A Monte-Carlo method for ex-core neutron response
Conference
·
OSTI ID:325752
- Lockheed Martin Corp., Schenectady, NY (United States)
A Monte Carlo neutron transport kernel capability primarily for ex-core neutron response is described. The capability consists of the generation of a set of response kernels, which represent the neutron transport from the core to a specific ex-core volume. This is accomplished by tagging individual neutron histories from their initial source sites and tracking them throughout the problem geometry, tallying those that interact in the geometric regions of interest. These transport kernels can subsequently be combined with any number of core power distributions to determine detector response for a variety of reactor Thus, the transport kernels are analogous to an integrated adjoint response. Examples of pressure vessel response and ex-core neutron detector response are provided to illustrate the method.
- Research Organization:
- Knolls Atomic Power Lab., Schenectady, NY (United States)
- Sponsoring Organization:
- USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
- DOE Contract Number:
- AC12-76SN00052
- OSTI ID:
- 325752
- Report Number(s):
- KAPL-P--000179; K--97069; CONF-971005--; ON: DE99001953
- Country of Publication:
- United States
- Language:
- English
Similar Records
Estimation of ex-core detector responses by adjoint Monte Carlo
A Monte Carlo Green's function method for three-dimensional neutron transport
Modeling the Ex-core Detector Response into a Production Option in MPACT
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:22039553
A Monte Carlo Green's function method for three-dimensional neutron transport
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7057459
Modeling the Ex-core Detector Response into a Production Option in MPACT
Technical Report
·
Fri May 31 00:00:00 EDT 2019
·
OSTI ID:3002117