA

Department of Advanced Nuclear Heat Technology

Oarai Research Establishment

Japan Atomic Energy Research Institute

Oarai-tnachi, Higashiibaraki-gun, Ibaraki-ken

(Received February 13, 1997)

Among key issues of the safety design for an HTGR-hydrogen production system is to

ensure the safety of the nuclear reactor against fire and explosion accidents in the

hydrogen production plant. The fire and explosion accidents in the hydrogen production

plant are categorized into the following two cases; Accidents inside the reactor

building (R/B) and accidents outside the R/B.

Against accidents inside the R/B, the proposed safety design concept is to prevent the

occurrence of the accidents based on the defence in depth concept. The piping system

and/or heat transfer tubes which have the potential possibility of combustible materials

ingress into the R/B due to the failure are designed at the highest aseismic level to

prevent the failure against severe earthquake. Even if the failure occurs, the piping

trench and related compartments are fulfilled with nitrogen so as to prevent the

occurrence of accidents.

The proposed safety design concept for the accidents outside the R/B is the mitigation

of effects of accidents. Proposed countermeasures is to take the safe distance between

the hydrogen production plant and the items important to safety in the nuclear plant. We

showed that the anticipated accidents to estimate the safe distance are large scale

pool burning, fireball, pressure vessel burst and vapor cloud explosion. Especially,

new estimating concept to establish the safe distance is proposed for the vapor cloud

explosion. To reduce the safe distance, we proposed the underground non-pressurized

storage tank and ventilation system for the storage of large amount of combustible


liquid.

Keywords: HTGR, Hydrogen Production System, Safety Design Concept, Fire, Explosion,

Defence In Depth, Safe Distance, Pool Burning, Fireball, Pressure Vessel

Burst, Vapor Cloud Explosion

NEXT PAQE(S)loft BLANK


1. li^nbK l2. .i^#x^-7KlliM->zÂ0^!£it©S*^lf 3

2. i %&&!& 3

2.2 MUtfXip-7kf£$li&'>7>TAlZ!$ftts;^$L 4

2.3 >x& - mm^Mtz>%£miv%fcm 73. 'X% - mmttttz&£mme>m& 10

3.1 j&j-tpmiSiCD^Mm 10

3.1.1 m\H(D^±mm 10

3.1.2 Sft©££g$fi 12

3.2 it^-fyy Y(D-%±mm 14

3.2.1 ms.a^w& 143.2.2 mw& 153.2.3 Eta3>t*:j—hnîftibi 163. 2. 4 #141c£«y£ 173.2.5 fi*©g^(CfcU-£»ii£8S©#^ 18

3.3 *&-$f&icft-t£$£S*£0J£8 : 194. Jî^^^^rtSBT'^^-ra^^'JSÎ-^-rS^ÎSItO^X.^©*!!! 38

4. 1 ^4Kih*tm 39

4. 2 iftltiffl^nVftKfchr-S^ttm 40

4. 3 ^4t !Sl fCD#X.^©^^ 41

5. mTfcmm9i^m^t6X%'mmzttt&%£miv%îj<vtm 455.1 ymm&yyybvx&'mm 45

5.1.1 m%s\Hm-?(Dm% 455.1.2 mmwx~<D'X%.' mm 48

5.2 mmmm 50

5.2.1 xmmmm'XVLKMtzmmmM 51

5.2.2 yr-f-V-^-MzMt^MM^M 535.2.3 ®%\m%iztttzmm&M 55

5.2.4 mn-zmmztttzmffiWiM 58

5.2.5 mm'ii'M^nimm 645. 3 '^mi-oZHMoyym 66

6. ttA 102


UJ S? 106

107

109

vi


Contents

1. Introduction 1

2. Safety Design Concept of an HTGR-hydrogen Production System 3

2. 1 System Arrangement 3

2. 2 New Anticipated Events for an HTGR-hydrogen Production System 4

2. 3 Safety Design Concept against Fire and Explosion 7

3. Survey of Safety Design Regulations against Fire and Explosion 10

3. 1 Safety Design Regulations for Nuclear Power Plant 10

3. 1. 1 Regulations in Japan 10

3. 1. 2 Regulations in Overseas Countries 12

3. 2 Safety Design Regulations for Non-nuclear Chemical Plant 14

3.2.1 Kouatsugasu Torishimari Hou 14

3.2.2 Syoubou Hou 15

3.2. 3 Sekiyu Konbinato~tou Saigaiboushi Hou 16

3.2.4 Roudouanzen-eisei Hou 17

3. 2. 5 Safe Distance in Japanese Regulations 18

3. 3 Comparison of Safety Design Regulations 19

4. Proposal of Safety Design Criteria against Fire and Explosion

inside the Reactor Building (R/B) 38

4. 1 Occurrence Prevention 39

4. 2 Countermeasures for the Beyond Design Basis Accident 40

4. 3 Proposed Safety Design Criteria for the Accident inside the R/B 41

5. Proposal of Safety Design Criteria against Fire and Explosion

outside the R/B 45

5. 1 Fire and Explosion in the Hydrogen Production Plant 45

5. 1. 1 Explosion Caused in the Vessel 45

5. 1. 2 Fire and Explosion in the Plant Area 48

5.2 Safe Distance 50

5.2. 1 Distance against Large Scale Pool Burning 51

5.2.2 Distance against Fireball 53

5.2. 3 Distance against Pressure Vessel Burst 55

5.2.4 Distance against Vapor Cloud Explosion 58

5. 2. 5 Proposal for Reducing Safe Distance 64

VII


5. 3 Proposed Safety Design Criteria for the Accident outside the R/B 66

6. Conclusions 102

Acknowledgements 106

References 107

Appendix Development of Vapor Cloud Explosion Analysis Code 109

Vlll

JAERl-Research 97-022

l . u:

mit

( W E - N E T )

Yt>

T

< » u

x-litei>o

- 1 -

JAERI-Rcsearch 97-022

LTIt,

- 2 -


< © u x < HUx.^. J;

I A I -3 1=1 «>- s c t&p]±t h z. fc «t «9J®

<3>

2. I

- 3 -


2.

ttz,

2.2

9

> h TS!ig L 7K^«i^

(D ^ Ltz h U f- 0

ttz.

a vt-^x,

- 4 -


Z.ttU-

o ^

t@yp [ -r [p

Ltfc,

7 3 - .

/ /

«t •? {z

•> x f A £ ^Il^j te n x h X*mikt

S W ^ * (PA)y

- 5 -


t

0

«5

-5 PS

- 6 -


2.3

, Fig.

(1)

(2)

<^ >

>

7 7 - ,

- 7 -

JAERI-Researeh 97-022

C/V R/B

R/B : Reactor buiIding

C/V : Containment vessel

I/V : Isolation valve

ECR : Endothermic chemical reactor

SG : Steam generator

( a ) e n d o t h e r m i c c h e m i c a l r e a c t o r i n s t a l l e d i n p r i m a r y l o o p

7/ / / / / / / / /

Feed water

Product gas

Feed mater ial

Product gas

Feed material

SG

*— Feed water

Secondary h e l i u m p i p i n g

R/B

C/V

I/VECR

SG

IHX

Reac to r b u i I d i n g

Con ta inment vesse l

I s o l a t i o n v a l v e

Endothermic chemical reactor

Steam generator

Intermediate heat exchanger

( b ) e n d o t h e r m i c c h e m i c a l r e a c t o r i n s t a l l e d i n s e c o n d a r y l o o p

F i g . 2 . 1 S c h e m a t i c i l l u s t r a t i o n o f s y s t e m a r r a n g e m e n t

o f H T G R - h y d r o g e n p r o d u c t i o n s y s t e m

- 8 -


m*m

o

o T^M? g£

<*i G

G "?!ft ^I+, W.

