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Title: Photoneutron effects on pulse reactor kinetics for the Annular Core Research Reactor (ACRR).

Abstract

The Annular Core Research Reactor (ACRR) is a swimming-pool type pulsed reactor that maintains an epithermal neutron flux and a nine-inch diameter central dry cavity. One of its uses is neutron and gamma-ray irradiation damage studies on electronic components under transient reactor power conditions. In analyzing the experimental results, careful attention must be paid to the kinetics associated with the reactor to ensure that the transient behavior of the electronic device is understood. Since the ACRR fuel maintains a substantial amount of beryllium, copious quantities of photoneutrons are produced that can significantly alter the expected behavior of the reactor power, especially following a reactor pulse. In order to understand these photoneutron effects on the reactor kinetics, the KIFLE transient reactor-analysis code was modified to include the photoneutron groups associated with the beryllium. The time-dependent behavior of the reactor power was analyzed for small and large pulses, assuming several initial conditions including following several pulses during the day, and following a long steady-state power run. The results indicate that, for these types of initial conditions, the photoneutron contribution to the reactor pulse energy can have a few to tens of percent effect.

Authors:
Publication Date:
Research Org.:
Sandia National Laboratories
Sponsoring Org.:
USDOE
OSTI Identifier:
970262
Report Number(s):
SAND2009-2817
TRN: US1000950
DOE Contract Number:  
AC04-94AL85000
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACPR REACTOR; BERYLLIUM; EPITHERMAL NEUTRONS; IRRADIATION; KINETICS; NEUTRONS; PHOTONEUTRONS; PULSED REACTORS; REACTOR KINETICS; TRANSIENTS

Citation Formats

Parma, Jr, Edward J. Photoneutron effects on pulse reactor kinetics for the Annular Core Research Reactor (ACRR).. United States: N. p., 2009. Web. doi:10.2172/970262.
Parma, Jr, Edward J. Photoneutron effects on pulse reactor kinetics for the Annular Core Research Reactor (ACRR).. United States. https://doi.org/10.2172/970262
Parma, Jr, Edward J. Mon . "Photoneutron effects on pulse reactor kinetics for the Annular Core Research Reactor (ACRR).". United States. https://doi.org/10.2172/970262. https://www.osti.gov/servlets/purl/970262.
@article{osti_970262,
title = {Photoneutron effects on pulse reactor kinetics for the Annular Core Research Reactor (ACRR).},
author = {Parma, Jr, Edward J},
abstractNote = {The Annular Core Research Reactor (ACRR) is a swimming-pool type pulsed reactor that maintains an epithermal neutron flux and a nine-inch diameter central dry cavity. One of its uses is neutron and gamma-ray irradiation damage studies on electronic components under transient reactor power conditions. In analyzing the experimental results, careful attention must be paid to the kinetics associated with the reactor to ensure that the transient behavior of the electronic device is understood. Since the ACRR fuel maintains a substantial amount of beryllium, copious quantities of photoneutrons are produced that can significantly alter the expected behavior of the reactor power, especially following a reactor pulse. In order to understand these photoneutron effects on the reactor kinetics, the KIFLE transient reactor-analysis code was modified to include the photoneutron groups associated with the beryllium. The time-dependent behavior of the reactor power was analyzed for small and large pulses, assuming several initial conditions including following several pulses during the day, and following a long steady-state power run. The results indicate that, for these types of initial conditions, the photoneutron contribution to the reactor pulse energy can have a few to tens of percent effect.},
doi = {10.2172/970262},
url = {https://www.osti.gov/biblio/970262}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2009},
month = {6}
}