‘The measurement of thermal neutron flux depression for determining the concentration of boron in blood’—suggestions as to further development of the method
A Bolewski Jr; M Ciechanowski; A Dydejczyk
German National Library of Science and Technology (GetInfo) (German)
Yield of Neutrons per Interaction in U, Pb, W, and Sn by Protons of Six Energies between 250 and 900 Mev Selected from Cosmic Radiation
Bercovitch, M.; Carmichael, H.; Hanna, G. C.
Vessel and Channel Fast Reactors Cooled by Boiling Water or Water with Supercritical Parameters
Kuznetsov, Yu. N.; Reshetov, V. A.; Gabaraev, B. A.
Trace multielement analysis of reactor moderator water: Simultaneous determination of copper, gold, silver, and mercury using differential pulse stripping voltammetry
Almon, A. C.; Department of Energy, Washington, DC
Time-of-flight implementation of an ultra-small-angle neutron scattering instrument
Littrell, K. C.; Agamalian, M.; Rehm, Ch.
Thermal neutron transport near a moderator discontinuity using the method of weighted residuals: III. Temperature discontinuities in graphite and light water
T D Beynon; J R Moon
Thermal neutron transport near a moderator discontinuity using the method of weighted residuals - II. Cold neutron sources
J R Moon; T D Beynon
The neutron ‘thunder’ accompanying the extensive air shower
A D Erlykin
The First Water-Cooled Water-Moderated Critical Assemblies in the USSR
Nikol'skii, Yu. V.; Gladkov, G. A.
The Detector for Advanced Neutron Capture Experiments at LANSCE
Ullmann, J. L.; Reifarth, R.; Kaeppeler, F.
TMRS MK III engineering design
O'Toole, J.A.; Valicenti, R.A.; Woloshun, K.A.
Study of moderator thickness for an accelerator-based neutron irradiation facility for boron neutron capture therapy using the 7Li(p, n) reaction near threshold
Sergei Zimin; Barry J Allen
Stress Concentration Factors for Magnox Moderator Graphite
Lamb, M.; Royal Society of Chemistry (Great Britain); British Carbon Group
Steady-state thermal-hydraulic analysis of SCWR assembly
Cheng, Xu; Liu, Xiaojing
Square lattice honeycomb reactor for space power and propulsion
Gouw, Reza; Anghaie, Samim
Space- and angle-dependent steady-state thermal neutron spectra in finite water assemblies
S Garg; F Ahmed; L S Kothari
Site-site pair correlation functions of water from 25 to 400 °C: Revised analysis of new and old diffraction data
Ricci, M. A.; Soper, A. K.; Bruni, F.
Radiological Experience on Decontamination of Moderator and Associated System at NAPS # 1
Yadav, C. L. R.; Mitra, S. R.; Pawar, S. K.
Possibility of using the alternating nuclear engine with a ten per cent enriched uranium in the case of heavy water as moderator
Cristea, G.; Gheorghiu, E.
Plutonium Recycling in Pressurized Water Reactors: Influence of the Moderator-to-Fuel Ratio
Kloosterman, J. L.; Bende, E. E.
Parametric Study of LEU Particles in Water or a UO~2/Water Moderator
Erickson, D. G.; Toffer, H.
Oxidation performance of graphite material in reactors
Yu, Suyuan; Luo, Xiaowei; Yu, Xinli
Optimisation studies for a moderator on a pulsed neutron source
D J Picton; D K Ross; A D Taylor
On-Line Purification of Heavy Water Coolant/Moderator - Experience with Gel and Macroporous Resins
Bose, H.; Kumar, R.; Gandhi, H.C.
Noise Analysis Method for Monitoring the Moderator Temperature Coefficient of Pressurized Water Reactors: Neural Network Calibration
Thomas, J. R.; Adams, J. T.
Neutronic design of instrumentation for thermal effects measurement on VR-1 reactor
Bily, Tomas; Sklenka, Lubomir
Neutronic Studies of a Liquid Hydrogen-Water Composite Moderator
Tahara, T.; Iverson, E. B.; Crabtree, J. A.
Neutron-Proton Capture Cross Section
Stooksberry, Robert W.; Crouch, Marshall F.
Neutron source for Neutron Capture Synovectomy
Vega‐Carrillo, Héctor René; Manzanares‐Acun˜a, Eduardo
Method for Removing Gadolinium from Used Heavy Water Reactor Moderator
Wilde, E. W.; Berry, C. J.; Goli, M. B.
Measurement of the thermal neutron distribution in a water phantom using a cyclotron based neutron source for boron neutron capture therapy
Tanaka, H.; Sakurai, Y.; Suzuki, M.
Measurement of the neutron beam intensity from the KENS ambient temperature water moderator
Ino, T.; Yasui, S.; Ogawa, Y.