SIu

5 »K? G

_ ^ Mil

SK IS-

<

|G

1n

o

CDDO

o

CJ3

X

-a

a)

toDOca

a>ocoo

toCD

- a

cuCO

cvi

DO

- 9 -

JAKRl-Research 97-022

3.

t izt

3.

3.1.1

- 10 -


o L ^ U

3. 1 ( c ^

Table 3. Kc J; 9 Jc

JARRI-Rcseuah 97-022

j; 9

3.1. 2

L t , I A E A c Z ) FFire Protection in Nuclear Power Plants J (9)

^'Evaluations of Explosions Postulated to Occur on Transportation Routes near Nuclear

Power PlantsJ " 0 ) ^ ^ o

te < -t% C 1 1NRc©s

9

rnftitz

D i s t a n c e )

- 12 -

JAERl-Rcsearch 97-022

C t (c J;

lpsi

W T N T

^ f i F i g . 3.

(3 .1)

<n) ^ ( 3 . 1

tm^LTI>^o cni ts m:T-

LTl >£/A HPI L/c pJ^

- 13 -

JAKRI-Research 97-1122

3.2

>

> h 9 > h i L

3. 2. 1 ( 1 3 )

2 kg/cm2G

y bX\t

(JilT, — (WT.

- 14 -


3. 2 iZ

'JlWiHis.

3 .2 .2 1 4)

, y ^ y -

lS:. Br

- 15 -


3. 3

Ix© C 5 x LTl

3. 2. 3 SMl ^ > f > - h ^ ^ •a- ( i s )

g U^ L f c A ^ i

LT,

- 16 -


3.2.4

y Y

3. 4 IC

- 17 -


3.2.5

LT, -/?>

3. IKffs

3. 5 f

ic, Ai*

=> >

o.

O. 125kg/cm2

0. lkg/cm2 i l ^

>t*BiJ{cfc(j-5f|--gfl|ilJ[E 0.

- 18 -


8)

r =0.576(KW) 1 / 3 ( 3 . 2 )

^ r : , W :

K .• rt

tm Li

Fig. a 1 iz7F

ig. 3.

WTNT = W Oe <P r H o

H( 3 . 3 )

T N T

T N TOi i f f i lK=l , OOOkcal

/kg). , e .

^ r (TN

£0.064

3. 7 (C/K

(r/WTNT1'3)

r = 0 . 5 7 6 (Wo

: T , e = 1 . 0 i U Fig. 3. 1

14.4^^(3.3)^^;At"Si,

. lkg/cm2

( 3 . 4 )

6. 4

3. 3

3. i sen. 2 >

- 19 -

JAERI-Rcsearch 474)22

, T t

ix, m

X 6 C tL T

tt-i- z.t ts.z>o z.ttz,

tztk \zir%> Z. t

- 20 -


Table 3.1 Safety design guideline for fire and explosion in nuclear power plant

±

LT

t

?•

© Ri«8t4^K«r)l?iB! L

- 21 -


Table 3.2 Safety design guideline for fire and explosionin kouatsugasu-torishimarihou (13) (1/3)

t

i -

— <_

- 22

JAERI-Researdi 97-022

Table 3.2 Safety design guideline for fire and explosionin kouatsugasu-torishimari-hou (l3> (2/3)

i 0

t

19;# (Brtf^l^O

XflicJg-

t

.if x 1 o

- t

t

19!

- 23 -


Table 3.2 Safety design guideline for fire and explosionin kouatsugasu-torishimari hou (13> (3/3)

a

C i.

, m m -®ffi

24 -


Table 3.3 Safety design guideline for fire and explosion in S y o u b o u h o u < M ) (1/3)

Ci

mm,

it ti

^ 4 stil

:JS i;

> ? ic

- 25 -


Table 3.3 Safety design guideline for fire and explosion in S y o u b o u - h o u < l 4 ) (2/3)

fifc

ih

. 15m

z £

s -IttflXft

- 26 -


Table 3.3 Safety design guideline for fire and explosion in Syoubou-hou (14> (3/3)

> l= J;

W'Xffife

U - hit. > ^ 'J-

ft.

- 27 -

JAERI-Researdi 97-022

Table 3.4 Safety design guideline for fire and explosionin Roudouanzeneisei-hou (lfi) (1/2)

K

W

i t

\:/v, xmm,

tu

. S

v -

T , WESIt* Ltt btt

- 28 -


Table 3.4 Safety design guideline for fire and explosionin Roudouanzen-eisei-hou < 1 G ) (2/2)

tiu

* »Ef©«ffl 4 li L it I

itt

- 29 -

JABRI-Research 97-022

Table 3.5 Safe distance in Kouatsugasu-torishimari-hou ( 1 7 ) ( I B ) (1/2)

m LTli. Siig^

r =0.576 (K • W) l / 3

r :K : #

W : S!!igS

0. 1 kg/cm2 tltz

>

1. IXWBIB

ax

(a) ^

(b)

- 30 -


Table 3.5 Safe distance in Kouatsugasu-torishimari-hou (1 7) (I 8) (2/2)

m m *& »a2. B T I * • raitC/v^ftxWfllB

MM^M (KW) *n.2 xlO7 H

3.3 0 0 nf*A:(i3 0 0

1 ( D i ^

4.

L, LT 8

5.

t

- 31 -


Table 3.6 Safe distance in Syoubou-hou (M> (1/2)

I I

1-1

m

Eg

tztzL,

U

5 0 m , 1 .8D ( L )

2 1 ° C ~ 7 0 ° C 4 0 m s 1 . 6 D ( L )

70°C£l± 30m, 1.0D ( L )

1-2

1 . 8 D

2rc~70°c 1.6D

1.0D ( L )

D :H :L :

(m)£ (m)

(m)

m2h a<, 4000kcal/

1.8D> ^/v U >

- 32 -


T a b l e 3 . 6 Safe d i s t a n c e in Syoubou-hou (14> ( 2 / 2 )

m m

(a)

(b)lOmJiLt

m

C_

(a)(b)(c)

(e) # ;

1 - 2

(a)(b)

(c)

2.

