Three-dimensional RAMA fluence methodology benchmarking
Creators
- 1. TransWare Enterprises Inc., 5450 Thornwood Dr., San Jose, CA 95123 (United States)
- 2. Electric Power Research Inst., Inc., 1300 West W. T. Harris Blvd., Charlotte, NC 28221 (United States)
Description
This paper describes the benchmarking of the RAMA Fluence Methodology software, that has been performed in accordance with U. S. Nuclear Regulatory Commission Regulatory Guide 1.190. The RAMA Fluence Methodology has been developed by TransWare Enterprises Inc. through funding provided by the Electric Power Research Inst., Inc. (EPRI) and the Boiling Water Reactor Vessel and Internals Project (BWRVIP). The purpose of the software is to provide an accurate method for calculating neutron fluence in BWR pressure vessels and internal components. The Methodology incorporates a three-dimensional deterministic transport solution with flexible arbitrary geometry representation of reactor system components, previously available only with Monte Carlo solution techniques. Benchmarking was performed on measurements obtained from three standard benchmark problems which include the Pool Criticality Assembly (PCA), VENUS-3, and H. B. Robinson Unit 2 benchmarks, and on flux wire measurements obtained from two BWR nuclear plants. The calculated to measured (C/M) ratios range from 0.93 to 1.04 demonstrating the accuracy of the RAMA Fluence Methodology in predicting neutron flux, fluence, and dosimetry activation. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448683-7
- Imprint Pagination
- 16 p.
Conference
- Title
- Global Developments
- Acronym
- PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems
- Dates
- 25-29 Apr 2004
- Place
- Chicago, IL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42096368
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BENCHMARKS; BWR TYPE REACTORS; COMPUTER CODES; DETERMINISTIC ESTIMATION; DOSIMETRY; MATHEMATICAL SOLUTIONS; MONTE CARLO METHOD; NEUTRON FLUENCE; NEUTRON FLUX; ORNL-PCA REACTOR; PRESSURE VESSELS; REGULATORY GUIDES; ROBINSON-2 REACTOR; THREE-DIMENSIONAL CALCULATIONS; TRANSPORT THEORY; VENUS REACTOR
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZERO POWER REACTORS
Optional Information
- Notes
- 7 refs.