Text

Florida Power & Light Evaluation of BNL 15X15 Lattice Std Problem.
	ML17346B249
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Site:	Turkey Point
Issue date:	10/10/1986
From:	Hoskins K, Knuckles E, Poteralski D; FLORIDA POWER & LIGHT CO.
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ML17346B248	List: ML17346B247; ML17346B249;
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FLORIDA POWER 6 LIGHT EVALUATION OF THE BROOKHAVEN NATIONAL LABORATORY 15x15 LATTICE STANDARD PROBLEM Prepared By: Date: D' Kevin C. Hoskins Engineer, Core Physics Reviewed By:

Ed Knuckles Date: P /6' Supervisor, Core Physics Approved By: Date: >>>> Z4 D.C. Poteralski Manager, Nuclear Fuel Technology 8&i02800'P PDR ADOCK i 861 02 i 05000250 )'

PDR ~

~ I ~ I BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.

Upton, Long Island, New York 11973 (516) 282'595 Department of Nuclear Energy FTS 666'ugust 8, 1986 Mr. Edward Knuckles Fuel Resources Florida Power and Light P.O. Box 029100 Miami, Florida 33102

Dear Mr. Knuckles:

As you requested, I have enclosed a copy of the BNL 15x15 W type fuel assembly Standard Problem. As indicated in the definition, the analysis of "the Standard Problem requires an assembly depletion calculation together with a series of reactivity defect calculations. The problem includes a burnable-poison rod assembly, and both rodded and unrodded assemblies. The burnable-poison rod and rodded assemblies include strong local absorbers and, as we discussed, are not an appropriate application of the methods presently being reviewed.

If you have any questions concerning the modeling or execution of this problem, please do not hesitate to contact us.

Sincerely,

/

.F. Carew, Group Leader Core Performance Group JFC/lr Encs.

cc: J. G. Guppy w/o W. Y. Kato w/o L. Lois M. S. Dunenfeld

FUEL ASSEMBLY STANDARD PROBLEM The standard problem is to be calculated in two dimensions, in an iterated-,

source mode using reflecting boundary conditions in the horizontal plane ne-glecting axial leakage. The following series of assembly depletion and re-activity defect calculations are to be calculated.

I. DEPLETION CALCULATIONS Provide the following edited quantities for an assembly with and without burnable poison rods at BOL, 500, 5000, 10000, 20000, 30000 and 40000 MWD/MT*. For the controlled assembly only provide the pin powers (item-l), reaction rates (item-3) and assembly characteristics (item-4) at BOL and 30,000 MWD/MT.

1. Relative pin powers

2. Assembly yolume averaged fuel pellet isotopics; U235, U238, Pu239, Pu~" , Pu 4 , Pu242 and calculated fission product densities [atom/barn-cm] at 500 and 40,000 MWD/MT

3. Assembly total reaction rates (A-absorption, F-fission)

a. Fuel u235 (A) Pu240 (A)

U235 (F) Pu240 (F)

U238 (A) Pu241 (A)

U238 (F) Pu241 (F Pu239 (A) Pu242 (A)

Pu239 (F) Pu242 (F)

b. Clad (A)

c. Burnable Poison (A)

d. Water (A)

e. Control Rod (A)

4. Assembly Characteristics

a. k - Infinite Multiplication Factor

b. M~ - Migration Area [cm ]

c. BM

- Material Buckling [cm ]

d. B

- Delayed Neutron Fraction

e. Two-Group Inverse Neutron Velocityi'sec/cm]

5. Two-Group Collapsed Assembly Averaged Cross Sectionsi'

[cm],)a[em ], fr[em ],

v)ffcm- ], ~Q [watt/cm], )f[cm" ]

These are editing points and do not necessarily correspond to the depletion steps.

t Thermal breakpoint assumed at 0 625 [eV]

