PDF Code Manual - Revision history

Abrunett at 20:14, May 17, 2023

2023-05-17T20:14:45Z

← Older revision		Revision as of 20:14, May 17, 2023
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	:T. H. Fanning, A. J. Brunett, and T. Sumner, eds., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-16/19, Nuclear Engineering Division, Argonne National Laboratory, March 31, 2017.		:T. H. Fanning, A. J. Brunett, and T. Sumner, eds., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-16/19, Nuclear Engineering Division, Argonne National Laboratory, March 31, 2017.

	Links to the ~~latest~~ version of the manual are provided in the sections below. For the previous version of the manual, please visit [[Code Manual, Version 3.0 \| this page]].		Links to the 2017 version of the manual are provided in the sections below. For the previous version of the manual, please visit [[Code Manual, Version 3.0 \| this page]].

	== Introduction ==		== Introduction ==

Dogrady: Dogrady moved page Code Manual to PDF Code Manual

2023-05-17T15:33:35Z

Dogrady moved page Code Manual to PDF Code Manual

← Older revision	Revision as of 15:33, May 17, 2023
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Abrunett at 18:37, April 20, 2017

2017-04-20T18:37:53Z

← Older revision		Revision as of 18:37, April 20, 2017
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	:T. H. Fanning, A. J. Brunett, and T. Sumner, eds., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-16/19, Nuclear Engineering Division, Argonne National Laboratory, March 31, 2017.		:T. H. Fanning, A. J. Brunett, and T. Sumner, eds., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-16/19, Nuclear Engineering Division, Argonne National Laboratory, March 31, 2017.

	Links to the latest version of the manual are provided in the sections below. For previous ~~versions~~ of the manual, please visit [[Code Manual, Version 3.0 \| this page]].		Links to the latest version of the manual are provided in the sections below. For the previous version of the manual, please visit [[Code Manual, Version 3.0 \| this page]].

	== Introduction ==		== Introduction ==

Abrunett at 18:34, April 20, 2017

2017-04-20T18:34:39Z

← Older revision		Revision as of 18:34, April 20, 2017
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	The manual for SAS4A/SASSYS-1 describes code capabilities, user input, and major code modules. It is divided into 16 chapters as described below. The general citation for the SAS4A/SASSYS-1 manual is		The manual for SAS4A/SASSYS-1, Version 5.0 describes code capabilities, user input, and major code modules. It is divided into 16 chapters as described below. The general citation for the SAS4A/SASSYS-1, Version 5.0 manual is

	:T. H. Fanning, A. J. Brunett, and T. Sumner, eds., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-16/19, Nuclear Engineering Division, Argonne National Laboratory, March 31, 2017.		:T. H. Fanning, A. J. Brunett, and T. Sumner, eds., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-16/19, Nuclear Engineering Division, Argonne National Laboratory, March 31, 2017.

			Links to the latest version of the manual are provided in the sections below. For previous versions of the manual, please visit [[Code Manual, Version 3.0 \| this page]].

	== Introduction ==		== Introduction ==

Abrunett at 18:04, April 20, 2017

2017-04-20T18:04:38Z

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Abrunett at 17:33, April 20, 2017

2017-04-20T17:33:50Z

← Older revision		Revision as of 17:33, April 20, 2017
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	The manual for SAS4A/SASSYS-1 describes code capabilities, user input, and major code modules. It is divided into 16 chapters as described below. The general citation for the SAS4A/SASSYS-1 manual is		The manual for SAS4A/SASSYS-1 describes code capabilities, user input, and major code modules. It is divided into 16 chapters as described below. The general citation for the SAS4A/SASSYS-1 manual is

	:T. H. Fanning, ed., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-12/4, Nuclear Engineering Division, Argonne National Laboratory, ~~January~~ 31, ~~2012~~.		:T. H. Fanning, A. J. Brunett, and T. Sumner, eds., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-16/19, Nuclear Engineering Division, Argonne National Laboratory, March 31, 2017.

