ML19350E190: Difference between revisions
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} Design to Design i Review Delay Review Final I y y Program Reinstated y y y Design | } Design to Design i Review Delay Review Final I y y Program Reinstated y y y Design | ||
! Des,ign v/nuss///A---------------------Tf////u////////A Review j | ! Des,ign v/nuss///A---------------------Tf////u////////A Review j | ||
i | i Testing vus/gruuuruus/A------------- M g ,,,,,,, | ||
Testing vus/gruuuruus/A------------- M g ,,,,,,, | |||
l NRC l | l NRC l | ||
Approval | Approval | ||
Line 103: | Line 101: | ||
, . l t ..- s ,' * .j Q''; . X 2*.* * . m. t r ., f. | , . l t ..- s ,' * .j Q''; . X 2*.* * . m. t r ., f. | ||
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b .r*. W ..' ' | b .r*. W ..' ' | ||
3 , | 3 , | ||
Line 246: | Line 242: | ||
% "y&.n'w j % eph:.Q W .&@yyM.w @*.9 W<.g, n .. M W y. mW +8%.m msiva% | % "y&.n'w j % eph:.Q W .&@yyM.w @*.9 W<.g, n .. M W y. mW +8%.m msiva% | ||
p %4 o - | p %4 o - | ||
r.gW . 2 Aw dggM w d e 3., q . g.: m drW. - is Wa &g,s. | r.gW . 2 Aw dggM w d e 3., q . g.: m drW. - is Wa &g,s. | ||
Q ,:- -( ~ z, 9* w | Q ,:- -( ~ z, 9* w | ||
Line 263: | Line 258: | ||
*$mm R t-, .% - | *$mm R t-, .% - | ||
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$' .Kl - | $' .Kl - | ||
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"t j 4.c m. | "t j 4.c m. | ||
w %w#M . w .. q 4 w e +.e WK :m w %* a& gWwe-wW.v e,. m es @W m- - < ,W | w %w#M . w .. q 4 w e +.e WK :m w %* a& gWwe-wW.v e,. m es @W m- - < ,W 7.. Q' h .2%ph.s %. %+y&M | ||
7.. Q' h .2%ph.s %. %+y&M | |||
... M wb .3 msw 1i ry M4&p, p S. .c+..n?$@m 4 ~., p.g%'M,.ji .- . - | ... M wb .3 msw 1i ry M4&p, p S. .c+..n?$@m 4 ~., p.g%'M,.ji .- . - | ||
. . ,-p | . . ,-p | ||
Line 310: | Line 302: | ||
) | ) | ||
FOR 3 YEARS. WO . | FOR 3 YEARS. WO . | ||
CRUC I FORM CONTROL RODS | CRUC I FORM CONTROL RODS | ||
/ IN CORE SINCE :.972 . | / IN CORE SINCE :.972 . | ||
; S - | ; S - | ||
: 33. \ G 30 R ~~ T ULL CORE COMPLEMENT 4 | : 33. \ G 30 R ~~ T ULL CORE COMPLEMENT 4 | ||
l l | l l | ||
Hafnium RCCA Rodlet Design For 212, 312, 412 Plants-n | Hafnium RCCA Rodlet Design For 212, 312, 412 Plants-n | ||
Line 388: | Line 377: | ||
1 I I O | 1 I I O | ||
li l | li l | ||
i l l l | i l l l l ' | ||
l ' | |||
1 i l l i 8 i i | 1 i l l i 8 i i | ||
, I : | , I : | ||
Line 415: | Line 402: | ||
:4 s | :4 s | ||
1 i | 1 i | ||
i Key Differences t | i Key Differences t | ||
Line 441: | Line 427: | ||
== Conclusion:== | == Conclusion:== | ||
Design margin is unchanged or improved | Design margin is unchanged or improved | ||