May 8, 1985

FUEL ASSEMBLY STANDARD PROBLEM II ~ REACTIVITY DEFECT CALCULATIONS Provide the following reactivity defects (Xd k/k) for an assembly with and without burnable poison rods at BOL and EOL (30,000 'Mwd/MT):

UNPERTURBED PERTURBED REACTIVITY DEFECT {gb, k/k

CASEt CASE

1. Fuel TemPerature Tbase (Tfuel ) fuel moderator

2. Moderator Temperature (Tmoderator)

3. Moderator 8 Fuel Temperaturett base (TModerator & TFuel) moderator 68oF base fuel 68'F

4. Moderator & Fuel Temperaturett base (TModerator & TFuel) moderator 300oF base fuel 300'F

5. Boron Concentration (Nboron) base 0 ppm boron

6. Xenon Concentration (Nxenon) Equi 1 ibrium 0

7. Control Rod > Unrodded Rodded f11 f1 for each state-point.

t Unperturbed parameters are at their base values indicated in the Standard Problem definition.

g In the case of the W (17xl7) assemb'ly only the unpoisoned assembly is required.

tt Pressure is to be maintained at base value.

TABLE-1. TYPE-1 FUEL ASSEMBLY DATA 15 x 15 W Type Fuel Assembly 4

1 1 111 1 - Fuel Rod 1113 2 - Burnable Poi son Rod (BPR) 31111 3 - Guide Thimble 113113 4 - Instrument Thimble 1111111 11111111 Note: 1. For an unrodded or unpoi soned case replace all BPRs (2) with guide thimbles (3).

2. For a rodded case control rods are inserted in guide thimbles (3).

2. Fuel Assembl Data Rod ar ray 15 x15 Fuel rods per assembly 204 Rod pitch (in)P 0. 563 Assembly pitch (in)** 8.466 x 8.466 Assembly length (in) 151. 0 Active fuel length (in) 144.0 Number of spacer grids~ 7 Composition of space grid 83'A Inconel 718, 175 Stainless Steel Weight of spacer grids (lb) 15. 5 Number of guide thimbles 20 Number of instrument thimbles 1 All dimensions are given at cold (68'F) conditions.

i'even in active length.

- Center to center assembly pitch.

TABLE-1. TYPE-1 FUEL ASSEMBLY DATA (Cont.)

15 x 15 W Type Fuel Assembly

3. Fuel Rod Data Clad O.D. (in) 0.422 Clad thickness (in) 0.0243 Diametral gap (in) 0.0075 Clad mater ial Zi real oy-4

4. Fuel Pellet Data Haterial U02 - Undished Density (5 of theoretical) 95 Enrichment (w/o) 2.25 Diameter (in) 0.3659

5. Guide Thimbles and Instrument Thimble Data Number of guide thimbles 20 Number of instrument thimbles 1 Composition of thimbles Zi real oy-4 Guide Thimble O.D. (in) 0. 545 Guide Thimble I.D. (in) 0. 515 Instrument Thimble O.D. (in) 0. 545 Instrument Thimble I.D. (in) 0. 515

6. Eontrol Rod Data Neutron absorber (w/o) 5$ Cd, 155 In, 80% Ag Absorber diameter (in) 0.347 Absorber density (lb/in3) 0.367 Cladding material 304 Stainless Steel Cl ad O.D. ( i n) 0.445 Clad thickness (in) 0.019 Number of control rods 20

INTRODUCTION TO ANALYSIS RESULTS This transmittal contains the results of FPL's evaluation of Brookhaven's 15xl5 lattice Standard Problem using FPL's CHEETAH/PDQ methodology. As agreed, the analysis was performed only for the unpoisoned/unrodded lattice. Due to the structure of FPL's CHEETAH/PDQ methodology, some of the data provided is slightly different from that requested:

1) Instead of providing absorption rates for all of the water in the assembly, absorption rates for the guide and instrumentation thimbles are given. This modification was agreed-to previously.

