Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, SOFTWARE REQUIREMENTS, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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To submit a request, click below on the link of the version you wish to order. Rules for end-users are
available here.

Program name | Package id | Status | Status date |
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SAGEP-FR | NEA-1779/01 | Arrived | 09-MAR-2007 |

Machines used:

Package ID | Orig. computer | Test computer |
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NEA-1779/01 | Linux-based PC |

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3. DESCRIPTION OF PROGRAM OR FUNCTION

SAGEP-FR is a program package relating to sensitivity analysis for fast reactors, which consists of the SAGEP[1,2], SAGEP-BURN[3-5], PSAGEP[6-8], ABLE and ACCEPT codes[9-11].

(1) SAGEP:

SAGEP calculates sensitivity coefficients of reactor parameters with respect to the microscopic cross section in two- or three-dimensional systems (XY, RZ and XYZ). The target reactor parameters are multiplication factor, reactivity worth, reaction rate ratio, reaction rate distribution and breeding ratio.

(2) PSAGEP/SAGEP-BURN:

PSAGEP is a user-interface program for SAGEP-BURN. PSAGEP and SAGEP-BURN are used in combination. PSAGEP/SAGEP-BURN calculates burnup sensitivity coefficients of reactor parameters with respect to the microscopic cross-section in a two-dimensional RZ system. The target reactor parameters are multiplication factor, reactivity worth, reaction rate ratio, reaction rate distribution, breeding ratio, burnup reactivity loss and atomic number density.

(3) ABLE:

ABLE performs cross-section adjustment (STEP1) and prediction uncertainty evaluation (STEP2). ABLE calculates adjusted cross-section, cross-section-induced uncertainty of reactor parameters and predicted C/E values.

(4) ACCEPT:

ACCEPT performs prediction uncertainty evaluation of reactor parameters based on the bias factor method, the cross-section adjustment method and the combined method[9].

SAGEP-FR is a program package relating to sensitivity analysis for fast reactors, which consists of the SAGEP[1,2], SAGEP-BURN[3-5], PSAGEP[6-8], ABLE and ACCEPT codes[9-11].

(1) SAGEP:

SAGEP calculates sensitivity coefficients of reactor parameters with respect to the microscopic cross section in two- or three-dimensional systems (XY, RZ and XYZ). The target reactor parameters are multiplication factor, reactivity worth, reaction rate ratio, reaction rate distribution and breeding ratio.

(2) PSAGEP/SAGEP-BURN:

PSAGEP is a user-interface program for SAGEP-BURN. PSAGEP and SAGEP-BURN are used in combination. PSAGEP/SAGEP-BURN calculates burnup sensitivity coefficients of reactor parameters with respect to the microscopic cross-section in a two-dimensional RZ system. The target reactor parameters are multiplication factor, reactivity worth, reaction rate ratio, reaction rate distribution, breeding ratio, burnup reactivity loss and atomic number density.

(3) ABLE:

ABLE performs cross-section adjustment (STEP1) and prediction uncertainty evaluation (STEP2). ABLE calculates adjusted cross-section, cross-section-induced uncertainty of reactor parameters and predicted C/E values.

(4) ACCEPT:

ACCEPT performs prediction uncertainty evaluation of reactor parameters based on the bias factor method, the cross-section adjustment method and the combined method[9].

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4. METHODS

(1) SAGEP, PSAGEP/SAGEP-BURN

Sensitivity calculation is performed on the basis of generalized perturbation theory with diffusion core calculation.

(2) ABLE

Cross-section adjustment calculation is performed on the basis of Bayesian theory and least-square technique.

(3) ACCEPT

Prediction accuracy calculation is performed on the basis of the bias factor method, the cross-section adjustment method and the combined method.

(1) SAGEP, PSAGEP/SAGEP-BURN

Sensitivity calculation is performed on the basis of generalized perturbation theory with diffusion core calculation.

(2) ABLE

Cross-section adjustment calculation is performed on the basis of Bayesian theory and least-square technique.

(3) ACCEPT

Prediction accuracy calculation is performed on the basis of the bias factor method, the cross-section adjustment method and the combined method.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

SAGEP-FR aims at fast reactor analysis. Therefore, if it were applied to other types of reactors, there would be some restrictions in the physics model. For instance, upscattering is not taken into account, and only the Eigenvalue problem is available in core calculations.

SAGEP and PSAGEP/SAGEP-BURN has the following restrictions.

(1) Maximum number of energy groups is 70.

(2) Maximum number of regions is 99.