9 | 9 Design Verification / Testing | ||
Design Verification / Testing | |||
! Verification Item | ! Verification Item | ||
* Reactivity Worth | * Reactivity Worth | ||
Line 484: | Line 467: | ||
l | l | ||
! Thermal Conductivity, , 0.213 at 620 F .902 at 600'F l (Watts /GM/ C) ; r .; | ! Thermal Conductivity, , 0.213 at 620 F .902 at 600'F l (Watts /GM/ C) ; r .; | ||
Density,(GM/CC) ... ' 13.36 10.17 1 | Density,(GM/CC) ... ' 13.36 10.17 1 | ||
i Modulus of Elasticity (PSI) 13.8 x 106 at 700 F 9.7 x 108 at 600 F i . | i Modulus of Elasticity (PSI) 13.8 x 106 at 700 F 9.7 x 108 at 600 F i . | ||
! Melting Point ( C) 2,222 800 | ! Melting Point ( C) 2,222 800 | ||
; Strength (PSI,0.2 YS) > 30,000 ~ 7,000 - | ; Strength (PSI,0.2 YS) > 30,000 ~ 7,000 - | ||
1 | 1 | ||
} Resistance to Corrosion < 10 > 200 (MG/DM2 IN 200 Days) - | } Resistance to Corrosion < 10 > 200 (MG/DM2 IN 200 Days) - | ||
l 1 . .. i j Dimensional Stability ' i Sus' c eptible!t o . . l | l 1 . .. i j Dimensional Stability ' i Sus' c eptible!t o . . l Susceptible to Irradiation | ||
Susceptible to Irradiation | |||
; Hydriding Swelling - | ; Hydriding Swelling - | ||
i j '8 1, | i j '8 1, | ||
Line 503: | Line 482: | ||
@ NFD and Naval Specification l | @ NFD and Naval Specification l | ||
! Chemistry Comparison | ! Chemistry Comparison | ||
-l | -l | ||
! .. . Naval @NFD - | ! .. . Naval @NFD - | ||
Line 511: | Line 489: | ||
! Total Metallic (PPM, MAX) 1,530 2,000 Negligible Impact l | ! Total Metallic (PPM, MAX) 1,530 2,000 Negligible Impact l | ||
Other than ZR ZR (% MAX) 4.5 4.5 Same HF (% MIN) 95.3 95.3 Same C;;' ' , ,, | Other than ZR ZR (% MAX) 4.5 4.5 Same HF (% MIN) 95.3 95.3 Same C;;' ' , ,, | ||
$ $ 3i l' - | $ $ 3i l' - | ||
4 | 4 | ||
Line 566: | Line 543: | ||
SAFEIY EVAUJATICN IMPACT REACTIVITY 10RTH l | SAFEIY EVAUJATICN IMPACT REACTIVITY 10RTH l | ||
NO PEACTIVITY lGTH F91ALTY (ESSENTIALLY SA N WORTH) | NO PEACTIVITY lGTH F91ALTY (ESSENTIALLY SA N WORTH) | ||
NO SIGNIFICANT EFFECT CN SAR-T6E ACCIDENTS RCCA DROP TIE i | NO SIGNIFICANT EFFECT CN SAR-T6E ACCIDENTS RCCA DROP TIE i | ||
PARlILN RCCA HEAVIER TPAN M-IN-CD FASTER DROP TIE PEEFICIAL TO ALL SAR-TYPE ACCIIHITS l | PARlILN RCCA HEAVIER TPAN M-IN-CD FASTER DROP TIE PEEFICIAL TO ALL SAR-TYPE ACCIIHITS l |
Latest revision as of 03:47, 18 February 2020
ML19350E190 | |
Person / Time | |
---|---|
Site: | South Texas ![]() |
Issue date: | 05/26/1981 |
From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
To: | |
Shared Package | |
ML19350E189 | List: |
References | |
NUDOCS 8106170124 | |
Download: ML19350E190 (34) | |
Text
.
