Apparatus and method for estimating core performance

• US 5,638,413 A
• Filed: 06/21/1995
• Issued: 06/10/1997
• Est. Priority Date: 06/21/1994
• Status: Expired due to Term

• Current Assignee: Kabushiki Kaisha Toshiba (Toshiba Corporation)
• Original Assignee: Kabushiki Kaisha Toshiba (Toshiba Corporation)
• Inventors: Iwamoto, Tatsuya, Tsuiki, Makoto, Nakajima, Tsuyoshi, Uematsu, Mikio
• Primary Examiner(s): Wasil, Daniel D.
• Application Number:
  US08/493,106
• Time in Patent Office: 720 Days
• Field of Search: 376/215, 376/216, 376/245, 376/259, 364/224.3, 364/224.9, 364/551.01, 395/11, 395/200.01, 395/800, 395/907
• US Class Current: 376/245
• CPC Class Codes: G21C 17/00 Monitoring; Testing measuring in general G01; Maintaining
• CPC Class Codes: G21D 3/001 Computer implemented control
• CPC Class Codes: Y02E 30/00 Energy generation of nuclear origin
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors

Abstract

The present invention relates to a technique for estimating core performance which includes the steps of: dividing a reactor core into a plurality of core portions, each consisting of at least one fuel assembly, then further dividing each of the core portions into segments by planes perpendicular to the axis thereof and allocating a parallel processing apparatus having a plurality of arithmetic processing units, a memory for storing processing data of the arithmetic processing units, and communications circuitry for transferring data with respect to the arithmetic processing units, in a manner such that the arithmetic processing units correspond to the segments of the core. Data on the power distribution for the entire core portion to which a corresponding segment belongs is transferred to each arithmetic processing unit, before each of the arithmetic processing units performs thermal hydraulic calculations. Each of the arithmetic processing units calculates the enthalpy distribution and void fraction of coolant in the segment on the basis of the power distribution data, independently of other arithmetic processing units.

Claims

1. An apparatus for estimating core performance, comprising a plurality of arithmetic processing units, a memory means for storing processing data for said arithmetic processing units, and communications circuitry means for providing data communications between said arithmetic processing units;

wherein;

each of said arithmetic processing units corresponds to a segment that is formed by dividing a core portion consisting of at least one fuel assembly by planes perpendicular to the axis thereof;

obtains a power distribution for the entire core portion to which said corresponding segment belongs, via said communications circuitry; and

calculates the enthalpy distribution, density distribution and void fraction distribution of coolant within each segment on the basis of said power distribution, independently of other arithmetic processing units.

2. An apparatus for estimating core performance according to claim 1, wherein said apparatus of estimating core performance repeats the calculations for said enthalpy distribution, density distribution and void fraction distribution of said coolant;

substitutes a void fraction distribution V.sup.(n-1) of an (n-1)th iteration into a void fraction distribution V.sup.(n) during the calculation of the following simultaneous equations for enthalpy distribution H.sup.(n) and void fraction distribution V.sup.(n) of said coolant within said calculations of said enthalpy distribution and void fraction distribution of said coolant;

space="preserve" listing-type="equation">H.sup.(n) =F1(V.sup.(n))

space="preserve" listing-type="equation">V.sup.(n) =F2(H.sup.(n))

and each of said arithmetic processing units independently perform thermal hydraulic calculations for said corresponding segment by calculating enthalpy H.sup.(n).sub.(z) for each of said segments along the axial direction of said fuel assembly, independently of void fraction V.sup.(n) (z).

3. An apparatus for estimating core performance according to claim 1, wherein said apparatus for estimating core performance repeats the calculations of said enthalpy distribution and density distribution of said coolant;

substitutes a density distribution D.sup.(n-1) of an (n-1)th iteration into a density distribution D.sup.(n) during the calculation of the following simultaneous equations for enthalpy distribution H.sup.(n) and density distribution D.sup.(n) of said coolant within said calculations of said enthalpy distribution and density distribution of said coolant;

space="preserve" listing-type="equation">H.sup.(n) =F3(D.sup.(n))

space="preserve" listing-type="equation">D.sup.(n) =F4(H.sup.(n))

and each of said arithmetic processing units independently perform thermal hydraulic calculations for said corresponding segment by calculating enthalpy H.sup.(n) (z) for each of said segments along the axial direction of said fuel assembly, independently of density D.sup.(n) (z) .

4. A method of estimation core performance, comprising the steps of:

dividing a reactor core into a plurality of core portions, each consisting of at least one fuel assembly, then further dividing each of said core portions into segments by planes perpendicular to the axis thereof;

allocating a parallel processing apparatus comprising a plurality of arithmetic processing units, a memory for storing processing data of said arithmetic processing units, and communications circuitry for transferring data with respect to said arithmetic processing units, in such a manner that said arithmetic processing units correspond to said segments of said core; and

transferring to each arithmetic processing unit data on the power distribution for the entire core portion to which the corresponding segment belongs, before each of said arithmetic processing units performs thermal hydraulic calculation, then causing each of said arithmetic processing units to calculate the enthalpy distribution, density distribution and void fraction distribution of a coolant in said segment on the basis of said power distribution data, independently of other arithmetic processing units.

5. A method of estimating core performance according to claim 4, wherein calculations for determining said enthalpy distribution, void fraction distribution of said coolant, and power distribution within said corresponding segment are repeated in a direction in which the power distribution of the core of the reactor converges;

a void fraction distribution V.sup.(n-1) of an (n-1)th iteration is substituted into a void fraction distribution V.sup.(n) during the calculation of the following simultaneous equations for the enthalpy distribution H.sup.(n) and void fraction distribution V.sup.(n) of said coolant within said fuel assembly in an n-th iteration of said calculations of said enthalpy distribution and void fraction distribution of said coolant;

space="preserve" listing-type="equation">H.sup.(n) =F1(V.sup.(n))

space="preserve" listing-type="equation">V.sup.(n) =F2(H.sup.(n))

and ethalpy H.sup.(n) (z) for each of said segments is calculated along the axial direction of said fuel assembly, independently of void fraction V.sup.(n) (z).

6. A method of estimating core performance according to claim 4, wherein calculations for determining said enthalpy distribution, density distribution of said coolant, and power distribution within said corresponding segment are repeated in a direction in which the power distribution of the core of the reactor converges;

a density distribution D.sup.(n-1) of an (n-1)th iteration is substituted into a density distribution D.sup.(n) during the calculation of the following simultaneous equations for the enthalpy distribution H.sup.(n) and the density distribution D.sup.(n) of said coolant within said fuel assembly in an n-th iteration of said calculations of said enthalpy distribution and density distribution of said coolant;

space="preserve" listing-type="equation">H.sup.(n) =F3(D.sup.(n))

space="preserve" listing-type="equation">D.sup.(n) =F4(H.sup.(n))

and enthalpy H.sup.(n) (z) for each of said segments is calculated along the axial direction of said fuel assembly, independently of density D.sup.(n).sub.(z).