(a) +°

(b)

fCi W L^ i f tl\$t£ b ^

5m txfffllBj

: 20mJil±

tfl&o 1 / 3 j

33 -


Table 3.7 Explosion contribution ratio (1 9)

mmm (%)

1 5

1 0

8

6

4

7-fcf-U>, tf-=Wb7-trf-U>\ ILMimM

TtaUy, 7-trh7^fhF\ ^ y x >

/?>, 7"^>, yf l /> , ^ ^ - ^ ^ ^ ^ > ^ >

•i-7-y-, 7-tr^>> -> p^\ + >> i^|kt"-;b

- 34 -


cco

CO

CD

CJ

-ocCO

BCO

COCD

co

DO

COCO

CoCO

oo.X

cCO

CO

CO

COCD

COCO

ocj

COCO

oCO

CO

o

CO

CO

CD

CO

G

A

^

G

K

f

Gitt H

by

G 1 ^mm- y nun

G mfc H

pG

S5 is

fl tyty

G

G 5&

G "K

G &

m M ^ -R 93 #Jm s m m

G

mG HEH »J

G

an

• i )

H

+< is

G

Ei

^ IF* G -t) ..Kl ig M GK> iff ^ '.^

S 1^ G §5s m « ^

Gmis

- 35 -

JAF.RI Research 97-022

1000

100

(0

a.

•ess

ur

o10

\\

\

\\

10 1001/3Scaled distance : r/WTNT / J (m/kg1/J)

Fig. 3.1 TNT charge blast ( r : real distance from chargeWTNT : charge weight of TNT)

36 -


i- msm.

L mam

mi

F i g . 3. 2 S a f e d i s t a n c e i n t h e c h e m i c a l p l a n t

- 3 7 -

JAERl-Rcsearch 97-022

4 .

il.t,

(I)

(Fig. 4.1

(Fig. 4.1

(Fig. 4.

(2)

(Fig. 4.2 (D)

. XVi

»5iA L T

- 38 -


4. 1

t

a

$.£ LT L.

- 39 -


m

L T

Ltli,

4.2

Ct

, S

- 40 -


0 ttz.

>

y

=>y

z. t le . 3 no&&mmfim&i'?> cttuz tz#>, mm

LTli,

£

iiU

ttt&

tzt-i,

«fc

4. 3

- 41 -

JAERl-Rescarch 97-022

U l^l4fft

- 42 -

R e a c t o r bui I d i n g

Nuclearreactor

Ci rculator

Chemicareactor

Steamgenerator

Steam!drum

Product gasFeed materia

mjo

Feed water

• _._.._.„ _.__.....„,

R u p t u r e o f p r o d u c t g a s p i p i n g

R u p t u r e o f f e e d p i p i n g

S i m u l t a n e o u s r u p t u r e o fr e a c t i o n t u b e a n d h e l i u m p i p i n g

F i g . 4. 1 E x p l o s i v e gas f l o w pass( c h e m i c a l r e a c t o r i n s t a l l e d i n s i d e r e a c t o r b u i l d i n g )

R e a c t o r bui I d i n g

Nuclearreactor

Ci r c u l a t o r

IHX

Ci r c u l a t o r

Chemicalreactor

Steamgenerator

+ Product gas- Feed material

Feed water

S i m u l t a n e o u s r u p t u r e o fr e a c t i o n t u b e a n d h e l i u m p i p i n g

73o

o

F i g . 4 . 2 E x p l o s i v e g a s f l o w p a s s( c h e m i c a l r e a c t o r i n s t a l l e d o u t s i d e r e a c t o r b u i l d i n g )

JAERI-Rescarch 97-022

5 .

• >

9

5. 1 7K^^it^7 y b

y h

5.1.1

^i6

, tLTf^t^Ci

- 45 -

JAFRI-Research 97-022

L ^ L > AU S

(2)

(4)

M 1

- 46 -


(5)

t

- 47 -


fffiU

5.1.2

U -y

7 7

mm,

(3)

L/c «9, L T

- 48 -


u

ig. 5.

(1)

y

tt

(2) 2

, m


B L E V E (Boilng Liquid

Expanding Vapor Explosion)i^9o ®%1)<BLEVE\zJ:i0i&mZtlZ£, ix

t 11 So

5.2

> b

, mm

- 50 -

JAERl-Researeh 97-022

z. t u&m

5. 2. 1

: : T , E :K1) , T : ^C^fiS(K). 0

a :

(5.1)

. 669x 10-

(22)

E = R , 0 (5. 2 )

- 51 -

JAE-RI-Roseardi 97-022

5.

t

- 5 ^ ^ 3 >^ U -

1 , r m7 tan [1^I

- ir nil

(5. 3 )

A = ( 1 + n ) z + m 2 , B = ( l - n ) 2 + m 2 , m = H / R , n = r / F U H : X

) , R : X'&¥mm) > r : X

(2)

> ^ U -(25) ^ > ^ U - M i

^ ISOF CGS.6°O JCB# 350F ( n o . 7(2G>

- 52 -


y? >)-

5. 2 w S t p ^ - ( 2 7 \ Hymes«Fig. 5. 2

5. 2 ^ ^ W 4 . 0 k W / m 2 ^ T ^ Fig. 5. 2

(28) m^

LT2.

(3)

5.

> ^ u -

5 . 2 . 2

(1) iM

^ X

tjrt^¥Li

-<^-*-(29)

= ( JL ) 2

\ D : 7 7^r-V

5 4 )

. r : y

5. 3 tc^-To (

t\

- 53


5. 4 iz (33> ( 3 8 )- ( 4 2 >

D = 8. 6 8 X m , l / 3

D = 6 . 2 2 x m (l / 3

D = 6. 0 x m , I / 3

( 5 . 5 )

( 5 . 6 )

( 5 . 7 )

7

, Table 5. 4

ig. 5. 3 (CTK

o i l . T , 7 r -f -V - ^ -

9

f i , 30,000

30,

Lihou Jhonson b © H S I I g ^ i fc— i

, 000kgW±T{i RobertscD^^, 30, OOOkgJ T

TJiLihou

t =2. 5 7 xm fl / ( i

t - 0 . 4 5 x m , l / !

, t : ^

( m , < 3 0 , 000kg)

( m , ^ 3 0 , 000kg)

^ m f

( 5 . 8 )

( 5 . 9 )

(2)

1 \zt%> z. £ !)<>&% t

- 54 -


\ t :B#rH1(s) , E

ig. 5. 4{

7 r J V-tf-

t x E 4 / 3 = 5 0

Hymes

(3)

, 7

5. 2tfcjg (i375kW/m2

t^m t x E 4/3 < 5 0 0 4 V-X-

5 . 2 . 3

t 60

U=( P i - P o ) V

7 - 1(5.10)

- 55 -


C C t , U :(Pa), V : ^ 7 :

Fig. 5.

$ 3l;Xh 6o

R = r / (2 U

Pn

, Fig. 5. 6

(5.11)

Po

\ R : *>r

- ( J ) , P : ^

(5.12)

, U :

5.5 a,

Fig. 5. 7 t c ^ f « t 9

5. 5

(2)

ig. 5. 8

- 56 -


3m—1. 6m. 8m~l.

20.

ig. 5. 8

U -

, JilgjcJ:

2. 11. 3kPa

11.3kPa

ig. 5.

it

^ 2 lOkPai ^

Ikg/cm2(9. 8kPa) ^ . N R C tpsi(6.9kPa)

- 57 -

JAF.RI-Researdi 97-022

(3)

. 5.

5. 2. 4

, tits, . Table 5.

