I l lKR010092

KAERI/AR-586/2000

ASME Section III Subsection NH

(A study on technical issues of materials and design bases inASME Section III Subsection NH Code)

A

3 2 / 48

ASME Section III Subsection NH 3£fi) $3.

2000^ 12-a 27«a

- 1 -

] ^ ASME Code Section III Subsection

ASME NHS *13J) 3 E 5 ] 7 ] ^ ^^-g-^- i - ^ S ' " ^ ^7}^

ORNL(Oak Ridge National Laboratory)^ ^7>^.JL^1- 7}^.S. § H . ^ f l ASME

NH SH7> oj-al SJfe- ^tfS-aJl ^

^t|.<^ ASME

* 1993^^1 M 5 R 4 . ASME NH^ ^A]-?] Code Case N-47^r 1989V4^Jg7M -g-§H£ 7fl^o) £6J5)^. ^ ylm^j 3.7]} 7^$%^. ^ ^ 1992^

Code Case N-47^f Subsection NHS ^ ^ € 1995\iS ^ - ^

60^ *r^7l:?H] rflt!- «)-§-ir.^1 et5]-2.2}(notch weekening effect)°fl tfltb °l«fl

3.%-3\SL

ASME SiE A ^

ASME NH5] 2]^!^-?] 1998

#oll cflsilAii 7]

- 2 -

Abstract

In this study, an analysis of evaluation report by ORNL on the technical

issues of elevated temperatures design guide line, ASME Code Section III

Subsection NH was conducted and a brief evaluation procedure of the

creep-fatigue damage was presented. ORNL published the report in 1993 and

reviewed the issue areas where code rules or regulatory guides may be lacking

or inadequate to ensure safe operation over the expected life cycles for liquid

metal reactor systems. From historical viewpoint of the ASME NH code

development, ASME Code Case 47 was changed much in 1989 edition, which

includes the stress relaxation behavior in creep damage evaluation. Afterwards

the 1992 version of CC N-47 was upgraded to Subsection NH in 1995 edition,

which is the same with that of CC N-47 1992 edition except few material data.

This report brings up the technical and regulatory issues that can not

guarantee the safe and reliable operation of the ALMR which got the conceptual

design certification from NRC. Twenty three technical issues were raised and

the settlement methodology were proposed.

Additionally, the status of items approved by ASME code subgroup of

elevated temperature design committee for the revision of the most recent 1998

edition of ASME NH was described.

3 -'

JEL

page

1. ^ § 5

2. ASME Section III Subsection NH^ 3i#•§•;*)) 7

2.1 tl^l-^ 7

2.2 *}<&$ g-^f. 28

2.3 sMtioVo> 3 2

3. ASME NH^ 7fl^ ^^l^fl^- 36

4. ASME NH l H^-s lS .^^- 3j7]-^ &<$ 38

4.1 3 l s . ^ ^ 5J7>^^> 38

4.2 3.%<£<# 5J7]-^S> 40

5. « 41

-^ 42

3. 1. 3J-3M -2-^slfe ASME NH «)-8- l -S.^ 75 2. 4 Afovofl tfl^ ^.^t 3 0

- 4 -

1.

AS. 1967\i ASME B&PV Code, Section III, Code Case 13313.^61 A W H 1975\! Code

Case 1592, 1977^ Code Case N-47-1: 7\% 31 # 3 ? ! iL&-§: *H 1995\! Subsection NH[1]

S. Hsv^d£lSi4. ^HJ31 Code Case N - 4 7 ^ f e 2 £ 7 ^ 4 £ 4 °J|*l)^r3. ^ 4

^r3.(Advanced Liquid Metal Reactor : ALMR) 7}7}°\]

-S31*131?! ASME Section III Subsection NH ^^]^

3j7>2f :£s i§H ^ ^ ^ ^ ^ ^ JL^oflAi ^ ^ s l f e ORNL^ oflul

£*])(issue)ir-l:

s | s ^ ORNL°1 ^«8t!: ^ 6 HASME'Subsection NH^I 31^^?i] xl^ofl xfit}^ y\y\ a f e

« a ^ ^ A S . ASME

4.

