科技报告详细信息
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.
关键词: 07 ISOTOPES AND RADIATION SOURCES;    ACCIDENTS;    AQUEOUS HOMOGENEOUS REACTORS;    CAPACITY;    FISSION PRODUCTS;    SLIGHTLY ENRICHED URANIUM;    ISOTOPE PRODUCTION;    LICENSING PROCEDURES;    NUCLEAR MEDICINE;    REACTOR LICE;   
DOI  :  10.2172/1013523
RP-ID  :  BNL--94462-2010
PID  :  OSTI ID: 1013523
Others  :  R&D Project: 15456
Others  :  Other: 401001060
Others  :  TRN: US1102679
美国|英语
来源: SciTech Connect
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【 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.

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