ENCLOSURE 2
<}
il R C fl E E T I Il G HAFllIUil ilAY26,1901 A G E il D A
- 1. IllTRODUCTION/ PURPOSE
- 2. TECHtllCALDISCUSSICtl A) OVERVIBl 0F SUBSTITUTI0tl PLAtl B) PRICR EXPERIBlCE C) OVERVIEW OF W RCCS IMSIsl u) DESIGl I'CDS/CCMPARISOff WIE [GIliCD
-312/4.12 PtAnTS
- XL PLANTS i E) I'ATERIALS i F) PHYSICS L
j G) SAFETY EVALUATIm ItPACT
- 3. LICSS!flG/kTIWS
- 4. C0tJCLUSION/[CTI0ts l
i .
I 81061 7 0 YbA i
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1 HAFNIUM CONTROL ROD ASSEMBLY DESIGN .
0
~
H A F il I U M ' A B S O R'B E R M A T E-R I'A L ~ SUBSTITUTION 0BJECTIVE: REPtKE AGINCD WIE FAFNIW STATUS: FAFNIW ItGRG)UCED IN 1980 I (1 P L E f1 E N T A T I O fl : FAF?HW SHIPfeUS ST/RT LATE 1981
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H A F il I U i1 APPLICABILITY 11CCA ALTEPRATIVE PLAr4T DESIGft STAWS fu-flF 17 x 17 312/412 CCTPLETE 17x17 XL PROPOSED 16x16 212 CCf4PLETE 15x15 312/412 FUTURE 14x14 ?17 FUTURE HFTIPS 312/412 C0f1PLETE tri EqC 17x17 7 ih'BRID XL C0fPLETE 0
,. - . - . - ,- _ _ _ _ . - - - - . , , , , - . - - - -,,,,.,,,,---.n,---
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t l Hainium Control Rod Assembly i Development Schedule Overview Preliminary Decision Intermediate
} Design to Design i Review Delay Review Final I y y Program Reinstated y y y Design
! Des,ign v/nuss///A---------------------Tf////u////////A Review j
i Testing vus/gruuuruus/A------------- M g ,,,,,,,
l NRC l
Approval
- Materials Report SubniittalY y
" "O Lead Plant SAR Y Amendment RCCA Prototype V
! Y/ H H H A l Production V Ship 1st j yppp/A Production 1
l iiiliiiIiiiliiiIiiiiiiiiiiiiiiiliiil i
1974 1975 1976 1977 1978 1979 1980 1981 1982 i
l a,
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- 1 Hafnium Production Process Outline ,
Zircon Sand r
ZrO 2 Hf0 2 Extraction Process -
v v Zirconium Metal Hafnium Metal Reduction Reduction and Purification
! v v Zirconium Metal Hafnium Metal Products Fabrication Products Fabrication e
h e
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Commercia0 Emperiertee 30
~~
N J A' \ \ CORE A HAD A F U L L.
~~
- \ :. COMPLEMENT l
YA\<EE 10.WE T ULL CORE COMPLEMENT
~~
)
FOR 3 YEARS. WO .
CRUC I FORM CONTROL RODS
/ IN CORE SINCE :.972 .
- S -
- 33. \ G 30 R ~~ T ULL CORE COMPLEMENT 4
l l
Hafnium RCCA Rodlet Design For 212, 312, 412 Plants-n
/l u
Plenum 4" t
a Hafnium Replaces 142" Ag-In-Cd u
V OE
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l Design Objective i ,
i
- Replace AGINCD with Hafnitim l
l l
- Minimize changes to already proven design l -
l l
1
Standard RCCA Configuration GisiiiiiB
- ; p Spring g , ,
t Spider Body S ,
h/h kh 0p.:!]l c L: 0,3 @
Spring Retainerm - --
9
.88 Travel N a
.362 Dia.- -* -
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l 150.574 a
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142.00 Absorber ,
Length
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- . . _ . . _ _ . - . _ . . _ . , . _ . , _ , _ , - - . . . , . . , , , , . _ _ , . . . . . . _ , . . - - - _ . _ _ . , - . . , _ . , _ _ _ , , _ , . , , - . . _ , __m-, -- - ..- _ _ . - . _- - . - _ . . . _ - . . - . - - . _ m
e Cladded Absorber Concept Preferred Over Unciadded
- One for one absorber material change
- f.