A PQ =

k M(1

k —

M : ^T-ftCkg/mol). R :

) ( 1 + )RT 2

aCmVs), A : BtiW©Bfr®S(m2). P

, JEE

a), T : / /xk : it&Jt,

(r>2)

- 58 -


q=M ( H i - H 2 ) / L

Z.CX\ q:

t°-(J/m3h

V =PL

\ V : ^ ^

P : /

(2.

M :

K T i - T

( n i t ) ' / !

K :

ii:>ft LT(i36m3/mVs (3.

(5.14)

i 3 ) , H i :i

°-(J/m3), L

. n

<52)

(5.15)

t : NF

5. 7 (c^- f o < 5 S »

< IT- >

- 59 -

JAI-RI-Researdi 97-022

9

In o yo i\\C=

: C T , C :

y : ^ * ^ ^ J ^ ^

exp

, a , (iTable 5. 8 (Oi

(2 a

Q : ^

: z

[exp I - — ( — )2} +exp2 a z

u : JHi§(m/s)

, z :

- ^ (m)

—( —2 o *

(5.16)

J ; < 9 , F i g .

Q exp T } exp { T ~ } Io

i o

(5.17)

A = q A

B = qB

- 1

- 1

(5.18)

(5.19)

. QB> , Table 5. 9 Kffs

Fig.

h+zl e r t (

<«'< -JIT; » - e r ' ( " j ^ T > < ' • > ^(5.20)

- 60 -


k t :

A , = q A {^AU

B , = q B {</>BU

x = u U i=n , h=0.

, £ :

a"

K n: y Ufa

(5.21)

(5.22)

(2)

m^H Table

. Table

(S7>

M * = a + b l n ( L * ) + c { l n ( L ' ) } 2 + d ( l n ( L * )

L t , P a s q u i l l

(5.23)

- 61 -

JAHRI-Rcscaah 97-022

% M* . L* =Li

K M : / J ' x i t f ) , Q : tfXjjfctfjSdnYsK u : HiSdn/s) , C * : # : * » £ .o ^/'c^ a> b> c> dliTable 5.Fig. 5.12

Piston-BlasUi(58>, 5.12

l l L , Fig. 5. 5 * ^

WTNT = W nH TNT

(5.27)

- 62 -

JAERI-Reseurch 97-022

M (4.18MJ/kgh 7 • TNTiR'$(0.4)

P . )

r r , E

ig. 5.14=b *9. Multi-Bnergy&T'liFig. 5.15«k

A P s = P - P o

Piston-Blast^Ttt .

(SB>

( 5 ' 2 8 >

(5.29)

Piston-Blast/iTtihigh reactivity © f t £ , Multi-EnergySt?

ig. 5.

16T'*<5o U Piston-BlastSTiihigh reactivity

o # E 1 ^ < ^ T N T / i i

- 63 -


tt&

CKFig. 5.

ttz,

, ^ (5 .28) . (5.29)R

K, Fig. 5.

5 . 2 . 5

t iXMth Ltz 4

17-5.

5.i3&c/Fig. 5.

zt

(1) 7 r -f

7 r -f i '

L E V E tt 5o

, B L E V E

^±, B

B L E V E U

- 64 -


Table 5. -5*ft«fifctS<h,

- 65 -


5. 3

9

(1)

(5.3)

(2)

5.1

i f S > ^ U - h

(3).10)~(5. 12), Fig. S- 5.5

(4) ^5

i f So^ ^(5.17)

5.L, ^(5.28)> (5.f J 4 fFig. 5.

- 66 -


LXli, (5. 14) i: (977 -y

- 67


Table 5.1 Emissive power of fire per unit surface area (22)

t> 7 vWcfo

* ] " / *

tltt

Jtnfe

n — +"V"

y ^y-;u

x^y-,u

LNG (y

Xf-ly >

7°O^>

7° D t° U >

n-7^>

^ 7 + /

>

D

4

5

5

4

2

6

8

1

7

1 3

7

7

8

j&fc

<

0.

8.

0.

1.

3.

1.

4.

9.

1.

5.

3.

4.

3.

2.

3

7

1

0

8

2

6

8

7

6

5

7

4

2

5

mm0

0

4

0

6

6

3

8

7

3

8

2

2

6

G

(k

D

1

1

1

1

1

2

1

7

4

2

2

2

W/m2 )

2=3 0

2. 7 9

7. 4 4

5. 1 2

2. 7 9

6.9 8

8. 6 0

5. 5 8

9. 7 7

1. 6 3

5. 5 8

0.7 0

2.0 9

2. 0 9

4. 4 2

D : (m)

- 68 -

Table 5.2 Effects of thermal radiation (2 7)

to

I

Radiation Intensity(kW/m2)

37.5

25.0

12.5

9.5

4.0

1.6

Observed Effect

Sufficient to cause damage to process equipment

Minimum energy required to ignite wood at indefinitely long exposures

Minimum energy required for piloted ignition of wood,melting of plastic tubing

Pain threshold reached after 8 secSecond degree burns after 20 sec

Sufficient to cause pain to personnel, if unable to reach coverwithin 20 secHowever, blistering of the skinCsecond degree burns) is likely0% lethality

Will cause no discomfort for long exposure

>m73

Table 5.3 Survey of experimental researches on fireball generation

Scale

Small

Large

Researchers

Fay and Lewis (30)

Hardee et al. (31)

Hasegawa and Sato l32)

Lihou and Maund l33)

High (34)

Hardee and Lee ( 3 5 )

Maurer et al. <36)

Johnson et al. (371

Containment

Soap bubble

Polyethylene bags

Glass spherepressurized

Soap bubbles

Pressurized tank

Pressurized tank

Fuels

CH4C2H6

CH4

C5H12

C4H10CH4

LocketFuel

C 3118

C3H6

C4H1 0Cans

Fuel Massmf(kg)

20-190(cnf)

0.1-1

0. 3-30

1. 5-6(g)

1-5000

1, 29, 454

0.1-452

1000-2000

Durationt (s)

0.4-0.8

1. 8-2. 4

0. 8-1. 7

0. 5-1. 00. 4-0. 7

1.5

4. 5-9. 2

DiameterD (m)

0. 2-0. 7

1. 5-2. 2

2.7-15

0. 4-0. 80. 3-0. 6

40

56-88

Emiss. Power(kW/irf)

3220

123

110-413

320-375

73

Table 5.4 Empirical relationship of duration and diameter of fireball

Scale

Small

large

Litera-ture

Researchers

Fay and Lewis (30)

Hasegawa and Sato (32)

Moorhouse and Pritchard <38)

Lihou and Maund (33)

Lihou and Maund <33)

Williamson and Mann (39)

Roberts u0)

Pietersen (41), Pitblado(42)

Fuel

C3H8

C5H12

C5H12

CH4

C3H6

C3H8

Data Source

Experiments

Experiments

Hasegawa and Sato

Hardee et al.

Maurer et al.

Hardee and Lee

Literature and model

Literature

Diameter(m)

6.28m,1/3

5.28m,° 277

5.33m,° 327

6.36m,° 325

3.51m,'/3

5.88m(1/3

5.8m,1/3

6. 48m, °- 325

Duration(s)

2.53m,I/6

1.10m,0 181

1.09m,0- 327

2.57m,° l67

0.32m,1/3

1.09m,'/6

0.45m,1/3

0. 825m, ° 2o

m2E50

m, : Constant initial fuel mass(kg)


Table 5.5a Adjustment factors for cylindrical vesse (4 1)

0.