2) Reactivity defect data was generated using CHEETAH only. It is FPL's position that the pincell CHEETAH and unit-assembly CHEETAH/PDQ agree closely on these calculations, and thus CHEETAH data is sufficient for the calculation.

3) Both CHEETAH and CHEETAH/PDQ isotopics were provided for the conditions requested. It is felt that the CHEETAH data is slightly more accurate because FPL's PDQ uses simplified isotopic chains, which causes a small but acceptable difference in Pu isotopic calculations.

I t

~

~ A

4) CHEETAH does not edit information for the fast group inverse neutron velocity; code modifications would be required to edit this value. Therefore, only thermal group inverse velocities are provided. Inverse neutron velocity data has never been used explicitly in PPI" s physics calculations, and its need is not apparent.

Therefore, it is felt that CHEETAH's 'shortcoming'n this respect is of little consequence.

5) CHEETAH does not edit delayed neutron fractions, and of course, PDQ does not calculate them. The delayed neutron data was generated by hand using fission rates from PDQ and documented isotope-dependent delayed neutron fractions.

If you have any questions on the attached data, please contact E. Knuckles (305) 552-3444 or K. Hoskins (305) 552-3437.

m 2

W BNL STANDARD PROBLEM ANALYSIS TABLE OF CONTENTS Ficiures Title Relative Pin Powers 9 150 MWD/MTU Relative Pin Powers 9 500 MWD/MTU.

3 Relative Pin Powers 9 5000 MWD/MTU....................

Relative Pin Powers 9 10000 MWD/MTU.

Relative Pin Powers 9 20000 MWD/MTU.... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Relative Pin Powers 6 30000 MWD/MTU...................

Relative Pin Powers 8 40000 MWD/MTU...................

Tables Title CHEETAH vs. CHEETAH/PDQ Koo vs. Burnup................

Assembly Volume-Averaged Isotopics.......

Assembly Total Reaction Rates 150 MWD/MTU.............

Assembly Total Reaction Rates 500 MWD/MTU....

i Assembly Total Reaction Rates 5000 MWD/MTU...

Assembly Total Reaction Rates 10000 MWD/MTU...........

Assembly Total Reaction Rates 20000 MWD/MTU...........

Assembly total Reaction Rates 30000 MWD/MTU...........

Assembly Total Reaction Rates 40000 MWD/MTU...........

10 Guide 6 Instrument Tube Absorption Rates..'............

Assembly Characteristics (koo, M2 , B 2 , ~ ,etc.........

12 Delayed Neutron Fractions 150 6 500 MWD/MTU...........

13 Delayed Neutron Fractions 5000 6 10000................

MWD/MTU

TABLE OF CONTENTS (Cont'd)

Tables Title Delayed Neutron Fractions 20000 S 30000...............

MWD/MTU 15 Delayed Neutron Fractions 40000 MWD/MTU...............

16 Thermal Group Inverse Neutron Velocity................

17 Two-Group Collapsed Assembly Averaged Xsecs...........

18 Reactivity Defect Calculations.

1 FIGURE 1

'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 150 MWD/MTU

.983

.979 1.000 1.012 1.043 1.060 1.067 1.065 1.039 1.050 1.040 1.032

.989 1.010 .985 .984 .997 .965

.957 .961 .961 .955 .953 .945 CHEETAH/PDQ DATA

FIGURE 2

'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 500 MWD/MTU 1.005 .983

.979 .979 1.000 1.025 1.012 1.043 1.060 1.067 1.065 1.039 1.040 1.050 1.040 1.032

.977 .989 1.010 .985 .984 .997 .965

.954 .957 .961 .961 .955 . 953'945 .

941'HEETAH/PDQ DATA

1 FIGURE 3

'BNL'TANDARD PROBLEM 15x15 W LATTICE RELATIVE PIN POWERS 5000 MWD/MTU 1.000 1.039 1.061 1.060 1.036 1.037 1.029 1.010 .987 .986 .998 .968

.964 .964 .958 .957 .949 .946.