- Retain proven features of design:
- S. ST structure and joints Wear interfaces e Manufacturing flexibility (same parts?
- Facilitate licensing I {' }
i
l -
1 1
i 312/41217 X 17 RCCA Design Features j .
! All Ag All Hf f' Absorber O.D. (inch)
Absorber
.341 .341
- Length:(inch) Ag or Hf 142 142 l
l Clad I.D. (inch) .344 .344
!. Clad O.D. (inch) .381 .381 Giad Material 304 S.S. 304 S.S. ,
i Rodlet Spring Material 302 S.S. 302 S.S.
SpiderSprings Single Double Nested 4
e Nested Spider Spring rg f3
)
u.- ~S.
\ ._ J 0-, Inner Spring w
l ,
Outer Spring 8
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l 312/41217 X 17 RCCA De' signs l Performance Comparison l
l All Ag All Hf l .
RCCA Wt. (Ibs.) 149 180
{ Drive Rod Wt. (Ibs.) 136 136 Overall Wt. (Ibs.) 285 316 Calculated N-1 '
Rod Worth (%A/>)
STD Fuel 5.71 5.76 OFA Fuel 6.15 6.20
- 4 s
1 i
i Key Differences t
Key Differences from AalNCD Design Hesult i
- Greater Weight
- Change rodlet spring (shipping)
- Use nested spider spring
- Use appropriate drive shaf* coupling i
- Faster drop time -
i' i
! Reactivity Worth / Depletion
- Better than AalNCD l Lower Coef. Therm. Exp.
- Larger hot clearances l Lower Thermal Conductivity
- Higher absorber temperature 4
(melting temp. higher also)
- Cause of Potential Absorber
- HF Volume Change due to hydriding:
i Dimensional Change AalNCD Volume change due to irradiation l Both within same design limits Greater Stiffness
- No measurable change in wear performance
- Corrosion Resistance
- Better than AalNCD j 4
't l
Conclusion:
Design margin is unchanged or improved
9 Design Verification / Testing
! Verification Item
- Reactivity Worth
- Computer Codes l
- 1974 Critical Experiment
- Drop Time
- Previous D-Loop Tests
! (with less weight)
!
- Scram Loads
- Analytical Models Bas'ed on i D-Loop and Bench Test Data 1
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- CRDM Stepping Loads,
- Previous D&M-Laop Tests Drive Line Wear, Vibration at Comparable Conditions
- Loads within Original Design Basis l
- Coupling / Joints
- Fatigue Tests at '
j Representative Loads t
l 0 Rodlet Integrity.
- Previous Tests and Operating Experience
- Cladded HF Autoclave Tests i
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PROPOSED XL HAFNIUti RCCA KEY DIFFERENCES XL- 312/IG2 ABSMBER LENGTH (IN.) 158.87 1412.00 R C C A Wr. (LBS) 200 180 OVERAU WT (LBS) 3ld 316 SPIDERSPRINGTRAVEL(IN) 1.05 0.88 Patsr SPRITS PRELCAD SalVSTED Fm WT.'
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Key Material Differences -
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' ' i i HF AGINCD i
- -Coefficient of Thermal 3.3 x 10 6 12.5 x 10 6 Expan.s. ipr) (IN/IN/ F).
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! Thermal Conductivity, , 0.213 at 620 F .902 at 600'F l (Watts /GM/ C) ; r .;
Density,(GM/CC) ... ' 13.36 10.17 1
i Modulus of Elasticity (PSI) 13.8 x 106 at 700 F 9.7 x 108 at 600 F i .
