An Improved Dancoff Correction Factor for the SCALE Code System
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5619064
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The SCALE code system has become a major tool for criticality safety analyses. Sequences within SCALE are automated to provide resonance self-shielding (via BONAMI and/or NITAWL) prior to calculation of keff by KENO V.a or XSDRNPM. This paper presents a modification to the Dancoff correction factor formalism used by NITAWL. The modified Dancoff factor treatment eliminates a breakdown observed in the past, which had been previously attributed to the limitations of the Nordheim treatment utilized by NITAWL.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5619064
- Report Number(s):
- CONF-880601--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 56
- Country of Publication:
- United States
- Language:
- English
Similar Records
Validation of SCALE-4 for LWR (Light Water Reactor) Fuel in Transportation and Storage Cask Conditions
Validation of the CSAS25 module of SCALE: Part 1, Highly enriched uranium solutions
Validation of the CSAS25 module of SCALE: Part 1, Highly enriched uranium solutions
Conference
·
Sat Nov 10 23:00:00 EST 1990
·
OSTI ID:6896829
Validation of the CSAS25 module of SCALE: Part 1, Highly enriched uranium solutions
Technical Report
·
Mon Jul 01 00:00:00 EDT 1991
·
OSTI ID:10146342
Validation of the CSAS25 module of SCALE: Part 1, Highly enriched uranium solutions
Technical Report
·
Mon Jul 01 00:00:00 EDT 1991
·
OSTI ID:7368443
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
97 MATHEMATICS AND COMPUTING
ALGORITHMS
BONAMI
COMPUTER CODES
CRITICALITY
DANCOFF CORRECTION
Dancoff Correction Factor Formalism
HYDROGEN COMPOUNDS
KENO V.a
MATHEMATICAL LOGIC
MODERATORS
MULTIPLICATION FACTORS
NITAWL
Nuclear Criticality Safety Program (NCSP)
OXYGEN COMPOUNDS
PHYSICS
PROBABILITY
R CODES
REACTOR PHYSICS
S CODES
SAFETY
SCALE
SHIELDING
WATER
X CODES
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
97 MATHEMATICS AND COMPUTING
ALGORITHMS
BONAMI
COMPUTER CODES
CRITICALITY
DANCOFF CORRECTION
Dancoff Correction Factor Formalism
HYDROGEN COMPOUNDS
KENO V.a
MATHEMATICAL LOGIC
MODERATORS
MULTIPLICATION FACTORS
NITAWL
Nuclear Criticality Safety Program (NCSP)
OXYGEN COMPOUNDS
PHYSICS
PROBABILITY
R CODES
REACTOR PHYSICS
S CODES
SAFETY
SCALE
SHIELDING
WATER
X CODES