CHEETAH/PDQ DATA

FIGURE 4 sBNLe STANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 10000 MWD/MTU

.987

.984 1.001 1.011 1.033 1.046 1.051 1.050 1.031 1.038 1.032 1.025

.992 1.008 .989 .988 .998 .972

.966 .970 .969 .965 .963 .956 CHEETAH/PDQ DATA

FIGURE 5

'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 20000 MWD/MTU 1.002 1.021 1.031 1.030 1.020 1.020 1.016 1.005 .994 .993 .997 .982

.981 .981 .978 .976 .971 .969.

CHEETAH/PDQ DATA

FIGURE 6

'BNL'TANDARD PROBLEM 15x15 W LATTICE RELATIVE PIN POWERS 30000 MWD/MTU

.996

.996 1.002 1.005 1.011 1.015 1.016 1.016 1.012 1.012 1.011 1.009

.998 1.002 .997 .997 .998 .990

.989 .990 .990 .988 .987 .984 CHEETAH/PDQ DATA

FIGURE 7

'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 40000 MWD/MTU 1.000 .997

.997 .997 1.000 1.004 1.002 1.007 1.009 1.010 1.010 1.007 1.006 1.008 1.007 1.006

.997 .998 1.001 .998 .998 .999 .994

.992 .993 .994 .994 .993 .992 .991 CHEETAH/PDQ DATA

TABLE 1 BNL STANDARD PROBLEM Koo VS BURNUP CHEETAH PXNCELL VS. CHEETAH/PD Koo Burnup CHEETAH CHEETAH/PDQ (MWD/MTU) ~On 1 15x15 Lattice 1.14129 1.14058 55 150 1.10463 1.10300 133 500 1.09916 1.09764 125 1000 1.09589 1.09425 136 5000 NC 1.05562 10000 1.00496 1.00347 147 20000 .91865 .91672 229 30000 .84832 .84626 286 40000 .79355 .79194 256 Total QK ( pcm) 0-40 K Bu 38396 38598 (PCM) (.5% diff)

Koo Includes Gap +Q,= (Kl-K2) x 10 /(K1K2)

NC = Not Calculated

TABLE 2 BNL STANDARD PROBLEM ASSEMBLY VOLUME AVERAGED ISOTOPICS +

(ATOMS/BARN-CM) 500 mWD/MTU 40000 NHD/MTU ISOTOPE CHEETAH* CHEETAH/PDQ CHEETAH* CHEETAH/PD U-235 1.52783 1.52846-4 1.62489-5 1.64792-5 U-238 6.72361-3 6.72366-3 6.49624-3 6.49561-3 Pu-239 2.15215-6 2.10674-6 3.18613-5 3.23974-5 Pu-240 3.3.2530-8 2.99997-8 1.74465-5 1.73614-5 Pu-241 8.50277-10 7.80787-10 9.84268-6 9.96180-6 Pu-242 4.33328-12 2.78212-12 6.83477-6 6.80422-6 F.P. 3.62248-6 3.56379-6 2.76862-4 2.76709-4

+ Does not include gap

CHEETAH values multiplied by 204 225 to generate Assembly Average Number Density

J t

TABLE 3 BNL 15x15 W LATTICE ASSEMBLY TOTAL REACTION RATES Buznu 150 MWD/MTU CHEETAH/PD

~Ieoto e Absoz tion (sec 1) Fission (sec 1)

U235 1.56352+15 1.29104+15 U238 9.45297+14 8.43912+13 Pu239 2.00797+13 1.28006+13 Pu240 8.35486+10 1.77856+8 Pu241 3.49011+8 2.56530+8 I

Pu242 Negligible Negligible Fuel Clad 3.73028+13 N/A Guide Thimble + 7.28549+13 N/A