! Melting Point ( C) 2,222 800
- Strength (PSI,0.2 YS) > 30,000 ~ 7,000 -
1
} Resistance to Corrosion < 10 > 200 (MG/DM2 IN 200 Days) -
l 1 . .. i j Dimensional Stability ' i Sus' c eptible!t o . . l Susceptible to Irradiation
- Hydriding Swelling -
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- 1 1; i ;I i e.
j i j 1:li : ' .( ' i- ,; .,bi i
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@ NFD and Naval Specification l
! Chemistry Comparison
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! .. . Naval @NFD -
Spec Spec Remarks -
j i i l Interstitial (PPM, MAX) 525 1,510 Difference Affects (0,N,H) Weldability and Formability 1
Iron (PPM) 200-500 750 Negligible impact
! Total Metallic (PPM, MAX) 1,530 2,000 Negligible Impact l
Other than ZR ZR (% MAX) 4.5 4.5 Same HF (% MIN) 95.3 95.3 Same C;;' ' , ,,
$ $ 3i l' -
4
l MATERIALS TESTS AND OPERATING EXPERIENCE OTHER THAN NFD NAVAL REACTORS EXPERIENCE SHIPPINGPORT ATR ETR OPERATING EXPERIEi;CE IN PWR'S NFD TESTING CLADDED HAFNIUM AUTOCLAVE TEST
, STAINLESS STEEL-HAFNIUM CHEMICAL COMPATIBILITY i
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r PHYSICS CONSIDERATIONS CONTROL R0D WOPTH HAFNIUM AND AG-IN-CD HAVE NEARLY IDENTICAL ROD WORTHS AT OPERATING CONDITIONS E DESIGN.
CRITICAL EXPERIMENT DATA AND ANALYTICAL-ESTIMATES INDICATE WORTH EQUIVALENCE AT OPERATING CONDITIONS.
METHODOLOGY EMPLOYED TO GENERATE HF GROUP CONSTANTS AND HF ROD WORTHS IS DESCRIBED IN WCAP-9217(P), 9218 (NP)
"RESULTS OF CONTROL ROD WORTH PROGRAM".
HF METHODOLOGY IS IDENTICAL TO AG-IN-CD METHODOLOGY.
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PHYSICS CONSIDERATIONS CRITICAL EXPERIMENT DATA SOURCE HAFNIUM COLD WORTH RELATIVE TO AG-IN-CD BNWL CRITICALS (1974) 2.2% LESS ANDERSON AND THEILACKER, NEUTRON ABSORBER MATERIALS FOR REACTOR CONTROL Sl.0% LESS VALENTINE (BETTIS) $2.5% LESS (SOME DIFFERENCE IN R0D GE0METRIES)
HARTLEY AND BAYARD (BETTIS) 1.2% LESS NOTE:
- 1) ABOVE COMPARISONS WERE MADE AT COLD TEMPERATURES (S68*F)
- 2) DIFFERENCES BETWEEN HF AND AG-IN-CD HZP ROD WORTHS WILL BE SMALLER THAN INDICATED ABOVE DUE TO THE HARDER NEUTRON SPECTRUM AT OPERATING TEMPERATURES.
- 3) BETTIS PERSONNEL INDICATE THAT HF IS WORTH SLIGHTLY MORE THAN AG-IN-CD AT OPERATING' TEMPERATURES.