NRCfe

7171S1

^ 425

fe 375 °C

PVRC(Pressure Vessel Research

Council)7]-

CRBRP °J

ASME Subsection 4-§-

«!•§-

- 5 -

(3)

^. 23

^ ^ o i ASME NH l s]A}^^ 1998^ ^^^1^] °}o\)•& ^l?t ASME 2 H ^ j m i - s j %-S-oi ?]1^S]ZL X14. ^r ^ i

1999^ 5Ti°fl 7fl*l€ ASME 2 £ ^ti.zLf- ^ ^ S ] si a] ii:sAi[9]f- 7}^s. 1998\! a]^A5.JfEi 7}1 ^o]

- 6 -

2. ASME Section III Subsection NH^

2.1 ^(issues)

2.1.1

ASME

7ASLS. 60Vi

s l i 525,000

of

Material Property Allowable Design Data Curves for 60-year

Design Life)

300,000*1 #

^ a

a 1. s} fe ASME NH «!-§-*]

st

Smt

Expected Min Stress-To-Rupture

Thermal Aging & Weld Reduction Factor

Smt (bolting)

Design Fatigue Strain Range *

Average Isochronous Stress-Strain Curve

Table 1-14.4

Table 1-14.3

Table 1-14.6

Table 1-14.10

Table 1-14.13

Table T-1420-1

-

Figure 1-14.4

Figure 1-14.3

Figure 1-14.6

Figure 1-14.13

Figure T-1420-1

Figure T-1800

Cr-lMo#ofl

7171- 304SS

fe 36.82^- °

316SS, 800H flsflA^ 31.65^, 2.25

= 31.56^- for 316SS)

2.1.2 4 ° J 2 : ^7l 2:4°fl 4-§r aL-S-^'H^ # ^ 1 ^^KDegradation of Material

Properties at High Temperatures due to Long-Term Irradiation)

- 7 -

<% ^ s] ^ - g ^ -7l?>(60Vi) 2^4^ ^ $=£ 2:471 <?] ^(transmutation)

^ # 4 7eV£r 1 ^-^S] ^ i 3 ^ . o . S ?]5H 4 ^ 4 . oL S: 2 :43 ^ 4

^ 2:4°fl ^ ^ ^ A] #3f o] ofl 1 =. ^ o] ^ a^j 2)-^^Cf. ASME 2 £

7]^(mechanism)7l-

;a£ 2:4

10%

et 2 a p p m ( i atomic part per

million)^ « l - a :

450 °C «1*H4 ^^rsl^l S^r4. zte]i4 550 °C=H|-3]3. 4

Van der Schaaf §••& ^ ^ s ] 3 ^ - s ] S . ^^lHJ-^-g: 2 : 4 S^^ l^ i AISI 304

# § ° 1 ^ ASME

2.1.3 4 ° J 3 : ^7}-fY 1 «H|ol^o(| 21 ^ ^ a - i - ^ ^ l ^ 1 ^(Degradation of

Material Properties due to Long-Term Thermal Aging)

60V!

phase), Laves-#f

^Sl-1-(carbide)^ f ^ A S ?]*

^ E ^ e f l i ^ - S ^ -fi-A]- f- -

o]ofl 45} ^ ^ o i #±z\n € 4 . 304, 316 ^ Alloy

i£7> xj-g-^s. ^ ^ ^ ^slfe ^HMweak phased J L ^ ^ - H 7OV£ ^ ^ ^ ^ : ^*M?ltj-. o]0] 304 ^ ^ 6 ] ^ ^ 7<MH ^ - ^ ^ H}-

]^7j-(bainitic steel)4 V}^

. "885 #|^"fe ^ ° s ^ ^ Sife ^ ° H , ASME 3.

14 Grade

(tempering)^el

"knok down" ?l >(factor)«*l| tfltb 17} 1993^

ASME Code Sect.III ^ f ^ ^ s l ^ t l ^ ^^}» ai-jl 5&fe ^ ° 1 ^ , °1

oflo]^ cfloiE fe ALMR 60\i ^ ^ ^ 1 s^M- H: ^ sa-i- PJ# ^ ^ 1 ?1

0)^0]

2.1.4 4o> 4 : 4 ^ ^ ^ - ^ - S . <?l?t # ^ ^ 1 ^ t2}(Degradation of Material

Properties due to Corrosion Phenomena)

- 9 -

. ASME 3.^^ ZL

ASME N H ^ 4f-J2. Slfe- ?J1S7V ? t ^ E | ^ SI 4 . ° 1>

^ Siife- ^ £ Sfe # ^ ^ ^Hfl(compositional gradient)^!

