Publications

POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System

Polaris is a new 2-dimensional (2-D) lattice physics capability in the SCALE code system for the analysis of light water reactor fuel designs. In this paper, the Polaris calculational methods are summarized and results are provided for a series of computational benchmarks. The summary includes the implementation of...

Guide to Performing Computational Analysis of Criticality Accident Alarm Systems ORNL/TM-2013-211

This document provides guidance on performing computational analyses of Criticality Accident Alarm Systems (CAAS). A brief overview of ANSI/ANS-8.3-1997 (R2012) [1], the standard that the United States Department of Energy uses to guide the placement of CAAS detectors, is provided with a focus on the parts of the...

2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc SILENE Facility

Several experiments were performed at the CEA Valduc SILENE reactor facility, which are intended to be published as evaluated benchmark experiments in the ICSBEP Handbook.  These evaluated benchmarks will be useful for the verification and validation of radiation transport codes and evaluated...

Benchmark Data from Experiments 2 and 3 of the 2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc SILENE Facility

A series of benchmark experiments were conducted at the CEA Valduc SILENE facility to create a new benchmark for the verification and validation of radiation transport codes and evaluated nuclear data used in the analysis of criticality accident alarm systems. The series consisted of three single-pulsed experiments...

Neutron Activation and Thermoluminescent Detector Responses to a Bare Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2015/462)

This is a 2016 revision of the ICSBEP benchmark alarm-tran-air-shield-001. None of the example computational results or technical details of the benchmark model have been changed. However, a few typos in the description of the benchmark model have been corrected. Also, some information and text have been added to...

Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data (NUREG/CR-7045, ORNL/TM 2011/12))

New coupled neutron-gamma cross-section libraries have been developed for use in light water reactor (LWR) shielding applications, including pressure vessel dosimetry calculations. The libraries, which were generated using Evaluated Nuclear Data File/B Version VII Release 0 (ENDF/B-VII.0), use the same fine-group...

Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries

The U.S. Nuclear Regulatory Commission's Regulatory Guide 1.190 states that calculational methods used to estimate reactor pressure vessel (RPV) fluence should use the latest version of the evaluated nuclear data file (ENDF). The VITAMIN-B6 fine-group library and BUGLE-96 broad-group library, which are widely used...

Monte Carlo Shielding Analysis Capabilities with MAVRIC

Journal: Nuclear Technology

Monte Carlo shielding analysis capabilities in SCALE 6 are centered on the Consistent Adjoint Driven Importance Sampling (CADIS) methodology .  CADIS is used to create an importance map for space/energy weight windows as well as a biased source distribution.  New to SCALE 6 are the Monaco functional module, a multi...

Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6 (NUREG/CR-6990, ORNL/TM-2008/047)

New coupled neutron-gamma shielding libraries have been developed for use with the SCALE (Standardized Computer Analyses for Licensing Evaluation) code system. Two libraries have been generated based on the Evaluated Nuclear Data File/B Version VI (ENDF/B-VI) Release 8 (ENDF/B-VI.8) and ENDF/B-VII Release 0 (ENDF/B...

Evaluation of the Concrete Shield Compositions from the 2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc SILENE Facility

In October 2010, a series of benchmark experiments were conducted at the French Commissariat à l’Énergie Atomique et aux Énergies Alternatives (CEA) Valduc SILENE facility. These experiments were a joint effort between the United States Department of Energy Nuclear Criticality Safety Program and the CEA. The...

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SCALE Nuclear Systems Modeling and Simulation