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PHYSICS CONSIDERATIONS CONTROL ROD WORTH CALCULATIONS TYPICAL CALCULATED ROD WORTHS FOR A 4-LOOP, 12 FT CORE, HZP, E0L, EQUILIBRIUM CYCLE, STANDARD 17X17 FUEL ROD WORTH (%ao)
N N-1 AG-IN-CD 6.95 5,70 HAFNIUM 7,00 5,74 N-1 R0D WORTH IS USED TO CALCULATE SHUTDOWN MARGIN HF N-1 R0D WORTHS WILL BE REDUCED BY 10% FOR SHUTDOWN MARGIN CALCULATIONS HAFNIUM AND AG-IN-CD WILL ALSO HAVE NEARLY IDENTICAL WORTHS IN 14 FT CORES AND OPTIMIZED FUEL CORES l
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PHYSICS CONSIDERATIONS GROUP CONSTANTS AND SPECTRUM EFFECTS COMPARISON OF HF AND AG-IN-CD GROUP CONSTANTS CONSTANT RATIO (HF/AG-IN-CD)
D1 1.03 El 1.16 ER 0.92 2
D 1.22 g2 ,
0.72 INCREASED RESONANCE ABSORPTION IN HF COMPENSATES FOR DECREASED THERMAL ABSORPTION INC . EASE .IN 01 /0 2WITH INCREASE IN TEMPERATURE RESULTS IN HF WORTH INCREASE RELATIVE TO AG-IN-CD (TYPICAL VALUES: 01 /0 2 COLD = 4.6, 0 /0 1 2 HOT = 5.8 )
l CORE AVERAGE 10 /0 2 IS NEGLIGIBLY CHANGED DUE TO PRESENCE OF HF:
01/02 (HZP, ARI)
HAFNIUM 6.14 AG-IN-CD 6.18 .
NO IMPACT ON CORE KINETICS e -- .- -- .- , . . - - , . . , - , - . , , , , - . . , - _ . . . , . . - - . . - - . - - , , - , . - - - - - . - , . . , - - - . , . - - - . . . , - - , , . . , . , - - - . . , ,
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. LIFETIME CONSIDERATIONS CONTROL ROD DEPLETION IS NORMALLY NOT A PROBLEM SINCE PLANTS ARE USUALLY OPERATED WITH AR0 HAFNIUM DEPLETES SLOWER THAN AG-IN-CD OVER A LARGE FLUENCE PANGE DUE TO:
- 1) TRANSMUTATION OF HF ISOTOPES
- 2) QUICK BURNUP OF CD-113 IN AG-IN-CD EVEN WITH DAILY LOAD FOLLOW, WORTH DEPLETION IS NOT A PROBLEM SINCE < 10% OF CONTROL RODS SEE SIGNIFICANT FLUENCE l
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SAFEIY EVAUJATICN IMPACT REACTIVITY 10RTH l
NO PEACTIVITY lGTH F91ALTY (ESSENTIALLY SA N WORTH)
NO SIGNIFICANT EFFECT CN SAR-T6E ACCIDENTS RCCA DROP TIE i
PARlILN RCCA HEAVIER TPAN M-IN-CD FASTER DROP TIE PEEFICIAL TO ALL SAR-TYPE ACCIIHITS l
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l CCNCLUSICNS: SAFETY REQUIFSINTS AE ET ETAL TO CR EETTER WN M-IN-CD l
LICENSIfE ACTIG S PRIOR #0 OJRRBE PAFNIlN APPROVALS PATERIALS TOPICAL GOP-9.U9) APP 90lX SLBITTED OCTGER,1980
- COP #DE PEAK FSAR #EDEIT II4 SLB1IIIw J#BRY,1981
- SNUFPS FSAR fEVISION 2 SUEMIllw FEBRJARY,1981 OTHER SPECIFIC PLANT FSAR #SDERS IN PROGRESS COWDE PEF #0 St0PPS SERS iN PREPARATION
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CONCUJSIWS BASED UPW TE MATERIAL ECPANICAL, NJCLEAR, #lD SAETY EVALUATImS FRESENTED, IT CAN E CWCUJED TFAT THE DIECT SUBSTITUTIm E FAFNIUM FOR AG-IN-CD INTO THE FRESENT TESTItG0JSE RCCA DESIC44S SATISFIES ALLPERTINENT RF0W#lCE AND SAFETY EQJIREPENTS AS DOCLPENED IN EGULAT0kT CUIE 1.70 #1D THE ST#GRD FE/IEW PLANS.
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