# The MC21 Monte Carlo Transport Code

## Abstract

MC21 is a new Monte Carlo neutron and photon transport code currently under joint development at the Knolls Atomic Power Laboratory and the Bettis Atomic Power Laboratory. MC21 is the Monte Carlo transport kernel of the broader Common Monte Carlo Design Tool (CMCDT), which is also currently under development. The vision for CMCDT is to provide an automated, computer-aided modeling and post-processing environment integrated with a Monte Carlo solver that is optimized for reactor analysis. CMCDT represents a strategy to push the Monte Carlo method beyond its traditional role as a benchmarking tool or ''tool of last resort'' and into a dominant design role. This paper describes various aspects of the code, including the neutron physics and nuclear data treatments, the geometry representation, and the tally and depletion capabilities.

- Authors:

- Publication Date:

- Research Org.:
- Knolls Atomic Power Laboratory (KAPL), Niskayuna, NY

- Sponsoring Org.:
- USDOE

- OSTI Identifier:
- 903083

- Report Number(s):
- LM-06K144

TRN: US0703198

- DOE Contract Number:
- DE-AC12-00SN39357

- Resource Type:
- Conference

- Resource Relation:
- Conference: Joint International Topical Meeting on Mathematics and Computation and Supercomputing in Nuclear Applications, Monterey, CA, April 15 -19, 2007

- Country of Publication:
- United States

- Language:
- English

- Subject:
- 42 ENGINEERING; BETTIS; DESIGN; GEOMETRY; KAPL; KERNELS; MONTE CARLO METHOD; NEUTRONS; PHOTON TRANSPORT; PHYSICS; SIMULATION; TRANSPORT; VISION

### Citation Formats

```
Sutton TM, Donovan TJ, Trumbull TH, Dobreff PS, Caro E, Griesheimer DP, Tyburski LJ, Carpenter DC, Joo H.
```*The MC21 Monte Carlo Transport Code*. United States: N. p., 2007.
Web.

```
Sutton TM, Donovan TJ, Trumbull TH, Dobreff PS, Caro E, Griesheimer DP, Tyburski LJ, Carpenter DC, Joo H.
```*The MC21 Monte Carlo Transport Code*. United States.

```
Sutton TM, Donovan TJ, Trumbull TH, Dobreff PS, Caro E, Griesheimer DP, Tyburski LJ, Carpenter DC, Joo H. Tue .
"The MC21 Monte Carlo Transport Code". United States. https://www.osti.gov/servlets/purl/903083.
```

```
@article{osti_903083,
```

title = {The MC21 Monte Carlo Transport Code},

author = {Sutton TM, Donovan TJ, Trumbull TH, Dobreff PS, Caro E, Griesheimer DP, Tyburski LJ, Carpenter DC, Joo H},

abstractNote = {MC21 is a new Monte Carlo neutron and photon transport code currently under joint development at the Knolls Atomic Power Laboratory and the Bettis Atomic Power Laboratory. MC21 is the Monte Carlo transport kernel of the broader Common Monte Carlo Design Tool (CMCDT), which is also currently under development. The vision for CMCDT is to provide an automated, computer-aided modeling and post-processing environment integrated with a Monte Carlo solver that is optimized for reactor analysis. CMCDT represents a strategy to push the Monte Carlo method beyond its traditional role as a benchmarking tool or ''tool of last resort'' and into a dominant design role. This paper describes various aspects of the code, including the neutron physics and nuclear data treatments, the geometry representation, and the tally and depletion capabilities.},

doi = {},

journal = {},

number = ,

volume = ,

place = {United States},

year = {2007},

month = {1}

}