3.

3S

5<

R

RRR

<0.

S3.

3

5

Mult

411

iplier

. 0

. 6

.4

Table 5.5b Adjustment factors for slightly elevated above ground (44)

R

R S1.0

1. 0< R

M u l t i p l i e r

2.0

1. 1

- 72 -

T a b l e 5.6 V a p o r cloud p r o d u c t i o n m e c h a n i s m for d i f f e r e n t c o n d i t i o n of c o m b u s t i b l e m a t e r i a l s

w

Am

/nn

Am

/mt

-ar .;E

ffi

E

m

m E

n E

B.

m it :A

m70


•R

LO >—I •—I .—It— CO OO OOCT3 CT> CX> CT3

H 04 XW X

O CU pcj S <— td < W _)

-uVJ

KGAm

r| p

X o X

co

COCOBO

CD

-a

A

ifiOOt— t—

G

1GK

li

M an

> QCO < J

Q T3 OI —> W

O W O

o <\

ca A

AJG

K G

G -a —o 3

K 3CO

GO Q

CT5 - I - ]

•t.

1mGR

O O

Gs

G Gin/1 r±->lay JQ

G G GK K K

-Hfr

- 74 -

Table 5.8 Atmospheric stability (5 3)

I

mm (u)

m / s

U< 2

2 SU< 3

3 ^ U < 4

4 Û< 6

6 Û

01*« ( T ) kW/rrf

TÔ. 60

A

A - B

B

C

C

0. 60 >T^0.30

A - B

B

B - C

C-D

D

0. 30 >T20.15

B

C

C

D

D

0.15>T

D

D

D

D

D

mm$L%m (Q) kW/nf

-0.020

D

D

D

D

D

- 0 . 020 >Q^-0 .040

G

E

D

D

D

-0.040

>Q

G

F

E

D

D

jo

A-B. B-C, C-D(i^n€'tlB> C>

Table 5.9 Diffusion parameter in the method of Sakagami (5 4)

Ien

£ 5E(F )

(D)

(C)

(B)

h (m)

0.5

10

20

30

0.5

10

20

30

0.5

10

20

30

0.5

10

20

30

0A

4.78X10-'

4.78X10-'

4.78x10"'

4.78X10"2

1. 48x10"'

1. 09X10-'

1. 01X10-'

0.97X10"'

4. 50X10"3

2.12X10-3

1.80X10"3

1.61X10"3

1.12X10"3

2. 52X10"4

1.78X10-4

1.44X10"4

/~qA

4.26

4.26

4.26

4.26

1.56X10'

2.18x10'

2.37x10'

2.48x10'

7.59x10'

1.59X10'

1.88X10'

2.09x10'

2.77x10'

1.24X103

1.73X103

2. HxlO3

0B

4.20X10"'

4.60X10-2

4.71x10- '

4. 77X10"2

1. 10x10-'

2.46X10"'

3.00x10"'

3.29x10"'

4.25X10"3

1.48X10-'

1.98X10-2

2. 34X10"2

1. 30X10-3

7.20X10"3

1.10x10"'

1.40x10"'

Q B

3. 50X10-'

2.93X10"'

2. 86X10-'

2. 83X10-'

5.30

1.02

7. 00X10-'

5.65X10"'

3.48x10'

2.87

1.61

1.14

3.73X102

1.18X10'

5.19

3.21

m

50


T a b l e 5 . 1 0 L o w e r l i m i t o f e x p l o s i v e f u e l - a i r d e n s i t y (B 5)

TW|,y

j-9 J -Jl

x-9 y

if- u >

* *

1

1

%

2. 5

5. 0

2. 5

3. 3

3. 0

2. 7

4. 0

/

/

m K «

+ •+>">

>-tf" y

9 y

9 /-H

1.

2.

2.1

1 .

6.

>

8

1

4

2

3

0

7

Table 5.11 Constants in Eq (5.23) (5fi)

B

D

F

a

0.844154

1.55211

2.31381

b

0. 0438042

0.0399075

0.0492857

c

-0. 0181337

-0. 00725134

0.0128593

d

0. 0035282

0.00325316

0.00277179

- 77 -


aoCOOO.X

oo

oex

COCT3

I

AV

y

O O

CO

o

ico

LOa>

P3Iao G

G

_J

#1

O

E-

- Q

H

<n o (d)

- 78 -

Table 5.13 Safe distance against four anticipated accidents at HTGR-hydrogen production system (1/2)

I

E=R (

E :

R f .•( E q . ( 5 . 3 ) )

2. 3 k W / m1 7 5 °C ( 3 > ? U - h:

17 5m

= 3 7 5 ( D / 2 r ) 2

Eq . (5. 5) ~ ( 5. 7))D :r :

t : mE q. (5. 8 ) , ( 5. 9 )

t x E 4 / 3 =5 0 0

B L E V E

8 5 0m

E q.(5.10) ~ (5 .12 ) . Fig. 5. 6r Kfctf £«H£A P s

1 0 k P a

- 5 0 OMJOi l^. Jt.^iitl. 3)

7 6 m

m50


CO

CO

s

CO

CO

B

o

o

DO

o

a)

ooas

CO

C

OOO3

03

inCD

8£

$W

JUx

m

K

A J

im

K' >A J

K

SiLid

mKS

•412Hi-

G'.0

-£>

• ^

3?

• > >

?N

i ^

r>GK

Hd

93

G

m111

Hd

^Ocu

62:_ i

CO

a

a

L O

* '

CT1

W

CO

L O

crw

iH

»fTio.

^ ^

A J

iCO

CM

a"aCDCO

oCML O

^ —

D"

W

93

mm

L O

^—'

crW

93^/!^ml

m

«ft

i t i

m

tnH

u

G•H

«HI

mIx

C OCM

L O

crw

mu

Jl-f

bo

uI

4—1

—

tn

t+d

i>

>I

HeLOJt-j l iIDE

i n

i r i

DO

• ^

* ~

CTDCO

L O

^-^

r

TOCO

i r i

cru

m

CL,

c>

'—1

iM

a6

oC O

-QO2,

A J

5siGO

<oT—(

a

20m

o

A J

tyGBO

<O

<or—H

93

"eoCM" • / •

-RA•*?\

"A

l|Bi

GfGu

93

ii

G

93

I'J

•E

G

Ulloa

m-ilna

CO

a

93

K

G

IfAJ

K8

j^AJ

£oC D

CO

I!II„

eo

CO

i n

~e IIco •—i

aL O

C D

II

S

BO

o

O2;• J

GUKIx^.