^ # 4 -^^(crevice corrosion) ^ o | -¥•

-614. ASME

(grade) iEflo]e|i:7ov ^ ieflo]e|ii7o^l?l Alloy

, o]6|)

^(degradation)^ =t>l ^-tg-^j ^-^ .^ ^ 0 1 ^ c]oi] cfl^.

C-HOJE-1

2.1.5 4ox> 5 : ^ ^ 3 ] -g-g- ^ ^2]-7l^ol] 7 ] s t t 3).g. # ^ ^ l £ l Jf^(Lack of

property allowables based on current melting and fabrication

practices)

304 ^ 316 i6«?l

-§--§-*ieUair melting

practice)^!! ^s-f^ ^ ^ ^ ^ 4 . €^1) D l^°)l^fe a H cH§f

(argon/oxygen decarburized) ^ ^ - i - ^-g-«>al S14. °1 ^

H^(grade) ^

- 10 -

fe- 3 M 4 . Alloy 800^1 £ ^(modification)£ JL^ ^<>14. °1 # ! •£ •

ASME NH°fl

-§--§-, ^i^l^-^D 7fl •§--§• (electroslag-remelted) Grade 22#-i-

s.7}- ^ < + € 4 . 3L r °0-#(extrusion) ^ ^ 304 i B

fe -2-^°! £ ] ^ °«M| ^-^(cavitation)^r ^ ^ A ] ? ] ^ 5 ) 0 ^ ^ - ^ ^ 01 rf.

Grade 917O>^ -§-^7J"H°fl

^l7ov£ #±'&x}7} ASME

Grade91

2.1.6 *}<& 6 : ^ ^A^r •%•^£\ IS}- ^^(Degradation effects of small cyclic

stress)

^Kprecipitate-stabilzed fine dislocation microstructure)0]] 7]<y«!:C}-.

2.1.7 A}6> 7 : ASME NH °l* r ^ £ ° H A i ^ 3L^7l?l sf^(creep-induced failures

at temperatures below ASME NH limits)

ASME

- 11 -

371 °C o l ^ H ^ S 3.

4 $14. ^ °14 Tr4tt 4£°1 -§1 60^ ^ ^ ^ l W ^ r 343

316-371 °C

2.1.8 4°J 8 : -M^A] 3J^ §J ^db#^^lsl 4-g-(Use of average vs minimum

material properties in design)

•g- ^^ fS -g-7] ^ ^ ^ ^ s ) (Pressure Vessel Research Council : PVRC)°)l i

si 4 SIABI n

(bound) *fl^^- ^*i'H- ^ja.71- &-& ^r $14. ^^1] 1 ASME S ^

ASME NH-& ^^^1-^-^1 (isochronous stress-strain curveHH

014. c^uf ASME NH l

^ - ^ ^ 1 ^V4. ASME 5L^fe

^ NE Standard F9-5T[3]<>1]

- 12 -

7] H^

* 1 ^ £*8t"£| ^ l ^ f £# ££«]] ^5!=i 3H 4471

-M « 1 *

heat ^JS" l -^^S^-E^

^ ASME 2ES1 ^^f-

50%

tb fl Hit 2:451^1 &&4. Htb ^)^^4fe ASME NH ll 4 ^ 2i7l

ASME 3 S

1.8%!-

7H3. 1-^*1 tflAj ^xj - ^ ^ s j -g.A^| AiEH^ 2V*t ^-i-g-^} o^^ zie)jL

2.1.9 ^ 1 - ^ 9 : Modified 9Cr~lMo 7OH1 tfltb ^^1UJ-^ -?-^(Lack of design

methodology for Modified 9Cr-lMo steel)

