A proposed MAPLE source replacement for the McMaster Nuclear Reactor

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society, Supplement; (USA)

OSTI ID:5227412

Lee, A G; Lidstone, R F; Gillespie, G E; Ernst, P C

The McMaster nuclear reactor (MNR) is a swimming pool reactor manufactured by AMF Atomics in the late 1950s. Licensed to operate at up to 5 MW of power, MNR is primarily used for research programs employing extracted neutron beams for neutron scattering experiments and for neutron activation analysis. Isotopes, such as {sup 18}F, are also produced for research and medical purposes. The present neutron source uses standard light-water-cooled, -moderated, and -reflected materials test reactor plate-type fuel shielded by the pool water and 2 m of barite concrete located in a concrete containment building. At 5-MW operating power the perturbed thermal flux at a beam tube nose is {approximately}5 {times} 10{sup 12} n/cm{sup 2}{center dot}S. This neutronic performance is inadequate for many extracted-beam programs. The neutron fluxes externally available are limited by the relatively large volume of the core and by the light water reflector. Since the radial beam tubes have a relatively high gamma and fast neutron component, the thermal flux from them may also be further limited by the need for filtration. In order to enhance this available thermal flux, it is proposed that the current core be replaced by a MAPLE-10 reactor core and reflector tank. As the MNR facilities, pool, containment building, primary cooling system, and secondary cooling system are in excellent condition, it is feasible to achieve this flux enhancement by replacing just the reactor structure and control system with a MAPLE-10 reactor structure and control system.

• OSTI ID: 5227412
• Report Number(s): CONF-890833--
• Conference Information: Journal Name: Transactions of the American Nuclear Society, Supplement; (USA) Journal Volume: 59
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACTINIDE COMPOUNDS
ACTINIDES
ACTIVATION ANALYSIS
BUILDING MATERIALS
CHEMICAL ANALYSIS
CONCRETES
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
DESIGN
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
IRRADIATION REACTORS
ISOTOPE ENRICHED MATERIALS
ISOTOPE PRODUCTION REACTORS
MATERIALS
METALS
MNR REACTOR
MODERATELY ENRICHED URANIUM
MODIFICATIONS
NEUTRON REFLECTORS
POOL TYPE REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SCATTERING
SILICIDES
SILICON COMPOUNDS
URANIUM
URANIUM COMPOUNDS
URANIUM SILICIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS