<p>In recent years, the rapid development of nuclear technology and large-scale scientific facilities has imposed stringent requirements on radiation protection systems for monitoring high-energy neutron doses up to several hundred MeV. Conventional energy-response-based neutron dose-equivalent meters typically have an upper measurement limit below 20&#xa0;MeV and therefore cannot adequately cover broad-spectrum neutron fields. To address this limitation, the present study employs the neutron fluence-to-dose-equivalent conversion coefficients recommended in ICRP Publication 74 and uses the Geant4 code to optimize the probe design of a neutron dose-equivalent meter. By systematically adjusting the polyethylene moderator thickness, the position of the cadmium absorber layer and the thickness of the lead compensating layer, and by introducing air channels to improve the response to thermal and intermediate-energy neutrons, a wide-energy-range neutron dose-equivalent meter with an upper measurement limit of 200&#xa0;MeV is developed. Simulation results demonstrate that, over the energy range from 2.53 × 10⁻⁸&#xa0;MeV to 200&#xa0;MeV, the relative energy response of the optimized design remains within the conventional factor-of-two tolerance band. Furthermore, spectrum-based validation was performed by placing the optimized probe in a ²⁵²Cf spontaneous-fission neutron field and in a secondary mixed neutron field produced by a 200&#xa0;MeV clinical proton beam striking a target; the indicated dose agreed with the reference true dose within a relative deviation of about 15.5%, satisfying the IEC 61005 requirement that the relative error should not exceed 20%.</p>