ASME NH^l ^1^1^ ^£.2] ^^-fe Dfl - 7)1^^014. Afls. 7 ^ 5 } 7fls.7> ^

1- 711 ^7>^]<y ^ ? H € ^7> 514. Modified 9Cr-lMo %-& ^ ASME

llfe ^7fs i of Si^l^- ASME Sect.HI % ASME

. Modified 9Cr-lMo 7ov^ ALMR

4

- 13 -

Z])X\M. ^«T- < g ^ ° l ^ o ] x H &J1 $14. Modified 9Cr-lMo

H ^ 2.25 Cr-1 Mo

°1 *l)Sfe 593 0C4*]fe -8-^3 ^-§-^7]- 304 i^l^lefli # 4 ti]£§H; 482C °lA

oHHfe 2.25Cr-l Mo # 3 . 4 #7J ^ a.*a #£.7> a ^ , Inconel 718 ^>#

014. Se> o

^ Alloy 617°1 Modified 9Cr-lMo 7ov4 ^-S-°l U 1 ^ 4 4 . Modified

9Cr-lMo 7^4 7Hvo] Alloy 617-g- 3.^$) ^l*J#£<ifl nj|^- <g^=^- 3.7JI ^ 4 . ^

«fl Code case7> 617^1 tJ|«H 7fl*^ 4 Sftjl ^ ^°H 3HS] ^ ^ ^ - ^ ^ S ] ^ ^

a ! 3 € 4 $14. °1 S ^ t Modified 9Cr-lMo ^ ^ §74-1- 7fl^«fj# ^ o i # 740]

4.

2.1.10 4 ° J 10 :

?J ^ ^ - T - # (Lack of understanding/validation of effects of

short-term overload events on subsequent mechanical properties)

Hanford ±4$\ FFTF(Fast Flux Test FacilityW

t 4 . ASME NHiL4 S.*&±.£\ RCC-MR 2 E

-^(negligible creep curve)"0! t | ^ ^ ^ ^ 1 4 . -rl

°n' 1^1 (threshold)4 ^ ^

- 14 -

(matrix)^- 3HH-^-§r 1HM?14.

£ 538 °C -

3i 3}-^: (relaxation

. ASME

2.1.11 A>O> n : 7 j ^ £ ] <g iEgfo |3g xfs. ^ ^7l]«ov^^ -^-^(Lack of validated

thermal stripting materials and design methodology)

UIS°fl

7] 7] S]

CRBRP l ^^lofl'M 4-8-it Inconel 718#

-^i^r Inconel 718^H1 tflsfl t ^ S 4 ° l

14.

3X7}

lfe Modified 9Cr-l Mo

- 15 -

Inconel 718

Si ^3]7l^(criteria)<»1 §14. CRBRP^

E)JL $14. CRBRP ^^1^1-1-^ °g f

Inconel 718°fl t)l«H Il7flsl cflolE] ^ Modified 9Cr-l Mo

tflolEi ^ # ^ - ^^*1-Sa4. ^l^-^l-^i SAFR t ^ ^ r 7fl^tl:

Westinghousefe 31633^1 tfl*H

4 . <&*}£] °1± ^ £ Inconel 718°D

^^£}-ol3g2j-3i ALMR 7]#7fl^: 7)1^^ Modified 9Cr-l Mo

l-7f| ALMRi

PVRC

^-^r ol

(a)

(b)

(C)

(d)

(e)

££7}

- 16

ASME

ASME S ^ ajs.-i?!! ^-^ i^ ; 106

si .2.7}

^r 316 +q}9lH}+^ Inconel 718 ^ Modified 9 Cr-1 Mo

l-S-*>^ ^r^«}-^4 . ^ 1 ^ ^ ^ 316 iEfl

Alloy 718

flH W t b ^ ^ - ^ M-^^:4. 1 i S e ^ - o l ^ ^ ^ - 8 : modified 9

Cr-1 Mo #ol 316 iBi]o]efli.7oV4 Alloy 718cHl «]*H -T-41^: ^ ^ - S . ^Ef^cf.

tiV^ A>zj-f§ 2.^5.] Hj-(bar)°ll tfl^ 1 iE.^-o]>§ Al^ofl^^. (a) modified 9 Cr-1

Mo # ° ] AJ^O) Alloy 7183)- 7]si) « 1 ^ § H (b) LMFBR^l ^^«V£7> 2xiO6 1

^7> Slfe ^ ^ . S 4 ^ ^ 4 . ASME 3H£] 5 ] ^ ^ - ^ ^ - J L ^

uH <§ i^sfo]>il Al^^Hlofl^ ^ ^ ^ t €-S-(fluctuation)<>l EBR-II

2.1.12 A>^V 12 : ^ispjsafe 3.^-3\3, -iTil^l^ ^^(Lack of reliable

creep-fatigue design rules)

