ML20038B257

Lynchburg Pool Reactor (Lpr)

ML20038B257
Person / Time
Site:	Lynchburg Research Center
Issue date:	08/26/1981
From:	BABCOCK & WILCOX CO.
To:
Shared Package
ML20038B249	List: ML20038B248 ML20038B251 ML20038B253 ML20038B255 ML20038B256 ML20038B257 ML20038B258 ML20038B259 ML20038B260 ML20038B261 ML20038B262
References
FOIA-81-317 NUDOCS 8112070067
Download: ML20038B257 (20)

Text

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.t SABCCCK AND WILCCX G ENER AL 1.1 ReacOr Name ( Acronym)

Lvnchbur: Pool Reac:ce (LPR) 1.2 License Number R 27

!.3 NRC Occke: Nurnber 50-99 L.'*

Reac :: Address The Sabcock & Wilc x Cc.~.:1nv Lvnchburz Resea. n Center a.

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.i..c 1.7 Reac r Owner Sabc:ck & Wi.:cox l.3 Reac cr Opera: r Sabcock & Wilc x 1.9 Reac cr Acminis::a: rs T. C. Ente!cer. LRC Direc cr R. N. Kubik. AC EFL M s.nazer R. H. Lewis. Nuclear Physics Manazer I

M. N. Sa!dwin. Reac cr O:ers:!cns Su:erviser 1.1C Reac:er :acility Staff a.

Scientific / Technical Personne! available as needed from Resea.ch Cen:er s aff 5.

Operations 5

c.

Supper:

Persennel avai.25!e as reeded from Research Cen:er staff 8112070067 010026 PDR FOIA PDR g't tgV181-317

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. acill:y Insurance

!.19 a.

Ceverage indemni:v: S!.5CC.CCO Liabill v: $100.000.000 Procertv damage: 3220.000.000 b

Annual Premium Insurance is fo. entire si:e. No brea'<down ava!!able.

n 9

u.w,i v.T u

.s.

2.1 Reac:cr Type Ocen cocl. lieht water mecerated. cla:e fue!.

Re' search reac:er.

2.2 Reactor Vessel a.

Configuration 0:en :cci b.

Overal! Dimensions 13.0 f:(3.96 m) !cn2 X 7.0 f:(2.13 m) wide X 13.0 f: (5.h9 m) deec.

c.

Material Ordinarv concrete d.

Ncemal Operating Pressure 5.75 csiz (0.2 bar) e.

Scrmal Opera:1.-6 o

o Tempera:ure 105 F (21 C) 2.3 Core a.

Volume 2.17 f (62.0 l) b.

Overall Dimensiens 1.33 f:(0.21 m) lone X 0.35 f:(0.26 m) wide X 1.96 f: (0.60 m) hizh.

c.

Lat: ice Configuratien Two erids: 10 elements wide X a elements !cne and 7 elements wide X 7 e!cments lenz d.

%mber cf Elemen::;

1.

Standard 12 2.

Centrol 4

133

2 I ~' R r

e.

.\\1aximum Number of Cric u, c e. : r..s, a. c _..,,...s -

s..

fer Fuel 125 (73 in one tric and ' 7 in -he c:ner) f.

Subdiviced Cere 1.

Number of Subcivisiens None 2.

Subdivision Diife. en-

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.N v.

M.r_= N.=.

3.

N.umcer cI :.,emen;s,cer

.C,.- m y.: s 1' C..

N u' I.=. ~ '- l.i c ' '_' ! =.

..v u.-.....,.

4,.,-..,a.

C v n ' i i. =... =.. ' J.". +... ~=

_ =.

r 1

b.

Ve!ume 2.7 X 10' f:' (76 5 m')

c.

.iL-

..,c2

q.,..:., 4,. c. s. c.,. n c.......... c.. -._..

L, c t,...:,.<

i

...v 2.5

.\\1ccerate r Lish: wa:er

2.6 Blanke

Cas Ncne 2.7 Ref!ec:crs 3.0 in (7.62 cm) X 3.0 in (7.62 cm) X 27.0 in (63.53 cm) 6G61-T6 Al clad trachi:e.

2.3 Therma! 5 hie!d Ncne 3.C f: (.,,. m) CerCre!e cCcl Wa!!s.

47 O!c!cEiCal 2nie!c.

2 a.