(3) Maximum number of nuclides is 34.

SAGEP-FR aims at fast reactor analysis. Therefore, if it were applied to other types of reactors, there would be some restrictions in the physics model. For instance, upscattering is not taken into account, and only the Eigenvalue problem is available in core calculations.

SAGEP and PSAGEP/SAGEP-BURN has the following restrictions.

(1) Maximum number of energy groups is 70.

(2) Maximum number of regions is 99.

(3) Maximum number of nuclides is 34.

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6. TYPICAL RUNNING TIME

The CPU times for sample problems on Linux with Intel Pentium4, 3.6GHz are as follows:

(1) SAGEP

- 18-group two-dimensional calculation:

- 1 second for multiplication factor and Doppler reactivity

- 2 seconds for reaction rate ratio

- 6 seconds for sodium void reactivity

- 18-group three-dimensional calculation:

- 2 seconds for multiplication factor and Doppler reactivity

- 15 seconds for reaction rate ratio

- 2 minutes for control rod reactivity

(2) PSAGEP/SAGEP-BURN

- 18-group two-dimensional calculation with 4 cycles

- 7 minutes for multiplication factor

- 11 minutes for atomic number density

(3) ABLE

- 6 seconds for the case of 18-group STEP1 calculation with 84 reactor parameters

- 2 seconds for the case of 18-group STEP2 calculation with 2 reactor parameters

(4) ACCEPT

- 4 seconds for the case of 18-group calculation with 84 reactor parameters

The CPU times for sample problems on Linux with Intel Pentium4, 3.6GHz are as follows:

(1) SAGEP

- 18-group two-dimensional calculation:

- 1 second for multiplication factor and Doppler reactivity

- 2 seconds for reaction rate ratio

- 6 seconds for sodium void reactivity

- 18-group three-dimensional calculation:

- 2 seconds for multiplication factor and Doppler reactivity

- 15 seconds for reaction rate ratio

- 2 minutes for control rod reactivity

(2) PSAGEP/SAGEP-BURN

- 18-group two-dimensional calculation with 4 cycles

- 7 minutes for multiplication factor

- 11 minutes for atomic number density

(3) ABLE

- 6 seconds for the case of 18-group STEP1 calculation with 84 reactor parameters

- 2 seconds for the case of 18-group STEP2 calculation with 2 reactor parameters

(4) ACCEPT

- 4 seconds for the case of 18-group calculation with 84 reactor parameters

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10. REFERENCES

Not included in the distribution package:

'SAGEP-BURN'

[3] T. Takeda and T. Umano, "Burnup Sensitivity Analysis in a Fast Breeder Reactor - Part I: Sensitivity Calculation Method with Generalized Perturbation Theory", Nucl. Sci. Eng., Vol. 91 pp.1-10 (1985).

'PSAGEP'

[6] K. Yokoyama, M. Ishikawa, M. Tatsumi and H. Hyoudou, "Restructuring of Burnup Sensitivity Analysis Code System by using an Object-Oriented Design Approach", Proc. Conf. on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications, Avignon, France, September 12--15, 2005 (M&C2005).

'ABLE & ACCEPT'

[9] T. Takeda, A. Yoshimura, T. Kamei and K. Shirakata, "Prediction Uncertainty Evaluation Methods of Core Performance Parameters in Large Liquid-Metal Fast Breeder Reactors," Nucl. Sci. Eng., Vol. 103, pp.157-165 (1989).

[10] M. Ishikawa, K. Sugino, W. Sato and K. Numata, "Development of a Unified Cross-section Set ADJ2000 based on Adjustment Technique for Fast Reactor Analysis", Proc. Int. Conf. on Nuclear Data for Science and Technology Oct. 7-12, 2001, Tsukuba, Ibaraki, Japan (ND2001), J. Nucl. Sci. Tech. , Suppl. Vol.2, p.1077-1080 (Aug. 2002)

Not included in the distribution package:

'SAGEP-BURN'

[3] T. Takeda and T. Umano, "Burnup Sensitivity Analysis in a Fast Breeder Reactor - Part I: Sensitivity Calculation Method with Generalized Perturbation Theory", Nucl. Sci. Eng., Vol. 91 pp.1-10 (1985).

'PSAGEP'

[6] K. Yokoyama, M. Ishikawa, M. Tatsumi and H. Hyoudou, "Restructuring of Burnup Sensitivity Analysis Code System by using an Object-Oriented Design Approach", Proc. Conf. on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications, Avignon, France, September 12--15, 2005 (M&C2005).