ASME 2 S 2 ] ^^1^1^-8: ^ ^ - TCS.*1N ^ « f l x ^ T-1400,

T-1700)«fl 1

envelope Sfe D-Diagram^l sitb 1 t^- ^ 7 1 ^ ^d^^-tlr^l 7la:®f^ Si

- 17 -

L S ^ Eddystone

£}§j-a| ASME 2JE£) SG

ASME

ASME S ^

ASME2:71

£14. a^ - s l s 4°1€ *H>M 7>#£|^1 ^fe 55}-

§171 ^S-^ll

tHJf£si ^ ^ ^ Ai^^. -fi-xiAi^oi 30

, LMR Q

ASME NHS] # $ £ # a 'g^-

A I ^ ^ P ] - ^ 5.^0] 7fl i£ ^ 7 ^ ^ E ] J I o] ^ o]

740I4.

2.1.13 Afo> 13 : O ^ J L , ui^- i L ^ ^ y 5}^1^ -S Tfl *141 (Difficult, overly

conservative ratcheting design rules)

- 18 -

ASME NH^ ^ T(T-12004 T-1300H Xl

° 1 ^ £ PVRC l

-g-°l -i-7>^sl-nl ASME NH^ 1 9 8 3 ^ tf^s]

(double-sided thermal shock)^ 3J7>oi]^ ^ ^ § j

CRBRP SS.^M7> ^ 5 l J L PVRC7> ^ s] ^-Xll- ^ " ^ t t o l ^ ] ^ ASME NH

-S-) ASME°fl $]*}^ ^ ^

CRBRP7}

ASME

^ (a) *1 4 ^^ S - 5tU, (b)ja. (c) -M l

2.1.14 4 ^ 14: ^ £ l -§-^^711 wj-^si -^^(Lack of validated weldment design

methodology)

^ %o) i ^ ^ o ] 614)014.

- 19 -

310)7}

°fl cfl - oi*i)7> ^-#§1-4. £ t i ^ l Phenix ^ j -Sfe 7}-§-^ ^ 4 5]*) ^o}. n 5.

. CRBRPS]

A S ^ CRBR5]

rate), ^>«>l#

rate) ^ -R-^l^l?>^ 3 :4 313^

^r(remaining uncracked wall thickness) •¥

enhanced 3 ^ s ] JLSj

CRBRP # £ ^^] ^7fl ^^#011 tfl*H

NRCfe 5 \ i ^ ^ 74^1 A ] ^ « B ^ ^ -sfl ^ ^ S S ^ ' S

. St ^ Smt *!-§- -^^j-^o^ ^ ^ ^ . ^ ^ c ^ *>f- |«H -S-^

&-3±v± <£?\}°}x}7} 7fl^£lJL iEtt ASME NHN «}^s]^4.(section 3221 &

Tables 1-14.10) CRBRP S.S.^S.7} ^ ^ s l $-3.

PVRCS.

ASME

- 20 -

?1 (welding reduction factor)^ 1986^^ ASME N H i

7)]

CRBRP^l ^ ^ ^ - # ^ ^

joint)^ 30^51

^ 15\i

oil 4-E 3-^

(mismatch), -g-^

- 21 -

2.1.15 4<?1 15 : ;£•§)• 3 j 7 } ^ * | - ^ ^ ( L a c k of flaw assessment procedures)

ASME NHofl-M 4^(fai lure)^ 5 - g ^ ^ l ^ M ^ S ^ £ ) E } i $14.

914.^f-(imperfection)

1-4 1 7floj) «a^ofl ^ ^ ] n]ifcg-<g(micro-crack)^

3 ^ ASME 2 H Sect. Xl^r

ASME NH ^ Sect. X H

o) ^ o > ^ JL§1 ^_g. L M R

oix}7j\% n®°]i%. nl^- DOES] * ] ^

Tfl(HTSD) SS-Zl'S § H H ° i ^ 7M1 A>3flofl tfl *fl ?gr^ Sg 7|-7>

- 22 -

EPRI7> *l*l *H ORNL^ J l ^ ^ a 3j7>^^]-l- 7fl^-*>^^Bj| o]^. ASME ^ ^

2.1.16 *>«£ 16 : ^ ^ -g-^^-tflo] ^-^-^Jg(Uncertainty of multiaxial stress state

effect)l^r^-H ^ S l 5 ^ ^ i n] fe «g ofl tfl o|

] ASME NH ^ ] ^ ^

o t i . ^ ^ t > A ) ^ A

10% opo)-s-§] 60^ ^r^^-S oflAj.sj.jT. oi^ ALMIH ^§H)5] 4 ^ ^5. ^ =iL

2.1.17 AfoV 17 : Nonradial ^ J L ^ S ] I T ^ - ^ A J (Uncertainty of nonradial

<nonproportional> loading effect)