Ex:e.nal Radiation Levels Eess than 300 mrem /hr 2: ccol surf ace.

Less -han 2 mren/hr :hrcuzh cec; wa!!s.

2.10

?cwer Level

.N v- -.., = 1.s. =. c y.<..=. =..

1.\\"i w" c.

b.

Pulsing Not acciicab!e

,;r

.y-

..a.t 1.., _= -, t

,1

... 3

?cwer Densi:y a.

Vclumetric L66.3 3 K.V /f ' (16.! 3 K W. !)

(S..ie,.2,l'.).3.e) 132

t. r~R b.

Linear 3.55 KW/f- (11.65 KTim)

(2.10. si(Num:er ci.:!a:es/

Pins X F12:e/?in Leng h))

2.12 Ncemal 5pecific Power 165.91 KT/lb (365.0 KT/kz) L'-235 (2.10.2/3.1.5) 2.13 Reac: r Control 2.

Safe:y Reds 1.

Number 2 cr 3 2.

Shape r.d Dimensicns Grooved. ended end rec:2. au!ar tube. 0.5S in z z cm) X 2. 2 i. b.

. cm) X 2.,.,- !.n.::.:: cm,.

( 2...

2

.2 t

3.

Ma:eria! anc Leading 1.5:6 bc.-a ed stainless s ee!.

a.

Norma! Ti:hc.awal/

Inse.-ica Speed 3.75 in/ min (9.53 cm/ min) 5.

Scram Inser-icn Speed 26 in/sec (116 c.,/sec) 6.

Total Reactivity 0.065 De!:a K/K 7.

Ncemal Average Reac-tivity Addinen Rate 0.0032 De!:a K/K/ min 3.

Scram Mechanism Safe:v rod marnet curren: inter.co:

b.

Pulse Reds i

1.

Number None 2.

Shape and Dimensions Not ac$licable j

3.

Ma:erial anc Le~ading Not acclicable i

f l

l C.

Normal Withdrawal /

Inser-icn Speed Not acclicable l

l 3.

Scram Inser icn 5:eed No: ace!! cable l

6.

To:al Reac:ivity No: acclicable 135 l

L

i_.oa 7.

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2_..

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p. m _.i =,

2, m

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x S.

Scram Mechanism Nc: a: licable c.

neeu., anne Roc.s I.

Number

.c. ;. _2..._..d D ;. =..~. <..n s

"..m

_..d

.-.._=.m".'_.-. _. =... R 3 i n ( ?...?.

n X 2.25 in f 5.72 cm) X 25.S3 in(65.72 cm).

3.

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1..., e.,.: s-,.

. s 5.

Tc:2! Reacnvire C.C'-S Del:a K /K 6.

Ncr.a! Ave.-age Reac-nvir/ Addition Ra:e 0.0079 Delta K/K/ min 7.

Scram Mechanism Nc: orovided d.

Chemical Shim Cen:rel 1.

Chemica!

None 2.

Leading Net acclicable 3.

Ccr.:rci Mechanism Not a:ciicable 4

Tctal Reac:ivi:y Not acclicable e.

curnao.e Po.ison

~

1.

Isc cces U:ihzed Ncne 2.

Lcca:icn No: acclicable 3.

Leading Not acclica:!e 2

Tota! Reactivi:y Net a 0!! cable t <vb

4 LPR

~.

=.L = r_

3.1 Standard Fuel Element a.

C onfiguration 10 curved (5.51 in (12.0 cm) radius) fuel cla es containing a total of 0.22 lb (0.I9 kr) U-235.

No :'e a: lower end.

5.

Elemen: Dimensiens 3.15 in (3.0 cm) X 3.0 in (7.61 cm) X 30.37 in (S7.31 cm) inc!udine nc::!e.

Overal! ?! ate /P.n Dimensicns 2.9 2 In (7.'-2 cm) X C.:6 in iC.! 5 cm) X 22.63 +

c.

' (6 2.5 5 cm).

c.

Number of Pla es/? ins per Elem en:

10 Dis ance Ee: ween Pla:e/ Pin e.

Center!ines 0.33 in (0.33 cm) f.

Active Per:icn of Fue! P!a:e/

Pin 1.

