AQUEOUS HOMOGENEOUS REACTORTECHNICAL PANEL REPORT

Diamond, D.J. ; Bajorek, S. ; Bakel, A. ; Flanagan, G. ; Mubayi, V. ; Skarda, R. ; Staudenmeier, J. ; Taiwo, T. ; Tonoike, K. ; Tripp, C. ; Wei, T. ; Yarsky, P.

Brookhaven National Laboratory

关键词: Uranium Aqueous;    Management;    Nuclear Medicine;    Aqueous Homogeneous Reactors;    Capacity;   

DOI  :  10.2172/1013523
RP-ID  :  BNL--94462-2010
RP-ID  :  DE-AC02-98CH10886
RP-ID  :  1013523

美国|英语

来源: UNT Digital Library

【 摘 要 】

Considerable interest has been expressed for developing a stable U.S. production capacity for medical isotopes and particularly for molybdenum- 99 (99Mo). This is motivated by recent re-ductions in production and supply worldwide. Consistent with U.S. nonproliferation objectives, any new production capability should not use highly enriched uranium fuel or targets. Conse-quently, Aqueous Homogeneous Reactors (AHRs) are under consideration for potential 99Mo production using low-enriched uranium. Although the Nuclear Regulatory Commission (NRC) has guidance to facilitate the licensing process for non-power reactors, that guidance is focused on reactors with fixed, solid fuel and hence, not applicable to an AHR. A panel was convened to study the technical issues associated with normal operation and potential transients and accidents of an AHR that might be designed for isotope production. The panel has produced the requisite AHR licensing guidance for three chapters that exist now for non-power reactor licensing: Reac-tor Description, Reactor Coolant Systems, and Accident Analysis. The guidance is in two parts for each chapter: 1) standard format and content a licensee would use and 2) the standard review plan the NRC staff would use. This guidance takes into account the unique features of an AHR such as the fuel being in solution; the fission product barriers being the vessel and attached systems; the production and release of radiolytic and fission product gases and their impact on operations and their control by a gas management system; and the movement of fuel into and out of the reactor vessel.