^7)]^^S] 10%

nonradial t f f ^ } ^ ^ s H ASME NH^ *l^-|r ^ ^ ^ V*b ^«»1E17> 7 ^

*V Aj-Eflolcf. ^7flS| ASME NH£:

ORNL^l nonradial Sj-f1 *HA1 r

- 23 -

2.1.18 >M-°> 18 : t*] W M ^ ol*l) ^ 3^3] ^(Validation of notch

weakening effects)

£ £ -i^^HM ^ ^ 3W7fl -g^Hr ^ ^ 5 1 ^ 2 : '

74

-f ^-l- ^r^fe 5!(stress raiser)^ ^^fl ^ ^^Hl T J ^ cf^.^ ^ 7\^

^r net^ -^^ . ^-elfe 74^ S*V 3 ^ - 3 f ^ ^^-^l 2:71

3:471- tn^-^-si

^(transverse shear)4 £•& §]-

- 24 -

2.1.19 A}O> 19 :^•r-^1 (Lack of conservatism in code rules for simplified

fatigue evaluations based on plastic strain concentration factor)

CRBRP ^31<?}^

t ^ ^ ^ l * r ? l Ke <y*>£] A>-g-jz}. # £ £ 4 . ASME 3 ^

fe <H*r ^ ^l^l-g-^^^(primary plus secondary stress range)7} 3

2 Syl- 2 4 t ^ -g^S. oi oi^fe. i^- ^j^Tfl ^cf. # ^ s i fe^-^Ai ASME

2.1.20 4°J 20 : j i ^ r ^ ^ ^ l ^ lS^ l - H-Bfifl 7j^sl x ]^ ^-^(Lack of

validated rules / guidelines to account for seismic effects

at elevated temperature)

• # £ CRBRP ^^l 1 ?]^ 4^°Jlxi Finding No.

ASME NH£ ^r

ited intensities)^

secondary

enhanced 3

1H r Si4.enhanced

CRBRP21 ^g^< ] °1 ^-^lfe NRC7]-

^ ^ f f e enhanced

- 25 -

& 4 . ASME 2 £ f e^^*}?i ^^71-0)] cfl*> ^l^ol *}&$*) 5U*1 & 4 . LMFBRS]

2.1.21 ^>°1 21 : yH V2l UTE}-^ ^ 7 f l ^ > Jf^(Lack of inelastic design procedure

for piping)

fe Robinson^

Tfl ^l^ollA^ A)-§-£)jL ^ fe 7j|^6]t}.. ^ - A j * ^ ^ 42) £ £ 7 }

o]

11- 7}X)5L $14. 2 H

^ o] £o)ofl^ ^ ^ o ] ^o^ufjl 014.f. CRBRP2] °i^} I ^ ^ ^ l ^

CRBRP uM^l^s-l ^7] ^ S Ki^A^i ^ . ^ j . u s N R C

HJ-A^S^ 3g7V«V^ 4 ^ t ^ 3J7}-^0l -O-^ ^ O_]

4 014. o] Tg.^^

. ASME 3 H

- 26 -

& o . ^ LMFBR

%v°l £S«V -g-c^fe ASME HLEL

CRBRP7> ^ ^ 5 1 olsfls. ASME 5LHfe Subsection NH

7A°-S. ^^Sj-fe ^^r ol ^ ^ ^ ^ 1 W ^ ^ 9?

2.1.22 A } ^ 22 : *14*l7fl ^-^r^1?! 2}-# 7]§(0verly conservative buckling rules)

ASME

H> Si4.