	== Introduction ==		== Introduction ==
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	SAS4A/SASSYS-1 provide a detailed, multiple-channel thermal/hydraulic treatment of the reactor core. Each channel represents a fuel pin, its cladding, the associated coolant, and a fraction of the subassembly duct wall. Other positioning hardware, such as wire wraps or grid spacers, is usually lumped into the structure field with the duct wall. Within a channel, the flow is assumed to be one-dimensional in the axial direction, and the temperature field in the fuel, cladding, coolant, and structure is assumed to be two-dimensional in the radial and axial directions. Usually, a channel represents an average fuel element in a subassembly or a group of subassemblies. A channel may also represent pins in blanket or control subassemblies. Alternately, a single channel may also be used to represent the hottest pin in an assembly, or any other subset of a subassembly. The axial extent of a channel covers the entire length of a subassembly, including the core, the axial blankets, the fission gas plenum and the spaces above and below the pin/cladding geometry. Different channels may be used to account for radial and azimuthal design geometry, power, coolant flow, and burnup variations within the reactor core. From ten to thirty channels normally provide sufficient discretization, depending on the core design. Significantly more channels can be used if necessary.		SAS4A/SASSYS-1 provide a detailed, multiple-channel thermal/hydraulic treatment of the reactor core. Each channel represents a fuel pin, its cladding, the associated coolant, and a fraction of the subassembly duct wall. Other positioning hardware, such as wire wraps or grid spacers, is usually lumped into the structure field with the duct wall. Within a channel, the flow is assumed to be one-dimensional in the axial direction, and the temperature field in the fuel, cladding, coolant, and structure is assumed to be two-dimensional in the radial and axial directions. Usually, a channel represents an average fuel element in a subassembly or a group of subassemblies. A channel may also represent pins in blanket or control subassemblies. Alternately, a single channel may also be used to represent the hottest pin in an assembly, or any other subset of a subassembly. The axial extent of a channel covers the entire length of a subassembly, including the core, the axial blankets, the fission gas plenum and the spaces above and below the pin/cladding geometry. Different channels may be used to account for radial and azimuthal design geometry, power, coolant flow, and burnup variations within the reactor core. From ten to thirty channels normally provide sufficient discretization, depending on the core design. Significantly more channels can be used if necessary.

	([[Media:SAS_Ch01_-_Introduction_(ANL-NE-12-4).pdf\|PDF]])		([[Media:SAS_Ch01_-_Introduction_(ANL-NE-16-19).pdf\|PDF]])

	== User's Guide ==		== User's Guide ==
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	Chapter 2 contains a user's guide for SAS4A/SASSYS-1 applications, including a complete description of the standard input file.		Chapter 2 contains a user's guide for SAS4A/SASSYS-1 applications, including a complete description of the standard input file.

	([[Media:SAS_Ch02_-_User_Guide_(ANL-NE-12-4).pdf\|PDF]])		([[Media:SAS_Ch02_-_User_Guide_(ANL-NE-16-19).pdf\|PDF]])

	== Steady-State and Transient Thermal Hydraulics in Core Assemblies ==		== Steady-State and Transient Thermal Hydraulics in Core Assemblies ==

Fanning at 13:40, March 18, 2013

2013-03-18T13:40:04Z

← Older revision		Revision as of 13:40, March 18, 2013
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	The manual for SAS4A/SASSYS-1 ~~version 3.1.2~~ describes code capabilities, user input, and major code modules. It is divided into 16 chapters as described below. The general citation for the SAS4A/SASSYS-1 manual is		The manual for SAS4A/SASSYS-1 describes code capabilities, user input, and major code modules. It is divided into 16 chapters as described below. The general citation for the SAS4A/SASSYS-1 manual is

	:T. H. Fanning, ed., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-12/4, Nuclear Engineering Division, Argonne National Laboratory, January 31, 2012.		:T. H. Fanning, ed., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-12/4, Nuclear Engineering Division, Argonne National Laboratory, January 31, 2012.

Fanning at 13:23, May 29, 2012

2012-05-29T13:23:08Z

← Older revision		Revision as of 13:23, May 29, 2012
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	The manual for SAS4A/SASSYS-1 describes code capabilities, user input, and major code modules. It is divided into 16 chapters.		The manual for SAS4A/SASSYS-1 version 3.1.2 describes code capabilities, user input, and major code modules. It is divided into 16 chapters as described below. The general citation for the SAS4A/SASSYS-1 manual is

			:T. H. Fanning, ed., ''The SAS4A/SASSYS-1 Safety Analysis Code System'', ANL/NE-12/4, Nuclear Engineering Division, Argonne National Laboratory, January 31, 2012.

	== Introduction ==		== Introduction ==

Fanning: Update with links to larger chapter files.

2012-05-29T13:12:54Z

Update with links to larger chapter files.