Dimensions 2.0 in (6.1 cm) X 9.03 in (0.C3 cm) X 23.5 n (59.69 cm).

t 2.

Comcositien Uranium-Aluminum allov.

I f

3.

U-235 Enrichmen:

93?$

I 4

Fissile Material Densi y 0.022 lb/in* 3 (0.69 2m/cc) U-235

.z.

Reflec cr -crtion ci rue!

Pla e/ Pin 1.

Comccsi:icn.

None 2.

Dimensions No: acclicable h.

C!ac 1.

Composition

!!CO Aluminum l

t 137

s e.1

..x..; w. < - a 55 rt. J.i 5 :. (u. ; 2. -)

a a

..i-1.

q-1. a.

.c.i.=. a 1.

Composition 63.o, i _t e.:uminum 2.

ThiCkr.ess 0.19 in (0.' S Cm) s

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w 56 r=ca.

.N' e 6. w' v v..

3

.I17 O

. -. ~

LPR t

.~

Recrecessed at du? n l'

g.

Dispcsitien of Spent Fue!

Savannah River. Scu:h Carelina r

Nationa! Lead cask Spen: Fue! Shipping Cask n.

..s N.ot orovice.

_ pent ruel h.andling

.t.

Peel wa er iscicoic analvsis. Fact surf ace air' j.

Fuel Failure Detection car:!culate moni cr.

3.2 Fuel Inven: cry Curren: F!ssile Ma:erial a.

• !nven: ry Sta us 1.

New Fuei :n-Frecess Ncne 2.

New Fue! On Mand 5 s:andard. 2 cen:rci. 2 Oar:ia!

3.

Fuel In-Cor e -

12 siandard. L cent:el v

4 Spent FuelIn Sterage None i

5.

qcent rue,,ceing Re recessed Ncne J

t 6.

Non-fuel Special Nuc!ea.- Ma:erial Ncne b.

Fissile Material Inventerv.

I Needec to Assure Cen-inuity I

of Opera:icns I.

New Fuel In-Process None 2.

New Fuel On Hand 3 standard. 2 con:rol. 2 car-ial t

i 12 standard. a con:r:I 3.

Fuel In-Cere I

3.5 Fue! Scorce 1

The Babceck & Wilccx Cemoany a.

Fue! Fabricator I

Lvnchburz. Virginia l

139 4

.a-,,,---.,.~-

.,c,--

_,,-,.-,-n.-,

m-,

e,

-,-,---.-,,,--,e--,.._-

s LFR 1

b.

Fue! Su:: lie.-

The Sabcock & T:!c x Comcahv Lynchbu.2. Victinia c.

Fissile Ma:erial Origin U.S.A.

d.

Enrichmen: Su plier U.S.A.

e.

Methec cf Fabrica:icn Uranium-A!urninum a!!ov ho: rollec in aluminer clad. swased er cinnec in a!uminum side c:a:es.

f.

Fuc' Element C:s:

Unknown a.

u. =-.:.. r. e..,.s _c : : =..:. t.,-

.. v n

5.1 Fue! E!emen: Mea: Transfer Area 117.22 f:- (10.92 m')

(Number of F!a es/ Fins X Ac:ive F!ste/F:n sur: ace m Centac: wi:h Ccclan:)

?

2 2.2 Fue! Elemen: Flow Area 0.75 f t- (0.07 m )

2.3 Fue! Elemen: We::ed Ferime:er 61.0 f: (1S.73 m) i L.c Fuel Mea: Thermal Resistivity Unknown

2.5 Clac-Ceclan

Hea: Transfer Ceefficient (a: Hot Soc:)

1.200 BTU /hr-f:2-F (6.S !6 W/m'- Ci (forced cco!!n2) 2.6 Hea: Flux a: F! ate Surf ace L

L 2

a.

Nermal Average Heat Flux 2.9 X 10 STU/hr-f t' (9.15 X !O W/m )

c.

Feak Hea: Flu.k 1.

Wi:heu: He: Channel Factors 9.14 X LO BTU /hr-ft2 (2.SS X 105 W/m?)

4 2.

Wi:h Hot Channel Fac:crs Not croviced 140 i

D 5

LFR c.

Axial Feaking Fac:ce in Mc:

Channe! (:.re m.mx:11 -.riss en Rate Distributien) 1.

Wi:hout Mc: Channe!

