Assessment of the 2D/1D implementation in MPACT
- 1. Dept. of Nuclear Engineering and Radiological Science, Univ. of Michigan, Ann Arbor, MI (United States)
- 2. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
Description
The 2D/1D method is used in the MPACT code to obtain 3D solutions of the Boltzmann transport equation for practical reactor geometries. The OECD C5G7 transport benchmark problem is used first to assess the accuracy of the method with a fixed set of cross-sections. The VERA Core Physics Progression Problems are then used to compare the accuracy of the transport solver using a 56-group library based on ENDFB-VII.0. Single assembly PWR designs are simulated, and the eigenvalue and pin powers are compared to continuous-energy Monte Carlo results. A 3x3 assembly cluster with a control rod inserted into the center assembly is then compared to Monte Carlo to assess the ability of MPACT to predict a control rod worth curve. Finally, MPACT is used to simulate the initial critical states of a full 3D initial core of a PWR at zero power conditions. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 13 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042866
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOLTZMANN EQUATION; COMPUTER CODES; CONTROL ROD WORTHS; CROSS SECTIONS; EIGENVALUES; FUEL PINS; ONE-DIMENSIONAL CALCULATIONS; PWR TYPE REACTORS; REACTOR CORES; TECHNOLOGY ASSESSMENT; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; ZERO POWER REACTORS
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; INTEGRO-DIFFERENTIAL EQUATIONS; KINETIC EQUATIONS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1126966.pdf; 10 refs., 8 figs., 6 tabs.