← Older revision		Revision as of 13:12, May 29, 2012
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	Chapter 3 contains the description of the formulation for the SAS4A/SASSYS-1 pin heat transfer and single-phase coolant thermal/hydraulics model. A major new addition to this model is the capability to treat channel‐to-channel heat transfer due to conduction and convection at all axial locations between the channel inlet and outlet, permitting a consistent multiple-pin subassembly treatment. Also, the subassembly-to-subassembly heat transfer model has been improved, and axial conduction in the coolant has been added. These modeling additions have been proven in validation analyses of EBR-II Shutdown Heat Removal Tests, and are required for accurate predictions of intra-subassembly flow and temperature variations in EBR-II during transients from normal to shutdown operating conditions.		Chapter 3 contains the description of the formulation for the SAS4A/SASSYS-1 pin heat transfer and single-phase coolant thermal/hydraulics model. A major new addition to this model is the capability to treat channel‐to-channel heat transfer due to conduction and convection at all axial locations between the channel inlet and outlet, permitting a consistent multiple-pin subassembly treatment. Also, the subassembly-to-subassembly heat transfer model has been improved, and axial conduction in the coolant has been added. These modeling additions have been proven in validation analyses of EBR-II Shutdown Heat Removal Tests, and are required for accurate predictions of intra-subassembly flow and temperature variations in EBR-II during transients from normal to shutdown operating conditions.

			([[Media:SAS_Ch03_-_Core_Channel_Thermal_Hydraulics_(ANL-NE-12-4).pdf\|PDF]])

	== Reactor Point Kinetics, Decay Heat, and Reactivity Feedback ==		== Reactor Point Kinetics, Decay Heat, and Reactivity Feedback ==
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	Chapter 5 presents a full description of the formulation for the PRIMAR-4 sodium loops thermal/hydraulic model. This model provides boundary coolant pressure and flow conditions for the core channel models, including transient heat losses through normal and emergency heat removal systems and the transient performance of pumps. The major new addition to PRIMAR-4 is the option for multiple core inlet and outlet coolant plena, permitting exact representation of the actual EBR-II coolant systems geometry.		Chapter 5 presents a full description of the formulation for the PRIMAR-4 sodium loops thermal/hydraulic model. This model provides boundary coolant pressure and flow conditions for the core channel models, including transient heat losses through normal and emergency heat removal systems and the transient performance of pumps. The major new addition to PRIMAR-4 is the option for multiple core inlet and outlet coolant plena, permitting exact representation of the actual EBR-II coolant systems geometry.

			([[Media:SAS_Ch05_-_PRIMAR-4_(ANL-NE-12-4).pdf \|PDF]])

	== Control System ==		== Control System ==
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	== Balance of Plant Thermal/Hydraulics Models ==		== Balance of Plant Thermal/Hydraulics Models ==

	The balance-of-plant (BOP) model described in Chapter 7 is new for SAS4A/SASSYS-1. It was implemented to permit 1) improved simulation of EBR-II design basis transients, 2) whole-plant analysis of IFR designs for optimization of advanced reactor control system strategies, and 3) core temperature margin assessments in unprotected accident sequences (i.e. beyond design basis accidents (BDBA) and anticipated transients without scram (ATWS)). In these latter sequences, core response depends strongly upon the performance of the balance-of‐plant, because the core neutronic and thermal/hydraulic behavior is determined by the availability of heat sinks outside the core. The BOP model couples to PRIMAR-4 at the steam generator.		The balance-of-plant (BOP) model described in Chapter 7 is new for SAS4A/SASSYS-1. It was implemented to permit 1) improved simulation of EBR-II design basis transients, 2) whole-plant analysis of IFR designs for optimization of advanced reactor control system strategies, and 3) core temperature margin assessments in unprotected accident sequences (i.e. beyond design basis accidents (BDBA) and anticipated transients without scram (ATWS)). In these latter sequences, core response depends strongly upon the performance of the balance-of‐plant, because the core neutronic and thermal/hydraulic behavior is determined by the availability of heat sinks outside the core. The BOP model couples to PRIMAR-4 at the steam generator.