Fac ces L.4 2.

With Hot Channel Fac:crs No: crevided c.

Het Sect Loca:icn Unknown L.7 Feak Opera:ing Fuel F's:e/ Fin Tempera ure a.

A:,r!a:e!-. n rn: ace 1.

Wi:het: Mc: Channel Fac:ces 201 F (9L C) 2.

Wi a Het Channel Fac:ces Not crevided b.

Inside Fuel Niest 1.

Withou: Het Channel O

0;.0- (95 C) 2 r ac:ces e

2.

With Mc: Channel Fac:ces No: crovided 0.3

.Orimary Ceciant Lizh: water t.9 Coelan: Flow a.

F!ow Direc:icn Ver-ically downward throush cere Flow Induced By 25 HP cen:rifu2a! oumo c.

c.

Normal Flow Ra:e SSS ecm (3.3601/ min) d.

Ataximum Flow Ra:e SSS rom (3.3601/ min) e.

Alean Ccre F!cw Ve!ccity 2.05 f t/sec (C.63 m/sec) f.

Ncemal Core Inle:

0 Tempera:ure 70 F (21 C) 1L1

4 L.c o

.s

.y. ~.. =.' C ' - a ~i a..~.. r a...,..'. - a.

g

<.ea r(

..,-.C)

.m s e h.

.=., '< L O Ls > =.,...t.........

1.

.w..

Rise a: Hot Scot.

1.

Without Hot Chanc.el c

o

-rac crs

7. e,3.- (.,. 2 e C) r., ;. x. u. o. C. _=.,. i

=,rr.

s

.N o., e.,.. s...

Cs. u...

..<<u... =. C..

w u...

c.. :., - < ; - (.

.%.. )

.s s...... _. u.

~

t,._...

.c.,.

v.

.?.*...u. v L,. : n. L.n.,.., I

..6

. = =

\\,.,..,. :.

.v.

..v.

.vt 2.

Ti:n Mc: Char.nel Not orovice:

rac:crs 2.10 Mc: Char.ne! Fac: rs (including Cnly Effects 0:her :han Nuclear

.... 5.,

O r e _= ' ' '. v..s)

.o.2'..--.,

q,

. s.o3

~

=

..- C ^ v-1.=... *. 1....

a.

=. ".-..R.; s e.N o ?. - - - JI w _ d

-s.v da v

F. :n....

...-. =

-a.

3...s a

.N v-. o rm v.

ad.

r.

u.

c.

C:hers No crovided 4.! !

Core Hea: Dissica:!cn Sys:em Frirrarv-secencarv he2: exchanzer.

1.,.

s

r. v-

s..,%.

C,v,

_=...

L, L,.n. n t

.,s....

.l

.v a.

2. l.'>.

C a.y...o w r u... =. R.. i C'.' a.i

,E., V, s. *. '.1

.N A. *. 'w.=.' C 'n v a. "...'.' r.

a.

,J.,c r s t C a s e. :., a:s e c. -.:me : rom Shu:down :o Ccclan: Indepen-cence Ti:nou: Fue! Dis:Or:ico 3.0 sec

. 13 r.....

..c.": C ra. C c.il.. S v s. a.m.

N -

~a

..w.

.I # ".P O

,r

/-

e L?R 3.

NUCLEAR DATA

/

3.1 Fuei Leading a.

11inimum Cri;ical Alass 1.0S I$ (2.3S Rc) O-233 b.

Normal Core Leading 1.25 lb (2.7% kg) U-235 (Eeeinnine of Cv. cie at o

=

Ra:ed Power)

. laximum K Cemeenents

\\

c.

excess 1.

Tempera ure C.003 Delta K/K 2.

Ecuilibrium Xenon G.023 De!:a K/K 3.

Ecui!!brium Sa.~.arium Nc: crevided Xenon Overrice 0.006 De!:a K/K 3.

Eurnup (!..c!ccing Nc: : rov'.ded Eurr.able ?cisen) 6.

Experimen:a! Sample 0.C!3 De!:a K/K 7.

Others Not oroviced S.

Total 0.027 De! a K/K I

d.

Shutdown 51argin C.01 De! a K/K wi:n the most react ve shim-safe v red and he re2ulatinz red fully wi:hdrawn.

t l

l 3.2-Reac:ivi v Ceefficients a

l a.