'ABLE & ACCEPT'

[9] T. Takeda, A. Yoshimura, T. Kamei and K. Shirakata, "Prediction Uncertainty Evaluation Methods of Core Performance Parameters in Large Liquid-Metal Fast Breeder Reactors," Nucl. Sci. Eng., Vol. 103, pp.157-165 (1989).

[10] M. Ishikawa, K. Sugino, W. Sato and K. Numata, "Development of a Unified Cross-section Set ADJ2000 based on Adjustment Technique for Fast Reactor Analysis", Proc. Int. Conf. on Nuclear Data for Science and Technology Oct. 7-12, 2001, Tsukuba, Ibaraki, Japan (ND2001), J. Nucl. Sci. Tech. , Suppl. Vol.2, p.1077-1080 (Aug. 2002)

NEA-1779/01, included references:

-- Most parts of the documents are available in English in electronic form withlinked html and PDF files

'SAGEP'

[1] A. Hara, T. Takeda and Y. Kikuchi "SAGEP: Two-Dimensional Sensitivity

Analysis Code Based on Generalized Perturbation Theory" JAERI-M 84-027 (Jan.

1984) [in Japanese].

[2] M. Ishikawa, Y. Yamashita, T. Ikegami, T. Hoshi, H. Kusunoki and K.

Shirakata, "A Study on Cross-Section Adjustment for Large LMFBR Cores

(Preparation of Adjusted Cross-Section for Demonstration LMFBR Cores)", PNC

TY9471 92-001(1) Vol.2, A.1 (Mar. 1992) [in Japanese].

'SAGEP-BURN'

[4] H. Hanaki, S. Sawada and T. Sanda, "Preparation of Computer Codes for

Analyzing Sensitivity Coefficients of Burnup Characteristics", JNC TJ9124

93-009 (Mar. 1993) [in Japanese].

[5] H. Hanaki, T. Sanda and M. Ohashi, "Preparation of Computer Codes for

Analyzing Sensitivity Coefficients of Burnup Characteristics (II)", JNC TJ9124

94-007 (Mar. 1994) [in Japanese].

[5a]Hiroshi HANAKI, Toshio SANDA and Masahisa OHASHI, "Preparation of Computer

Codes for Analysing Sensitivity Coefficients of Burnup Characteristics (II)",

JAEA-Review 2008-047 (October 2008) [in English]

'PSAGEP'

[7] M. Tatsumi and H. Hyoudou, "Systemization of Burnup Sensitivity Analysis

Code", JNC TJ9400 2003-012 (Feb. 2004) [in Japanese].

[8] M. Tatsumi and Hyoudou, "Systemization of Burnup Sensitivity Analysis Code

(II)", JNC TJ9400 2004-002 (Feb. 2005) [in Japanese].

[8a]Masahiro TATSUMI and Hideaki HYOUDOU, "Systemization of Burnup Sensitivity

Analysis Code (II), JAEA-Review 2008-038 (August 2008) [in English]

'ABLE & ACCEPT'

[11] M. Ishikawa, Y. Yamashita, T. Ikegami, T. Hoshi, H. Kusunoki and K.

Shirakata, "A Study on Cross-Section Adjustment for Large LMFBR Cores

(Preparation of Adjusted Cross-Section for Demonstration LMFBR Cores)", PNC

TY9471 92-001(1) Vol.2, A.2 (Mar. 1992) [in Japanese]

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Package ID | Computer language |
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NEA-1779/01 | FORTRAN-77, PYTHON |

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

SAGEP-FR is supposed to use input data files processed by the auxiliary programs. SAGEP and PSAGEP/SAGEP-BURN require PDS files processed by SLAROM, JOINT-PNC, CITATION-FBR codes. ABLE and ACCEPT require group-wise nuclear data covariance processed by ERRORJ code.

SAGEP-FR is supposed to use input data files processed by the auxiliary programs. SAGEP and PSAGEP/SAGEP-BURN require PDS files processed by SLAROM, JOINT-PNC, CITATION-FBR codes. ABLE and ACCEPT require group-wise nuclear data covariance processed by ERRORJ code.

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NEA-1779/01

Source programs for SAGEP, SAGEP-BURN, PSAGEP, ABLE, ACCEPTSample problems

Auxiliary codes

User's manuals and documents

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- C. Static Design Studies
- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, cross sections adjustment, diffusion equations, fast reactors, perturbation theory, sensitivity analysis.