Methods for calculating group cross sections for doubly heterogeneous thermal reactor systems. [HTGR]
The report discusses methods used at LASL for calculating group cross sections for doubly heterogeneous HTGR systems of the General Atomic design. These cross sections have been used for the neutronic safety analysis calculations of such HTGR systems at various points in reactor lifetime (e.g., beginning-of-life, end-of-equilibrium cycle). They were also compared with supplied General Atomic cross sections generated with General Atomic codes. The overall agreement between the LASL and the GA cross sections has been satisfactory.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7306976
- Report Number(s):
- LA-NUREG-6685-MS; TRN: 77-007851
- Country of Publication:
- United States
- Language:
- English
Similar Records
Technical notes. Rational approximations for cross-section space-shielding in doubly heterogeneous systems. [HTGR]
Cross section space shielding in double heterogeneous HTGR systems
Calculation of cross-section space shielding factors for doubly heterogeneous reactor cores: pointwise or ultrafine group method
Journal Article
·
Wed Dec 01 00:00:00 EST 1976
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:7306976
Cross section space shielding in double heterogeneous HTGR systems
Technical Report
·
Sat Nov 01 00:00:00 EST 1975
·
OSTI ID:7306976
Calculation of cross-section space shielding factors for doubly heterogeneous reactor cores: pointwise or ultrafine group method
Technical Report
·
Sun May 01 00:00:00 EDT 1977
·
OSTI ID:7306976
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR KINETICS
GROUP CONSTANTS
HETEROGENEOUS EFFECTS
MULTIGROUP THEORY
MULTIPLICATION FACTORS
REACTIVITY COEFFICIENTS
THERMAL REACTORS
CROSS SECTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
KINETICS
NEUTRON TRANSPORT THEORY
REACTORS
TRANSPORT THEORY
210300* - Power Reactors
Nonbreeding
Graphite Moderated
HTGR TYPE REACTORS
REACTOR KINETICS
GROUP CONSTANTS
HETEROGENEOUS EFFECTS
MULTIGROUP THEORY
MULTIPLICATION FACTORS
REACTIVITY COEFFICIENTS
THERMAL REACTORS
CROSS SECTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
KINETICS
NEUTRON TRANSPORT THEORY
REACTORS
TRANSPORT THEORY
210300* - Power Reactors
Nonbreeding
Graphite Moderated