Monitor Scientific

Monitor Scientific develops software specific to clients’ needs.
A short list of Monitor Scientific developed codes is given in this page.
Please click on the links for more details

• COMPASS: Near-field and source-term
..compartment model and PA code for the
..unsaturated repository at Yucca Mountain

• SATRAP: Laplace transform code solving
..transport of radionuclides in multiple geological
..media that are either fractured or non-fractured.

• SAGE: probabilistic framework of safety
..assessment for near-surface waste disposal
..facilities
.......• SAGENF: source term, near-field and
.........unsaturated-zone transport
.......• SAGEFF: far-field (saturated-zone) transport
.......• SAGE-BIO: biosphere
.......• QUARK: QA database
.......• SAGE-GUI: framework executor and
.........graphic user interface

• MOSAIC: probabilistic framework of safety
..assessment for low and intermediate waste
..disposal facilities with a concrete degradation
..model, database and graphic user interface.
.......• 4sight: concrete degradation model/code
........ adapted for the framework
.......• MNF: source term, near-field and
........ unsaturated-zone transport
.......• MFF: far-field (saturated-zone) transport

• MSA06: source term, near- and far-field
..transport for rock cavern I/LLW disposal facility

• INPAG: a framework of performance assessment
..for spent nuclear fuel geological.disposal with the
..KBS-3 type concept with GUI and database
.......• INPAGN: source term and near-field transport
.......• INPAGNV: source-term and
........ two-dimensional near-field transport
.......• INPAGNH: source-term and transport
........ for KBS-3H type repository
.......• INPAGF: far-field transport
.......• INPAGFL: Laplacian transform solution
.........to radionuclide transport in fractured rock

• QUASAR: QA and information management tool

• QUASAR-Tono: QA and information management
..tool for Tono Natural Analogue Project

COMPASS (COmpartment Model for Performance ASsessment of
near-field and Source term) was developed for EPRI’s Total System
Performance Assessment of Yucca Mountain (IMARC). The code uses
a compartment model approach to simulate radionuclide mobilization
after canister failure and subsequent release and transport from the waste
canister through the EBS and eventually to the near-field rock. The output
of the code feeds the far-field transport code of IMARC. COMPASS was
first developed in 1995. Over the years, COMPASS has been updated
and modified in response to changes and development in design, new
information and data, taking the advantage of the flexibility offered by
the compartment model approach. The FEPs considered in the
model include:
.......• Instant and rate-controlled dissolution of radionuclides
........ from spent fuel
.......• Dissolution of radionuclides from HLW glass
.......• Radioactive decay and ingrowth
.......• Shared elemental solubility limit
.......• Sorption
.......• Diffusion and/or advection transport in degraded waste packages,
........ EBS, and near-field rock matrix and fracture

MOSAIC stands for “MOdular Safety Assessment code with Integrated
Concrete analysis”. This is a suite of assessment codes with a parameter
database developed for the Korean concept of L/ILW disposal safety
assessment carried out by Korean Hydro and Nuclear Power (KHNP).

SAGE-GUI is the graphic user interface for SAGE framework. The GUI
provides interfaces for preparing input files for SAGENF, SAGEFF, and
SAGEBIO either from scratch or from an existing disk file. In the former
case, the GUI interfaces with QUARK to provide default data values.
Functions provided by the GUI include:
.......• Prepare a single input file for each of the SAGE suite codes for
........ a deterministic calculation (single run)
.......• Provide Latin Hypocube Sampling (LHS) for sampling uncertain
........ parameters
.......• Prepare multiple input files for each of the SAGE suite of codes
........ for probabilistic calculations using the sampling results
.......• Launch either single or multiple (probabilistic) runs of the SAGE
........ suite of codes
.......• Plot results (release rates as function of time and statistical
........ results)

