ML18139C061: Difference between revisions

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| number = ML18139C061
| number = ML18139C061
| issue date = 10/04/1982
| issue date = 10/04/1982
| title = Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code.
| title = Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code
| author name =  
| author name =  
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
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=Text=
=Text=
{{#Wiki_filter:* PAGE 1 TABLE 1' ': Summary of Comparisons with THING-I Case I Pressure PotJer Flow I Tin I FQE Axial I Minimum DNBR No. I (psia) (%) (%) I Co F) I Offset I COBRA THING-I -------------------------------1-----
{{#Wiki_filter:*
---------1--------
PAGE 1
--------I I 1 2200. 1 1 2 . 1 0 0 . 554. I 1 . 2 4 zero I 1 . 2 7 1 . 30 I I 2 2400. 118. 1 0 0 . 563. I 1 . 0 3 zero I 1. 30 1. 33 I 3 2400. 101. 1 0 0 . 563. I 1. 03 large 1. 32 1 . 3 9 positive 4 2400. 81. 7 10 0. 618.4 1. 03 large 1.30 1. 33 negative 5 1855. 11 2 . 90. 515. 1. 03 zero 1. 47 1. 47 6 2220. 100.5 76.5 547. 1. 03 zero 1. 32 1. 32 ~': 7 2400. 101. 1 0 0 . 563. 1.03 large 1. 42 1. 50 positive
TABLE 1' ':
* Supplemental information to the letter from R. H. Leasburg (Vepco) to H. R. Denton (NRG), Serial No. 284, dated May 23,1982, entitled "Vepco Reactor Core Thermal Hydraulic Analysis Using the COBRA-IIIc/MIT Computer Code" .,~aii 0120305 a21004 I* * *PDR -ADOCK 05000280 ,: PDR p . ----*-----}}
Summary of Comparisons with THING-I Case I Pressure PotJer Flow I Tin I FQE Axial I
Minimum DNBR No. I (psia)
(%)
(%) I Co F) I Offset I
COBRA THING-I  
--------- -------- ------- -------1----- ---------1-------- --------
I I
1 2200.
1 1 2.
1 0 0.
554. I 1. 2 4 zero I
1. 2 7 1. 30 I
I 2
2400.
118.
1 0 0.
563. I 1. 0 3 zero I
: 1. 30
: 1. 33 I
3 2400.
101.
1 0 0.
563. I 1. 03 large
: 1. 32 1. 3 9 positive 4
2400.
: 81. 7 10 0.
618.4
: 1. 03 large 1.30
: 1. 33 negative 5
1855.
11 2.
: 90.
515.
: 1. 03 zero
: 1. 47
: 1. 47 6
2220.
100.5 76.5 547.
: 1. 03 zero
: 1. 32
: 1. 32  
~':
7 2400.
101.
1 0 0.
563.
1.03 large
: 1. 42
: 1. 50 positive
* Supplemental information to the letter from R. H. Leasburg (Vepco) to H. R. Denton (NRG), Serial No. 284, dated May 23,1982, entitled "Vepco Reactor Core Thermal Hydraulic Analysis Using the COBRA-IIIc/MIT Computer Code"  
.,~aii 0120305 a21004 I*  
* *PDR -ADOCK 05000280 PDR p. ----*-----}}

Latest revision as of 21:02, 5 January 2025

Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code
ML18139C061
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 10/04/1982
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139C060 List:
References
VEP-FRD-33-ERR, NUDOCS 8210120305
Download: ML18139C061 (1)


Text

PAGE 1

TABLE 1' ':

Summary of Comparisons with THING-I Case I Pressure PotJer Flow I Tin I FQE Axial I

Minimum DNBR No. I (psia)

(%)

(%) I Co F) I Offset I

COBRA THING-I


-------- ------- -------1----- ---------1-------- --------

I I

1 2200.

1 1 2.

1 0 0.

554. I 1. 2 4 zero I

1. 2 7 1. 30 I

I 2

2400.

118.

1 0 0.

563. I 1. 0 3 zero I

1. 30
1. 33 I

3 2400.

101.

1 0 0.

563. I 1. 03 large

1. 32 1. 3 9 positive 4

2400.

81. 7 10 0.

618.4

1. 03 large 1.30
1. 33 negative 5

1855.

11 2.

90.

515.

1. 03 zero
1. 47
1. 47 6

2220.

100.5 76.5 547.

1. 03 zero
1. 32
1. 32

~':

7 2400.

101.

1 0 0.

563.

1.03 large

1. 42
1. 50 positive
  • Supplemental information to the letter from R. H. Leasburg (Vepco) to H. R. Denton (NRG), Serial No. 284, dated May 23,1982, entitled "Vepco Reactor Core Thermal Hydraulic Analysis Using the COBRA-IIIc/MIT Computer Code"

.,~aii 0120305 a21004 I*

  • *PDR -ADOCK 05000280 PDR p. ----*-----