Ternpera:ure

-9.6 X 10 ' De! a K /K/ F 1.

Aledera:cr

(-1.73 X 10 Del a K/K/ C)

~

l l

2.

Deppler Nc: crovided 3.

Fue! Expansien Nc: crovided L.

Bernable Peisen Not crevided l

b.

Vcic Nc: orovided 1

l I

123 1

l

w

?f LPR 5.3 Neutr:n Flux Densi:!es 13 a.

5:eacy Sta:e Average Thermal 3.0 X 10 n/cm /see I

b.

5:eady 5:a:e Peak Thermal c.0 X IC n/cm /sec 12 c.

5:eady Sta:e Average Fas:

1.0 X 10 n/cm /see l'

2 d.

5:eacy State Peak Fas:

1.5 X 10 n/cm /sec e.

Peak Pulsing Power Nc: ace!! cable f.

Fulse In:egrated Power Net acclicable 5.0 Fulnng Charar:eris:ics Fulse feri:d No: a::!icable a.

b.

Fu!LWic:n a: Ma!! Maximum Nc a:clicable c.

Maximum Frequency cf Fulses Net aro'icable 5.5 Fissicn De.nsi:V.

l' 8.2 X 10 ~ fissiensiin3 (5.0 X 1011 a.

Nermal Average, fissiens/cc) 13 b.

Feak 2.6 X 10 fissions /in3 (1.6 X I G "i o fissiens/cc) f

/

,,x:al rea, /.,, verage Ra:io x

c.

for Typical Element 1.L 4.6 Maximum Fissien Produc: Inventery Unknown 4

,/

6.

OPER ATING EXFERIENC E

]

~

6.1 Fccced Ou aoes in :he Fast Fis e Y ea. s

~

a.

Equipmen: Malfunction 20 b

F b.

Perscnnel Errcr h

t,.i c.

Fup pot.er Cperating Hours 12S s

j 0

/

.k

.f*f i t.

e

\\

?,

e' I

f-

'i-I

~

e '-

s*a s

F 1 4 Es l

LPR q,.

G L. 2... %n.c

_e.

_. ec

.1 Acencv. Rescensible for Regula: cry Jurisdic:icn U.S. Nuclear Regula:crv Cernmissien 3.

PAST MODI. IC ATIONS AND FUTURE PL ANS S.1 Pas: Major Modifica:icns a.

Power increase /Da:e Frem 200 KW to 1 MW/Sectemcer 25. 1962 b.

Fue! Ccnve.sien/Da:e Ncne None c.

0:her/Da:e 3.2 Future Maice Mcdifica:icns a.

?cv.er increase /Da:e None clanned 5.

Fue! Conversicn/Da:e Ncne cianned i

c.

Decommissicning/Da:e No: clanned d.

O her/Da:e None clanned t

5.3 Future Reac cts a.

Type /Dare None clanned l

l 9.

REACTOR. LABORATORY. AND EXPERIMENT AL F ACILITIES l

9.1 Accelera:crs a.

Descrip;ien None

[

9.2 Eeamper:s a.

Descrip:ica h horizental f

5.

Dimensienf 1: S.O in (20.3 cm) diameter 3: 3.0 in (7.6 cm) diame:er c.

Thermal Neutron Flux Unknown d.

Fas: Neu ren Flux Unknown e

125

LFR e.

Gamma Dese Ra:e Sc: Orev:ced 9.3 Conver:er 31ccks a.

Descriptien None b.

Dimensions Not acclicable c.

The mal Neu:ren F!ux Nc: acc!ic2ble d.

Fas: Neu:ron Flux Nc: a o icable e.

Gamma Dese Ra:e Nc: at !! cable 9.i Crit:ca' Asseme.:es a.

Descrip-icn CX-10 b.

Dimensions Nc O rcs iced c.

Therma!.Neu ren Flux Nc: Orcviced d.

Fas: Neu:ron Flux Nc: orovided e.

Gamma Dese Rate Not crevided 9.5 Gamma Scurces a.

Descrip:len Ncne b.

D:mensicns Net acclicable c.

Gamma Dese Rate Not acclicable 9.6 Hot Cells a.

Descrip;ien O ce!!s. var:cus sizes b.