QUARK (QUality Assurance program for Radioactive waste disposal in
Korea) is a database containing all the parameters necessary for running
the SAGE suite of codes. The database manages and updates the
parameters according to QA rules that enhance the traceability and
transparency of the performance assessment. Using a relational
database, QUARK maintains intrinsic relationships between parameters,
thereby maintaining the integrity of the data. For each parameter, the
coefficients for probabilistic density functions (PDF), source of the data,
date of publication, etc are part of the information record stored in the database. The database includes the following parameter types:
.......• Nuclide specific data
.......• Element specific data
.......• Material specific data
.......• Physical parameters
.......• Transport parameters
.......• Geometry/ design
.......• Biosphere

SAGE-BIO is the SAGE program the implements the biosphere model
and calculates pathway dose conversion factors (PDCF) for each
radionuclide. Using these factors, the code converts the far-field release
rates into dose rates.

SAGEFF is the SAGE code for saturated zone performance assessment
of waste disposal facilities. The code takes the input release rates
calculated by SAGENF or any other source-term model and calculates
release rates to the biosphere. The FEPs considered in the model include:
......• Fractured rocks or porous soils
......• Matrix diffusion for fractured rock
......• Sorption
......• Radioactive decay and ingrowth
......• Radionuclides with multiple parents in different chains
......• Longitudinal and transverse dispersion
......• Diffusion and advection

SAGENF is the SAGE code for near-field performance assessment of
waste disposal facilities. The FEPs considered in the model include:
.......• Mobilization of radionuclides from simple leaching (rate-controlled)
........ and surface resin (instant dissolution) waste forms
.......• Time-dependent infiltration rates
.......• Transport multiple unsaturated layers including EBS
.......• Flow shadow effect in unsaturated layers
.......• Radioactive decay and ingrowth
.......• Radionuclides with multiple parents in different chains
.......• Shared elemental solubility limit
.......• Sorption
.......• Diffusion and/or advection/dispersion transport

SAGE (Safety Assessment of Groundwater Evaluation) is a framework that
contains a suite of codes developed for Korean Hydro and Nuclear Power (KHNP) and the Korean Atomic Energy Research Institute (KAERI) for
assessing the performance of a near-surface facility for LLW disposal.
SAGE includes SAGENF, SAGEFF, SAGEBIO, QUARK, and SAGE-GUI.

SATRAP (SAturated zone TRAnsPort) was developed as an alternative
saturated-zone transport code for EPRI’s IMARC. The code uses
numerical inversion of Laplace transforms to solve the transport
equation for radionuclides through one or more geological materials,
which can be fractured rock or non-fractured porous media. SATRAP
uses a discrete fracture model with matrix diffusion. Sorption on both
the fracture surface and inside the matrix is considered, for cases in
which the sorption depth is less than or equal to the fracture spacing.
Flow, diffusion, and longitudinal dispersion along the fracture are also
considered. SATRAP takes time-dependent fluxes of radionuclides as
input and produces time-dependent fluxes of radionuclides at the end
of the saturated zone.

The MOSAIC framework includes the following assessment codes/modules:

4sight was developed by US National Institute of Standards and
Technology (NIST http://ciks.cbt.nist.gov/4sight/) and has been modified
to be integrated into the MOSAIC framework. 4sight evaluates the behavior
of a buried concrete vault, including structural and flow behavior, by solving
the coupled processes of flow, solute transport, and chemical reactions.

MNF is the MOSAIC near-field performance assessment code that covers
the facility and the vadose zone below the facility. The FEPs considered
in the model include:
.......• Mobilization of radionuclides from simple leaching (rate-controlled),
........ surface resin (instant dissolution), and diffusion-controlled-release
........ waste forms
.......• Time-dependent infiltration rates calculated by 4sight
.......• Transport in multiple unsaturated layers
.......• Flow shadow effect in unsaturated layers
.......• Radioactive decay and ingrowth
.......• Radionuclides with multiple parents in different chains
.......• Shared elemental solubility limit
.......• Sorption
.......• Diffusion and/or advection/dispersion transport