DO

( O

C O

C O

tnlni]

GIKIxm

mm

ao__,

IICM

6o

C O

II

*"•

Hd

aoC D

cn

LLUO H

S

C D

{•^

aoCJ5

CT3

- 80 -

00

I

-X'A

m2jo

Fig. 5.1 Accident scinario after leackage of combustible materials


1000

100

>

ca)

EO

CD'-TD

CO

rr 10

N

\N\

\

K

\

N

\pain

"N\K

s

3°

5C

1

Sx

\

\

burI

)%le

% let

:

s

\

s

'ns, to bare skin (2mm)I

lhality (average (

hality (aver

start of 2°

*< of bar

\

\

K

age c

burr

;lothin,

loth

s

ing

for blisterine skin

k

\

h\

s v

N

)

\s

\

NS

II

^ N

\

i

Ii

10Time (s)

100

Fig. 5.2 Tolerance time to burn-injury levels

for various incident heat fluxes (Hymes)'(28)

- 82 -


100

100 1,000 10,000 100,000 1,000,000

Initial fuel mass (kg)

Fig. 5.3 Comparison of fireball duration among severalproposals

- 83 -


1000

>inc

co

•+J

to

3 burns, to bare skin (2mm)

50% lethality (average clothing)

1% lethality (average clothing)

start of 2 burns

range for blisteringof bare skin

t x E4/3=500

Fig. 5.4 Comparison of tolerance time to 1% lethality

between Eisenberg and Hymes(28X43)

- 84 -


1000

1310CO

>

o

100

10

\

j

K\ \\\\

ii

\s

\

\\

I N \\\\\i

x

10 1001/3 1/3NScaled distance : r/WTNT (m/kg )

Fig. 5.5 TNT charge blast 11 (r : real distance from chargeWTNT : charge weight of TNT)

- 85 -


10

Q.

tn

<D

a.\-voI/)1/3

~EoCOc0Eb

0.1

0.01

1 \\

\

\\\

\

\

\

\

\

\s\

\ V

\\

\\

K0.1 1 10

Scaled distance : R

100

Fig. 5.6 Over pressure of blast from vessel burst estimated by gasexpansion method (44)

- 86 -


1000

coCL

COCO

>o

100

10

\\

N \

^ \V

\

\

N

s

TNT

Comi i — (U - ;

uafor

V.

methc

1

pressed g500MJ

as e nergy

s expansion methoccylindrical vessel

z_)d

> \

!

j

i

10 100

Distance (m)

Fig. 5.7 Comparison of blast for vessel burstbetween TNT method and gas expansion method

- 87 -


Maximum bending stress a b

<Tb=0.5(a/hrPa = short span of wallh = thickness of wall

0 10 20 30 40

Applied pressure : P (kPa)

Fig. 5.8 Maximum bending stress crb on four edges fixed wall

- 88 -

00ID

CD

b

CO

CD

+JCO

c_Q

xCO

50

40 -

30

20

10

00 10 20 30

Applied pressure : P (kPa)

40

16Pdh2

u b

7T{d 4 - (d -2 t ) 4 }

h = 80m

d=1 m>

i

^ ^ d = 1m,

d = 2m,

• —

t=O. 05m^/^

t=O. 1m

50

m

jo

Fig. 5.9 Maximum bending stress on single fixed bar


1.0E+4

1.0E+3

1 .OE+2

1.0E+1

1.0E+0

/AV,• / — / •

AA

z/' //)

/' /

//

/

?-}

/ /

/- / /' A s

/ / // AA

*

//////

A

/ // 77

A

A

/ / // ? /

z / /A A

A A A/ /

/

/—//

A s 1^ • /

c / //D ' A/E /

F :::

0.1 1 10 100

Distance of downwind from the release point ( k m )

Fig. 5.10 Diffusion parameter a for equation of Pasquill(54)

- 90 -


1 .OE+3

1 .OE+2

1.0E+1

1.0E+0

V)/' /A/ /

/)V/

/V////

///////

A

11

J/7

/ ,/

y

/ /z/

1i /

//

V A' /

/ // /

' //

/

I/

/f

/

//

//

/

)

1

/

/

y

> //

y

/

1 //

//

/

/

/•

Y

-

0.1 1 10 100

Distance of downwind from the release point (km)

Fig. 5.11 Diffusion parameter cr2 for the equation of PasquillMI (54)

- 91 ~

1to

1

T

jnsity

(

MS

Q

0.04

0.035

0.03

0.025

0.02

0.015

0.01

0.005

0

I1\

Pasquill ^ >

Sakagam/

i

•—i

Wind velocity : u=1m/sHeight of release point: h=0.5Atmospheric stability : FDistance of acrosswind : Y-0Height from release point: Z-Relea

—

se rate

i .

= 1 mVs

m

0

70

n

0 200 400 600 800 1000 1200 1400 1600 1800 2000

Distance of downwind from the release point (m)

Fig. 5.12 Comparison of estimation methods for ensity of combustible material in vapor cloud

0.3

0.25

0.2

.£ 0.15wcoQ

0.1

0.05

0

\

1=1

1

\

\

\

\

\

\

\

\

\

ADm

1\

=20m

" ^ .~~~

HeigAtmr

i t of relelonl-iorir-

ase poine+nkili+\/

t : h=O.5r

Distance of acrosswind : y=0Height from release point : z=0

n n

— '' •

— «, _ _

n

0 200 400 600 800 1000 1200 1400 1600 1800 2000

Distance of downwind from the release point (m)

m70

Fig. 5.13 Density of combustibe gas in vapor cloud released gas instantaneously


Q_

g 0.1w

CD

Q.

i_CD

ow00

~EocCD

E 0.01Q

0.001

Merea

Low

diucti

r re

'e<

mvit

activ\s

Vv\

\

activit

\

ity

s

\ \\ \

vy \\

\

\ \

\

s

\

\

\

\

\

\\

\\\

\\

\V

\

\

\

\

\

\

s

\\

0.1 1 10

Scaled distance : R'

100

Fig. 5.14 Over pressure of blast from a hemispherical fuel-air estimatedby Piston-Blast model(58)

- 94 -


100

0)(/)

o.(D

oww

0)Eb

10

§ 0.1

0.01

0.001

leve

lev

;l 1

i\

>e\

level

lev

lev

te\

re\

level

lev'el

0

IIT

\\T

7 \>

6 —

5

4

3 —

1

\ \\ \

\\

N\

\ \\\

\

\

\

s

I >

\

\

>

\ s

\

\ \

\, \

\

—

\

\

s\

s^ '"\ ^

0.1 1 10

Scaled distance : R'

100

Fig. 5.15 Over pressure of blast from a hemispherical fuel-air estimatedby Multi-Energy model<59>

- 95 -

I

sI

300

250

D_ 200

<D

150w

Q.

0) 100

o

50

111

!

I?iii

i

s .

I

\

" 1 N 1

Piston-blast

Multi-E

— •

nergy

— —,

Detonation blastMethane 100ton

• — — - — i

m

73

200 400 600 800 1000 1200 1400 1600 1800 2000

Distance from the center of vapor cloud (m)

Fig. 5.16 Comparison of several estimation methods for over pressure of blast of vapor cloud explosion

Geometry factorEmissive power

* (estimated by Eq. (5. 3))Rf (see Table 5. 1)

I

Operator2. 3kW/m2

Thermal radiationE = Rf <t>

( Tank )

V-—A

Hm70

S a f e d i s t a n c e : r

F i g . 5. 1 7 S c h e m a t i c i l l u s t r a t i o n o f e s t i m a t i o n m e t h o d o f s a f e d i s t a n c e a g a i n s t p o o l f i r e

Diameter : D (estimated by Eq.Duration : t (estimated by Eq.