ASME 5LH£l Sect. I, III, VIII ^ 1 ^ l ^ m 2

71

ASME

(factor)^l ^SflS. 2>^ t t ^ * uL3i|*l-JL

CRBRP «

7HI ^1H1 ^-^^fji(imperfection insensitive), «112. 1 -S-

ASME

- 27 -

ASME N H ^

xtfl

. LMFBR

o] Aj-oj-^. "

2.1.23 4 ^ 23 : - i ^ l ^ l H H < i ^ # - i ^ l ^ ) ^ ^ ^ -S .^ (Need for thermal

stritification design guidelines)

LMR

en .

°1 ^^o1"0] ^Tflofl tit^£ljl oiq._ NRCi ^^>S^1 l Vxl- ^ 3 ^ Si A}

(utility community)^ °1 €-*fl# *fl7ltb H> Sl^.^, «>] ^ ^ 1 # sfl^-sf^l ^

°1

2.2 A)-of °) ^ s r

- 28 -

2.2.1

- (S) :

- (E) :

2.2.2- 7fla ^ t-HoiE^joii 7 l s (M)

- -i^l 7 ] s (D)

- £]£-] ^ 7]-*] a ^ (M&D)

2.2.3 4<L^ ^

i) T T 1 : *M£]*] ^A^ 60\i

ii) T § 2 : *}] 2 E

iii) ^ ^ 3 : ^ ^ S ^ vflofl

iv) -r§ 4 : ?H 2H

v) ^ f 5 :

vi) t t 6 : ^ f l 2 E flofl ^^flsl-fe «ov^2^ ^^°flfe- 4-8-€ ^ SiSi

- 29 -

S. 2. A

IssueNo.

1

6

16

19

18

14

20

2

3

4

12

11

7

9

10

IssueLevel

1

2,6

2

2

2

3,4,5

3,4

3,4

3,4

3,4

3

4

5

5

5

Issue

Lack of material property allowable design datacurves for a 60 year design life

Degradation effect of small cyclic stresses

Uncertainty of multiaxial stress state effects

Lack of conservatism in Code rules for simplifiedfatigue evaluation based on plastic strainconcentration factors

Lack of understanding /validation of notch weakeningeffectsLack of validated weldments to accoint for seismiceffects at elevated temperatureLack of validated rules /guidelines to account forseismic effects at elevated temperatureDegradation of material properties at high temperaturedue to long term irradiationDegradation of material properties due to long termthermal agingDegradation of material properties due to corrosionphenomenaLack of reliable creep -fatigue design rules

Lack of validated thermal striping materials anddesign methodologycreep-induced failures at temperatures below ASMENH limitsLack of design methodology for modified 9Cr-lMosteelLack of understanding /validation of effects ofshort-term overload events on subsequent mechanicalproerperties

Catagory

(type-bases)

M-S

M-S

D-S

D-S

D-S

D-S

D-S

M-S

M-S

M-S

M&D-S

M&D-S

M-S

M&D-E

M&D-S

- 30 -

IssueNo.

15

21

5

8

13

17

22

IssueLevel

5

5

6

6

6

6

6

Issue

Lack of flaw assessment procedures / rules

Lack of inelastic design procedures for piping

Lack of property allowables based on current metingpractices

Use of average vs minimum material properties indesign

Difficult, overly conservative ratcheting rules

Uncertainty of non-radial (nonproportional) loadingeffects

Overly conservative buckling rules

Catagory(type-bases

)

D-S

D-S

M-S

M&D-S

D-E

D-S

D-S

weekening effect)^]

- 31 -

2.3

^(program recommendation) <#-§••§• 4 ^ 4 7EV°

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- 32 -

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- Modified 9Cr-lMo 7j-s] ^-

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- 34 -

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3. ASME NH I 7H

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- 36 -

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- 37 -

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stress-strain curve)6!! j #*! A}O]^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ( £ t ) i . 2|-g-§H -§-^51: S,-&

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- 39 -

A

Subsection

- 40 -

5.

ASME Code Section III Subsection NH

ORNL°1

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107M

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], ASME

-O.S. i t ^ s ) RCC-MR4 °i££) DDS

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- 41 -

[I] ASME B&PV Code, Section III, Subsection NH, ASME, New York, 1995.

[2] R.L. Huddlestone, R.W. Swindeman, Materilas and Design Bases Issues in

ASME Code Case N-47, ORNL prepared for US NRC, NUREG/CR-5955,

ORNL/TM-12266, 1993.

[3] Guidelines and Procedures for Design of Class I Elevated Temperature

Nuclear System Components, Nuclear Standard NE F 9-5T, U.S. DOE

Office of Scientific and Technical information, Oak Ridge, Tennesse,

September, 1986.