MFF is the MOSAIC far-field performance assessment code that
simulates transport in the saturated zone. The code takes the input
release rates calculated by MNF and calculates release rates to the
biosphere. The FEPs considered in the model include:
.......• Fractured rocks or porous soils
.......• Matrix diffusion for fractured rock
.......• Sorption on fracture and matrix
.......• Radioactive decay and ingrowth
.......• Radionuclides with multiple parents in different chains
.......• Longitudinal and transverse dispersion
.......• Diffusion and advection

MSA06 was developed especially to support the safety assessment of
Korea’s L/ILW final disposal site at Gyeongju, South Korea. The code
covers radionuclide mobilization and release from waste forms, EBS, near
field, and far field. The FEPs considered in the model include:
.......• Mobilization of radionuclides from simple leaching (rate-controlled),
........ surface resin (instant dissolution), diffusion-controlled-release, and
........ HIC waste forms
.......• Time-dependent infiltration rates calculated by 4sight
.......• Transport in the near field with multiple barriers and far field
.......• Radioactive decay and ingrowth
.......• Radionuclides with multiple parents in different chains
.......• Shared elemental solubility limit
.......• Sorption
.......• Diffusion and/or advection transport
.......• Longitudinal and transverse dispersion

INPAG (Institute of Nuclear energy research Performance Assessment
for spent fuel Geological disposal) is a suite of assessment codes
developed for Institute of Nuclear Energy Research (INER), Republic
of China, for their spent nuclear fuel disposal program. The package
contains the following assessment codes: INPAGN, INPAGNV,
INPAGNH, INPAGF, INPAGFL

INPAGN is the INPAG code for assessing the performance of a
KBS-3 (vertical) type disposal concept in a hypothetical repository in
a granite formation. The model treats the waste package, EBS, and near
field as a series of cylindrical compartments. The FEPs considered in the
model include:
.......• Instant and rate-controlled dissolution of radionuclides from
.........spent fuel
.......• Radioactive decay and ingrowth
.......• Shared elemental solubility limit
.......• Sorption
.......• Diffusion transport in degraded waste packages and
.........bentonite buffer
.......• Diffusion and advection transport in excavated damage zone

INPAGNV is a two-dimensional version of INPAGN, which includes
vertical transport of radionuclides to the disposal tunnel.

INPAGNH is the INPAG code for assessing the performance of a
horizontal repository concept. This repository is conceptually similar
to KBS-3 (horizontal). The model uses a composite compartment
approach in order to effectively simulate mass transfer between waste
packages and bentonite buffers.

INPAGF is the INPAG far-field performance assessment code that
simulates transport in fractured rock. The code takes the time-dependent
release rates of radionuclides as input and calculates release rates to
the biosphere. The FEPs considered in the model include:
.......• Fractured rocks or porous soils
.......• Matrix diffusion for fractured rock
.......• Sorption
.......• Radioactive decay and ingrowth
.......• Longitudinal dispersion
.......• Diffusion and advection

INPAGFL solves the same model as INPAGF but uses numerical
inversion of Laplace transforms to solve the equations. This solution
approach has the advantage of providing fast and accurate calculations
suitable for probabilistic assessments.

QUASAR stands for QUality Assurance program for Scenario Analysis
of Repository safety, developed for JNC (now JAEA). QUASAR provides
a formal QA and information management system that is based on a
scenario approach to demonstrating safety. QUASAR organizes the
scenario analysis into a transparent, traceable, integrated, consistent,
and efficient system, all of which are vital both to aid decision-making
by government officials and scientific R&D managers, and to enhance
communications of repository safety to concerned stakeholders.
QUASAR is built as a framework that contains and processes
information. As an information management tool, QUASAR organizes
seemingly unrelated information into an integrated system in which
the information is connected according to intrinsic relationships found
in scenario analysis modeling and calculation. These relationships are
the foundation for reaching reasonable assurance. As an information
processor, QUASAR has built-in procedures that are subjectively
imposed to meet the prescribed QA standards.

QUASAR-Tono is a database and information management tool
derived from QUASAR for the JNC (now JAEA) Tono Natural Analogue
Project. The tool also helps document scenario analysis activities
according to prescribed QA procedures.