(5. 5)-(5.7))(5. 8)or (5. 9))

Firebal

I00

Thermal radiationE = 375 (D/2r)2

Stack

ReactorbuiIding

OperatorK

S a f e d i s t a n c e : r

7*

©

F i g . 5. 1 8 S c h e m a t i c i l l u s t r a t i o n o f e s t i m a t i o n m e t h o d o f s a f e d i s t a n c e a g a i n s t f i r e b a l l

8i

Overpressure S(estimated by gas expansion method,see Fig. 5. 6)

Burst

Stack

ReactorbuiIdingIQkPa

Operator10kPa Blast

>mso73n

Safe d i s t a n c e : r

Fig. 5. 19 S c h e m a t i c iI lustration of e s t i m a t i o n method of safe d i s t a n c e a g a i n s t p r e s s u r e vessel burst

Explosion of vapor cloud Formation of vapor cloud

o©

Stack

Overpressure A?%(estimated by multi energy method,see Fig. 5. 15)

ReactorbuiIdingTOkPa

OperatorlOkPa

Equivalentexplosivevapor cloud

Di ffusion(estimated by Eq. (5. 17)or(5. 20))

Explosive vapor cloud

Blast i Wind

Distance against explosion Distance againstdi ffusion

Safe distance : r

Release ofexplosive gas

Undergroundnon pressurizedstorage tank

m73

F i g . 5 . 2 0 S c h e m a t i c i l l u s t r a t i o n o f e s t i m a t i o n m e t h o d o f s a f e d i s t a n c e a g a i n s t v a p o r c l o u d e x p l o s i o n


o

CO1 _

JO

boI

o

o

o

a.o

o

- 101 -


6 .

6.1

y

z. t

Table 6.2 \z^f

- 102 -


11 u

fcffl^-tSl

9 L /c

LTl i , ^tnJ tc, It

- 103 -


CO

co

o-oo

aj

o

_3

co

Q.Xaj

-aca

DO

CO

CO

a>

mG

G

G

iff

44 ^|is is

*

GG

G 5 ^G

G

1544

15G

G1S

G

onumwmwOO CO

Q

H

1544

.1G

Q

CO

G

G iSK

G-K*

m

K

G

K

I!&K

ffi

Aim '

Una

<P K

mm

K

I!&K

- 104 -


o+->u

•s3O

COC

oto

CO

•f-H

8

oco

I

+(CD

T 3

CO

mG

IDD

"0

G

mI

"0

G

A

NX

G

A

G

is•K

ml- G

G mPi flf

I?

"0

m

G

ifEg

Pift

NX

•'0

NX

"0

gGA

^ %

i

nift

GJL.

A

ft

!1

G

A

ft

IE*

G

mG

tilIf

PI

iG

A3

"0mG

G to

NX

G G

.. # ^G to

G

9GnA

wG

NX

"0

G

G to

Gi

IS!Sir! ffi

IS ^ &4< -^ +

•E §&

W S|} A

^ « ^

- 105 -


itt> i^-T U > ^

- 106 -


(1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

(9)

(10)

(11)

(12)

(13)

(15)

(17)

(18)

(20)

(21)

(22)

(23)

(24)

(25)

(26)

WM jE . t fife, x t w U ^ - U t ' i - , 7_, 4 (1995)

Tsuruoka K. e t a l . , Trans. ISIJ., 23. 1091 (1983)

IAEA Safety Series

ffe, J. At. Energy Soc. Jpn. ,38, 835 (1996)

ffe, t£ 5 01/j^j • x*/i/^-ftffi•> > +° v o A35 (1994)

1 (1994)ibid.", ^/StilKStt, 79 (1994)

Safety Series No. 50-SG-D2", IAEA .Vienna (1992)

Regulatory guide 1.91", NRC .Washington D. C. (1978)

86 (1983)

9623.85, (1996)

Guideline for the protection of nuclear power plants against pressure waves from

chemical reactions by means of the design of nuclear power plants with regard to

strength and induced vibrations and means of the adherence to safety distance",

Germany, (1976)

, 1 (1991)

33 (1994)

\ 3268 (1993)

',%-'&m. .21 (1991), 105 (1991)

299 (1991)ibid.",

Jasber Singh,

59 (1974)

19 (1983)

39 • 159 (1993)

, 484 (1994)

3515

K7'-y 9', T-9 J iibid.", f ) / y X f A , 431 (1994)

« it ftii, a*mm¥£J:£mftmmtmm, 585 ci988)1995 ASME Boiler & pressure vessel code", ASME, Section HI Division 2, 207 (1995)

(27) "Guidelines for chemical process quantitative risk analysis", AlChE/CCPS, NY, 161

(1989)

(28) Hymes J. ."The physiological and pathological effects of thermal radiation", SRD R,

U.K. Atomic Energy Authority, 275 (1983)(29) nn.%mM&wmm&w, g±?-&\.\ 3515• 39• m (1993)(30) Fay J. A. and Lewis, Jr. D. H.. Sixteenth Symp. on Combustion, 1397 (1977)

(31) Hardee H. C. et al., Combustion Sci. Tech.. 17, 189 (1978)

(32) Hasegawa K. and Sato K.,Second Int. Symp. a Loss Prevention and Safety Promotion

in the Process Ind., 297 (1977)- 107 -


(33) Liliou D. A. and Mound J. K., Int. Chem. Energy Symp. Series, 71, 191 (1982)

(34) High R., Ann. NY Acad. Sci.. 15JL. 441 (1968)

(35) Hardee H. C. and Lee D. 0., Trans. Plant Tech., _2, 121 (1973)

(36) Maurer D. et al., Second Int. Symp. on Loss Prevention and Safety Promotion in

the Process Ind., 305 (1977)

(37) Jhonson D. M. et al. "Large scale catastrophic release of flammable liquid",

Commission of the European Communities Report, EV4T. 0014.UK(H) (1990)

(38) Moorhouse J. and Pritchard M. J., "Thermal radiation from large pool fires and

thermals-1iterature review", Int. Chem. Energy Symp. Series, 71 (1982)

(39) Williamson B. R. and Mann L. R. B., Combustion Sci. Tech., 25, 141 (1981)

(40) Roberts A. F., J. Fire Safety, l_ 197 (1982)

(41) Pietersen C. M. ."Report TNO Division of Technology for Society" (1985)

(42) Pitblado R. M., "Consequence models for BLEVE incidents", Major Industrial Hazards

project, NSW 2006, Univ. of Sydney (1985)

(43) Eisenberg N. A. et al., Nat. Tech. Inf. Service Rep., AD-A015-245 (1975)

(44) Baker W. E. et a 1., "Workbook for predicting pressure wave and fragment effects of

exploding propel lant tanks and gas storage vessels", NASA CR134906 (1975)

(45) "j$«I^ir, B # $ » m A4-52 (1987)

(46) "mmr.mmmi±m^ • mtm& JASS 5N fimmwimstK&v um^ >^ u - YJLW

B « ! S ^ £ , 47 (1994)