			([[Media:SAS_Ch07_-_Balance_of_Plant_(ANL-NE-12-4).pdf\|PDF]])

	== DEFORM-4: Steady-State and Transient Pre-Failure Pin Behavior ==		== DEFORM-4: Steady-State and Transient Pre-Failure Pin Behavior ==

	Chapter 8 provides a description of the DEFORM-4 fuel element behavior model for stainless steel‐clad oxide fuel, which is unchanged from prior versions of SAS4A/SASSYS-1.		Chapter 8 provides a description of the DEFORM-4 fuel element behavior model for stainless steel‐clad oxide fuel, which is unchanged from prior versions of SAS4A/SASSYS-1.

			([[Media:SAS_Ch08_-_DEFORM4_Pre-Failure_Pin_Modeling.pdf \|PDF]])

	== DEFORM-5: Metallic Fuel Cladding Transient Behavior Model ==		== DEFORM-5: Metallic Fuel Cladding Transient Behavior Model ==
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	The SSCOMP model described in Chapter 10 has been revised to reflect newly available metal fuel material properties evaluations recorded in the IFR Material Properties Handbook. An efficient correlation technique has been implemented in all SAS4A/SASSYS-1 material properties routines that accurately generates the data from the IFR Handbook for use in all the modules of the code. It is planned to revise the material migration capability in SSCOMP for ternary fuel, to add models for fission gas generation and release, swelling, and all other phenomena needed to describe the transition from cold, clean, unirradiated conditions to hot irradiated conditions.		The SSCOMP model described in Chapter 10 has been revised to reflect newly available metal fuel material properties evaluations recorded in the IFR Material Properties Handbook. An efficient correlation technique has been implemented in all SAS4A/SASSYS-1 material properties routines that accurately generates the data from the IFR Handbook for use in all the modules of the code. It is planned to revise the material migration capability in SSCOMP for ternary fuel, to add models for fission gas generation and release, swelling, and all other phenomena needed to describe the transition from cold, clean, unirradiated conditions to hot irradiated conditions.

			([[Media:SAS_Ch10_-_SSCOMP_Pre-Transient_Metallic_Fuel_(ANL-NE-12-4).pdf\|PDF]])

	== FPIN2: Pre-Failure Metal Fuel Pin Behavior Model ==		== FPIN2: Pre-Failure Metal Fuel Pin Behavior Model ==
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	== Sodium Voiding Model ==		== Sodium Voiding Model ==

	The TSBOIL module for liquid metal coolant boiling and two-phase thermal/hydraulics calculations has been retained intact from previous versions of SAS4A/SASSYS-1, with the addition of a set of modifications to describe the sudden release of noncondensible fission gas from a cladding rupture in the upper fission gas plenum of metal fuel elements and the subsequent plenum blow-down and liquid coolant expulsion. This option has been used to assess the safety implications of long-term fuel element irradiations in EBR-II.		The TSBOIL module for liquid metal coolant boiling and two-phase thermal/hydraulics calculations has been retained intact from previous versions of SAS4A/SASSYS-1, with the addition of a set of modifications to describe the sudden release of noncondensible fission gas from a cladding rupture in the upper fission gas plenum of metal fuel elements and the subsequent plenum blow-down and liquid coolant expulsion. This option has been used to assess the safety implications of long-term fuel element irradiations in EBR-II.

			([[Media:SAS_Ch12_-_Sodium_Voiding_(ANL-NE-12-4).pdf\|PDF]])

	== Cladding Motion Model — CLAP ==		== Cladding Motion Model — CLAP ==
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	The PLUTO2 model described in Chapter 14 is relevant only to oxide fuel, and have remained unchanged since the previous documentation.		The PLUTO2 model described in Chapter 14 is relevant only to oxide fuel, and have remained unchanged since the previous documentation.

			([[Media:SAS_Ch14_-_PLUTO2_Non-Voided_Fuel_Motion_(ANL-NE-12-4).pdf\|PDF]])

	== PINACLE: In-Pin Pre-Failure Molten Fuel Relocation Module ==		== PINACLE: In-Pin Pre-Failure Molten Fuel Relocation Module ==
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	== LEVITATE: Voided Channel Fuel Motion Analysis ==		== LEVITATE: Voided Channel Fuel Motion Analysis ==

	See [[#PINACLE: In-Pin Pre-Failure Molten Fuel Relocation Module]]		See the [[#PINACLE: In-Pin Pre-Failure Molten Fuel Relocation Module\|PINACLE]] chapter description.

			([[Media:SAS_Ch16_-_LEVITATE_Voided_Fuel_Motion_(ANL-NE-12-4).pdf\|PDF]])

Fanning at 13:56, May 3, 2012

2012-05-03T13:56:31Z

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