[4] R.A. Ainsworth, M.B. Ruggles, and Y. Takahashi, Oak Ridge National

Laboratory, Flow Assessment Guide for High Temperature Reactor

Components Subjected to Creep-fatigue loading, ORNL-6641, October,

1990.

[5] A.K.Dhalla, ed, "Recommended Practices in Elevated Temperature

Desgin •' A Compendium of Breeder Reactor Experiences (1970-1987),

Colume 1, Current Status and Future Directions," Bulletin 362, 42 Welding

Research Council, New York, April, 1991.

[6] L.K.Severud, 'Creep-Fatigue Assessment Methods Using Elastic Analysis Results and

Adjustment,' WHC, ASME FVP-Vol. 163, Honolulu, USA, 1989.

[7] RCC-MR, Design & Const. Rules for Mechanical Components of FBR Nuclear Islands,

France, 1985.

[8] J i ^ f ^ S . *fll^ 7]7)£\ 5L£^£ *A%H%(BDS), PNC, Japan, 1984.

[9] Meeting addenda, ASME subgroup on elevated temperature design, May 18,

1999.

[10] ORNL/9CR/92-2, Summary Report JAPC-USDOE Joint Study design methods

and data for Modified 9Cr-lMo Steel.

[II] Proposed text and data for inclusion of SA-533 and SA-508 into Appendix of

Subsection NH.

- 42 -

INIS

KAERI/AR-586/2000

n]-^- ASME Section III Subsection NH 2 £ ^ 1 ?•}]£.

(TR, AR^l7} 7]} ^ ^1 7} #71]

X]- . 7 ] 7-1] - g 7-1] 7 ] £ • 7)]

2000.12

211 Ol * j 42 p. 71 26cm

H] <?J a] « .

ASME Code Section III Subsection

ASME NH 3.^

ASME NH2]^- t lo j Code Case N-47-gr 1989>d

H]S.^ 371] 7fl =g Sj cf . =L 1992^1995^2.

. ASME

Code Case N-47J4 Subsection NH.S.

ASME Section NH Subsection NH, Code Case N-47,

BIBLIOGRAPHIC INFORMATION SHEET

Performing Org.Report No.

Sponsoring Org.Report No.

StandardReport No.

INIS SubjectCode

KAERI/AR-5 86/2000

Title/Subtitle

A study on technical issues of materials and design bases in ASME Section IIISubsection NH Code

Project Managerand Department(Main Author)

Hyeong-Yeon Lee/ KALIMER Mechanical Structure DesignDevelopment

Researcher andDepartment

Jong-Bum Kim, Bong Yoo / KALIMER Mechanical StructureDesign Development

Pub.Place Taejon,Korea

Publisher KAERI Pub.Date 2000.12

Page 42 p. Fig. & Tab. Yes( V ), No ( ) Size 26cm

Note

Classified Open(V), Restricted( ),Class Document

Report Type A State-of-the-ArtReport

Sponsoring Org. Contract No.

Abstract (15-20 Lines)

In this study, an analysis of evaluation report by ORNL on the technical issues of elevated

temperatures design guide line, ASME Code Section III Subsection NH was conducted and a

brief evaluation procedure of the creep-fatigue damage was presented. ORNL published the

report in 1993 and reviewed the issue areas where code rules or regulatory guides may be lacking

or inadequate to ensure safe operation over the expected life cycles for liquid metal reactor

systems. From historical viewpoint of the ASME NH code development, ASME Code Case 47

was changed much in 1989 edition, which includes the stress relaxation behavior in creep

damage evaluation. Afterwards the 1992 version of CC N-47 was upgraded to Subsection NH in

1995 edition, which is the same with that of CC N-47 1992 edition except few material data. This

report brings up the technical and regulatory issues that can not guarantee the safe and reliable

operation of the ALMR which got the conceptual design certification from NRC. Twenty three

technical issues were raised and settlement methodology were proposed. Additionally, the status

of items approved by ASME code subgroup of elevated temperature design committee for the

revision of the most recent 1998 edition of ASME NH was described.

Subject Keywords

(About 10 words)

ASME Section NH Subsection NH, Code Case N-47, Liquid metal

reactor, High temperature structure design, Creep-Fatigue