(47) "&%mh^y?*)-VmM\&WW,n*W&&&, 6 (1994)(48) "%mx¥1£1?, H #*»$#££. A4-23 (1987)(49) Hirsch F. G.."Effects of overpressure on the ear", Ann. NY Acad. Sci.,(1968)

(50) "An approacn to the categorisation of process plant hazard and control building

design", Chem. Ind. Assoc of U.K., Section 5 (1974)

(51) "$lfCD¥«\ B # } » m A5-58 (1987)(52) "?>£•)—V&£m<&ftffifflH*mr, i§;EE#x{S£t&£. 14 (1974)(53) "mnmm-Miwmw, g* ?-$\,\ 3515 • 39 • 174 (1993)(54) " I ^ T ; / j £ £ « £ $ £ M f i § § r i r , « ! i i K S } ± , 343 (1994)(55) i&± feUP, SS / /X , 19, 166 (1982)

(56) "4V£fe%Lfomik¥M I -7a*xM".im. 803 (1986)(57) "Guidelines for evaluating the characteristics of vapor cloud explosions, flash

fires and BLEVEs", AIChE/CCPS, NY, 112 (1994)

(58) "Yellow Book 1979", Committee for the prevention of disasters, Netherlands, (1979)

(59) Van den Berg A. C., J. Hazard Material. J Z _ 1 (1985)

(60) "Guidelines for chemical process quantitative risk analysis", AIChE/CCPS, NY, 88

(1989)

(61) "Rfr*6fl**t^ttffi'<> K7*-y ?", x ? J y X f A , 227 (1994)

- 108 -


=> -

L T , >

^ u

(D

(2)

- 109 -


(3) mm. M u l t i

M u l t i

, PHOENICS^CHAMPAGNE

- 1 1 0 -

(si) t

« 1 a2 a5 s1,1

n m8 5 RS]

ft H H)te It

f- Ifi fl.4 f* ft

*

T

7

X

-

fty

y

•y

T 7

*

h

' 7

t"

T

v/T

A

Ty

7

y

y

Sd *y

m

kgs

A

K

mol

cd

rad

sr

S 3

m

r.

«

m

«A-b

)tffl

ftUK

)) . IE ^J

t-^+H (t:#, .**»;P , «[ W *5i • , J l ^

4, ifi Hi, HM,h^1 i^ ii"xt. tit tfL

y 9 9 9 y ?**

* ft! Sy 9 0 9 y x^ -y •> x fi ffi

iN 8 ftit "1 «

><•y

* •

7

•?

• r

' S

-t?

f•y

* ft

j - )-

X 7J

-J

— P

r 7-

— > y

y ')* i - >? X

- y

?

V

— ^ IV

•v

y

IV

IV

Y

y

VK

A

y

IV

Y

Hz

NPaJ

W

C

V

F

ns

WbT

H

°Clm

Ix

Bq

GySv

ffiro si ftHft

s 'm-kg/s2

N/m2

N-m

J / s

A-s

W/A

C/VV/A

A/V

V-s

Wb/m"Wb/A

cd- srlm/m2

s"1

J/kgJ/kg

£ ft' / } , VSs, HIt • * } , »

i- y

« -f -t: iv Y

hi ymin, h, d

1, Lt

eVu

1 u=1.66054x 1O-" kg

* y-y/ < •

/<•'

-n+ 3\y y

7

u

X h D - A

— y

t- y yK

A

A

b

bar

Gal

Ci

R

rad

ren>

A=0.1 nm=10-'°m

1 bar=0.1 MPa = 10bPa

1 Gal=l cm/s ! = 10-2rn/

1 Ci = 3.7xl010Bq

1 R = 2.58xlO'C/kg

1 rad = lcGy=10 'Gy

1 rem=lcSv=10 ' Sv

ffsa1 0 "

10"

1 0 "

1O9

10'

10'

102

101

10 '

lO"2

i o - 3

1 0 '

io-'1 0 "

10"'s

i o - "

nX

•f

+

~r

r '

-b

7

r

J 1 • *

7

ii

aD

i]

y

y +i)

/

i A h

1-

EPTGMk

h

da

d

c

m

,t

n

Pf

a

(•it)

1. M\ 5(±

/ t t t f tW 1985if;pjfji;j;5c, t / i 'L , 1 eV

fc i t f l u Ofiftti CODATA O 1986^t#<g

l > -5. A s 11 •?,"(

3. barli, JISTIi«t(*mH:

2. jfi 4

r, barnfci

N( = 105dyn)

1

9.80665

4.44822

kgf

0.101972

1

i 0.453592

Ibf

0.224809

2.20462

1

tt /f 1 Pa-s(N-s/m2)=10P(tf T;O(g/(cin-s))

»lWit lm 2 /s=10'St(x h - 7 xMcmVs)

IH

/J

MPa( = 10bar)

1

0.0980665

0.101325

1.33322 x 1 0 '

6.89476 x 10-'

kgf/cm2

10.1972

1

1.03323

1.35951 x 1 0 3

7.03070 x lQ- 2

a tm

9.86923

0.967841

1

1.31579 x 10 :i

6.80460 x 10 •'

m m H g ( T o r r )

7.50062 x lO 1

735.559

760

1

51.7149

Ibf/in2(psi)

145.038

14.2233

14.6959

1.93368 x 10 !

1

X

)\»

1

It*

t

J( = 107erg)

1

9.80665

3.6x10 '

4.18605

1055.06

1.35582

1.60218 x 1 0 "

kgf' m

0.101972

1

3.67098 x 10s

0.426858

107.586

0.138255

1.63377 x 1O20

kW- h

2.77778 x 10-'

2.72407 x 10'6

1

1.16279 x 1 0 '

2 .93072x10"

3.76616 x 10 7

4.45050 x 1 0 "

caKItlft)0.238889

2.34270

8.59999 x 10s

1

252.042

0.323890

3.82743 x lO 2 0

Btu

9.47813 x 1 0 '

9.29487 x 1 0 '

3412.13

3.96759 x 10' '

1

1.28506 x 10-3

1 .51857x10"

ft • Ibf

0.737562

7.23301

2.65522 x 10'

3.08747

778.172

1

1.18171 x 1 0 "

eV

6.24150 x 10"

6.12082 x 10"

2.24694 x 10"

2.61272 x 10"

6.58515 x 1021

8.46233x10"

1

Bq

3.7 x !0'°

Ci

2.70270 x 10'

1

UK

ISW

Gy

1

0.01

rad

100

1

mWmm

C/kg

i

2.58 x 10"

R

3876

1

1 cal =-- 4.18605 J ( ,HW/J ; )

= 4.184 J (#Ht7->

= 4.1855 J (15 °C)

= 4.1868 JffSlB/S XT.

ffr-f*-*-- 1 PS (fA»i/j,)

=- 75 kgf-m/s

= 735.499 W

w

Sv

1

0.01

rem

100

1

(86if:-12H

n m u m npfi - International Nuclear Information System (INIS)

Documents

Transcript of n m u m npfi - International Nuclear Information System (INIS)

n *m * u m npfi - International Nuclear Information System (INIS)

Documents

Transcript of n *m * u m npfi - International Nuclear Information System (INIS)

n m u m npfi - International Nuclear Information System (INIS)

Transcript of n m u m npfi - International Nuclear Information System (INIS)