Safety analysis for operating the Annular Core Research Reactor with Cintichem-type targets installed in the central region of the core

Parma,; Edward, J

doi:10.2172/750880

Cited by 3 publications

(4 citation statements)

References 4 publications

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“…It can be shown (Ref. 21) that reactor yield should follow a concave upward parabolic curve based on a Fuchs-Nordheim analysis assuming the fuel Doppler reactivity feedback to be inversely proportional to the square root of the fuel temperature. With this in mind, it appears that the yield results for the 2016 pulses may be trending toward a concave downward parabolic curve.…”

Section: Predicted Reactor Yieldmentioning

confidence: 99%

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RAZORBACK - A Research Reactor Transient Analysis Code Version 1.0 - Volume 3: Verification and Validation Report.

Talley

2017

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This report describes the work and results of the verification and validation (V&V) of the version 1.0 release of the Razorback code. Razorback is a computer code designed to simulate the operation of a research reactor (such as the Annular Core Research Reactor (ACRR)) by a coupled numerical solution of the point reactor kinetics equations, the energy conservation equation for fuel element heat transfer, the equation of motion for fuel element thermal expansion, and the mass, momentum, and energy conservation equations for the water cooling of the fuel elements. This V&V effort was intended to confirm that the code shows good agreement between simulation and actual ACRR operations.

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Section: Predicted Reactor Yieldmentioning

confidence: 99%

“…. The analyses in Ref 21. which were used to produce the correlation were performed using the CYLSS code (Ref 22),.…”

mentioning

confidence: 99%

RAZORBACK - A Research Reactor Transient Analysis Code Version 1.0 - Volume 3: Verification and Validation Report.

Talley

2017

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“…Modifications to the ACRR have also been made for the previous medical isotope program and for other programs (Ref. 15,17). Both the reactor control system and rod drive system were also designed and implemented by SNL staff.…”

Section: Reactor Design Basismentioning

confidence: 99%

Sandia National Laboratories Medical Isotope Reactor concept.

Coats¹,

Dahl²,

Parma³

2010

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This report describes the Sandia National Laboratories Medical Isotope Reactor and hot cell facility concepts. The reactor proposed is designed to be capable of producing 100% of the U.S. demand for the medical isotope 99 Mo. The concept is novel in that the fuel for the reactor and the targets for the 99 Mo production are the same. There is no driver core required. The fuel pins that are in the reactor core are processed on a 7 to 21 day irradiation cycle. The fuel is low enriched uranium oxide enriched to less than 20% 235 U. The fuel pins are approximately 1 cm in diameter and 30 to 40 cm in height, clad with Zircaloy (zirconium alloy). Approximately 90 to 150 fuel pins are arranged in the core in a water pool ~30 ft deep. The reactor power level is 1 to 2 MW. The reactor concept is a simple design that is passively safe and maintains negative reactivity coefficients. The total radionuclide inventory in the reactor core is minimized since the fuel/target pins are removed and processed after 7 to 21 days. The fuel fabrication, reactor design and operation, and 99 Mo production processing use well-developed technologies that minimize the technological and licensing risks. There are no impediments that prevent this type of reactor, along with its collocated hot cell facility, from being designed, fabricated, and licensed today.4

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“…The computer code, KIFLHE, is a transient reactor-analysis code used to analyze ACRR power transients under pulsed and steady-state conditions. KIFLHE has been used extensively to study reactivity transients and accident conditions for the ACRR (Parma, 2000;Naegeli, 1999;Naegeli, 2000). The code solves the point-reactor kinetics equations, two-dimensional heat transfer (R-Z) in a fuel element, and one-dimensional fluid flow (Z) in a flow channel.…”

Section: Analysis Approachmentioning

confidence: 99%

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

Parma¹

2009

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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.

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Safety analysis for operating the Annular Core Research Reactor with Cintichem-type targets installed in the central region of the core

Abstract: Portions of this document may be illegible in electronic image products.Images are produced from the best available original document.

Cited by 3 publications

References 4 publications

RAZORBACK - A Research Reactor Transient Analysis Code Version 1.0 - Volume 3: Verification and Validation Report.

RAZORBACK - A Research Reactor Transient Analysis Code Version 1.0 - Volume 3: Verification and Validation Report.

Sandia National Laboratories Medical Isotope Reactor concept.

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

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