Dimensicns Frem L.0 f t (1.22 m) X 9.0 f (2.7L m) X 9.0 f-(2.70 m) to S.0 f- (2.LL m) X 16.0 f: (L.SS m) X 15.0 f: (2.57 --).

9.7 Irradia:icn Racks a.

Desc.-iptien Ncne IL6

LFR Dimensi ns Net are!icable c.

Thermal Neu:r:n F!ux Not zeelicable c.

Fas: Neutren Fiux Not a::licable e.

Gamma Dose Ra:e Not acolicable 9.3 Neutren Activation Analysis a.

Descrip:icn Comou:er-based multichanrei analv:ers for c.:n-cestrue:!ve de:ermina:icn ef trace cuan:ites cf ise:::es.

9.9 Neu:ren Ger. era::r a.

Descriptien None

. herma! Neu:ren Fiux Not acclica:fe T

b.

t c.

r as: Neutren riux Not ace!.! cable

. )

9.10 Neu:ren Radic raphy a.

Description 0.0 in (10.16 cm) diame:er. !./D = 61 9.11 Neu:ren Sources 1.

Descriptien Ncne b.

Dimensiens Not acc!icable c.

Thermal Neu ren Flux Not acclicable c.

Fas: Neu:ren F,Iux Net acclicable 9.12 Neutren Spec:reme:er a.

Descrip icn None 9.13 Fneumatic Tubes a.

Descrip icn Nene 5.

Dimensicns Not acclicable i

i

/

147 m

LFR c.

Thermal Neu:ren Flux Not ace!! cable d.

Fast Neu:ren Flux Not acclicable e.

Gamma Dese Ra:e Not acclicable 9.14 Radicisotope Labora: cries a.

Descriptien Available 9.13 Reac:cr Cere a.

Description Central loca::en 5.

Dimensiens 3.0 in (7.6 cm) X'3.0 in (7.6 cm) X 22.0 in (60.96 cm).

I3 2

c.

Thermal Neu:ren Flux 4.0 X 10 n/cm /sec 2

i d.

Fas: Neu ren Flux 1.5 X 10 n'cm /sec e.

' Gamma Dose Ra:e 3.0 X 10 rad /hr 9.16 Reac:cr Foot a.

Descriptien 4.0 in (10.16 cm) f rom core f ace.

b.

Dimensiens Varicus 12 2

c.

Thermal Neu:ren Flux 4.0 X 10 gfcm 73ec 11 n/cm?/sec d.

Fast Neutron Flux 3.0 X 10 6

2 e.

Gamma Dese Ra:e 3.0 X 10 n/cm f 3,c 9.17 Thermal Column a.

Descriptien None b.

Dimensions Not acclicable c.

Thermal Neutron Flux Not acolicable l

d.

Fast Neutren Flux Not acclicable 1

e.

Gamma Dese Ra:e Not acclicable 1

123 9---

~

w

--w-

O

,. -..s 10.

RESEARCH AND TECHNIC AL PROGR AM AND REACTOR UTILIZAT:ON

SUMMARY

10.1 nesearen, n ecnnical, and i ra:ning Program The Lvechburr Peel Reacter is ecera:ed en a cernand basis for neu:ren activa:!cn analvsis.

r.eut.-en racicerachv. neutren and ramr a ir.acia-

icr.s. reac:ct ecera:cr traininz. anc c rer cemearv creer:e:arv creiec:5.

e Nc..

i n..,

e.;r e..;-.t b.o+s.r.s...+s~-. e.

g.

t.i.

t u..i. L i :..=. C u+ n : q r m.. e_ t - =_ D, Ly n_ e_ _c c. y

-m

___m i_

m.

'i.'

Neu:renics Ncne 11.2 5:ruc: ural Des:gn a.

Reac:ce Vesse!

Nene b.

Fuel None c.

Cen:ainmen:

Ncne

! !'.3 Hea: Transfer Nene 12.

AC!LITY DESIGN AND OPER ATION REFERENCE DCCUMENTS BAT-72 & Succlemen:s I throuzh 12 - ccel :es:

i reac cr ha:ards evalunion ar.d a ere ents.

Tecnn:ca! 5cecifica:icr.s fer tre Lvrcnburt Pect I

Reacter.

t l

l 1.9 1

l I

9 e

0 e

6 e

e d

=

O e

0 0

15G

,