Measurement of the effective delayed-neutron dose by the α-Rossi method in water-containing media
Measurement of the Moderator Temperature Coefficient of Reactivity for Pressurized Water Reactors
Sung Sik Yu; Se Chong Kim; Young Whan Na
Measurement of Total Cross Sections at Pohang Neutron Facility
Kim, Guinyun; Ahmed, Hossain; Lee, Young Seok
Ion exchange resin degradation and carbon-14 emission control in CANDU moderator system
Caron, F.; Torok, J.; British Nuclear Energy Society
Impact of different moderator ratios with light and heavy water cooled reactors in equilibrium states
Permana, S.; Takaki, N.; Sekimoto, H.
ICONE18-29844 Analysis for Inverse Flow in Moderator Channels of Supercritical Water Cooled Reactor
Fu, S.; Xu, Z.; Yang, Y.
ICONE14-89392 Reactor Analysis for Counter-Flowing Moderator and Coolant in a Supercritical Water Reactor
Wilson, P. P. H.; Hu, P.
Horizontal Cold Source: Fluid Dynamics Tests on the Moderator Model in Water and Air Current
Hoffman, H.; Astruc, J. M.; Department of Energy, Washington, DC
Fate of Radionuclides in the Light Water Moderator of a Research Reactor
Fukui, M.; Yoshimoto, T.-A.; Okamoto, K.-I.
FEDSM2001-18061 Computations of Moderator Flows Inside Calandria of a Pressurized Heavy Water Reactor
Mandal, J. C.; Agrawal, L.; Marathe, A. G.
Environmental radioactivity in the ground water at the Gran Sasso National Laboratory (Italy): a possible contribution to the variation of the neutron flux background
Laubenstein, Matthias; Nisi, Stefano; Balata, Marco
Enhancing the moderator effectiveness as a heat sink during loss of coolant accidents in CANDU-PHW reactors using glass-peened surfaces
Nitheanandan, T.; Tiede, R. W.; Sanderson, D. B.
Effect of the use of a light water moderator upon the nuclear fuel concentration and of the geometric dimensions of the alternating nuclear engine
Cristea, G.; Gheorghiu, E.
Effect of Anisotropic Scattering in UO 2 and MOX Fueled LWR Cells and Cores
Takeda, Toshikazu; Inoue, Akira
Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores
Ama, T.; Ikeda, H.; Kosaka, S.
Distribution characteristics of 14 C and 3 H in spent resins from the Canada deuterium uranium-pressurized heavy water reactors (CANDU-PHWRs) of Korea
Kim, J.; Jee, K.; Park, S.
Direct-Flow Channel Reactor with Supercritical Coolant Pressure
Fedik, I.; Gavrilin, S.; Mityaev, Yu.
Diffusion Parameters of Thermal Neutrons in Water
von Dardel, G.; Sjöstrand, N. G.
Development of a standard for the moderator temperature coefficient of reactivity in water-moderated power reactors
Mosteller, R. D.; Department of Energy, Washington, DC
Development of a standard for calculation and measurement of the moderator temperature coefficient of reactivity in water-moderated power reactors
Mosteller, R. D.; Apperson, C. E.; Gavin, P. H.
Mosteller, R. D.; Hall, R. A.; Apperson, C. E.
Development of a noise-based method for the determination of the moderator temperature coefficient of reactivity (MTC) in pressurized water reactors (PWRs)
Development of a Standard for Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity in Water-Moderated Power Reactors
Mosteller, R. D.; Apperson, C. E.; Gavin, P. H.
Design of a supercritical water-cooled reactor - pressure vessel and internals
Design and Development of Rolled Joint for Moderator Sparger Channel of an Indian Pressurised Heavy Water Reactor
Joemon, V.; Sinha, R. K.; International Association for Structural Mechanics in Reactor Technology
Criticality Studies of a Natural Uranium Fuled, Light Water Cooled, Heavy Water Moderated Nuclear Reactor Part-II: Effect of Moderator Properties
Aslam; Malkawi, S. R.; Hamad, N. A.
Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents
Mochizuki, H.; Koike, M. H.; Sakai, T.
Core Coolability with Heavy Water Moderator of ATR in Situations Beyond the Design Basis Accidents
Computational study of moderator flow and temperature fields in the calandria vessel of a heavy water reactor using the PHOENICS code
Vaidya, A.M.; Maheshwari, N.K.; Vijayan, P.K.
Calculation of the moderator temperature coefficient of reactivity for water moderated reactors
Mourtzanos, K.; Housiadas, C.; Antonopoulos-Domis, M.
Basis for Interim Operation (BIO) for the Rework Unit (RW), Du Pont Water (DW) Plant, Moderator Processing Facility (MPF), and Technical Purification Facility (TPF)
Horne, R. E.; USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
Accounting for Moderator Heating in Supercritical Water Reactor Analysis
Wilson, P. P. H.; Hu, P.
Accelerators and Neutron Capture Therapy
Kreiner, A. J.; Burlon, A. A.; Valda, A.
A pulsed neutron source on the proton beam for the Moscow Meson Factory
Sadykov, R.; Kamanin, D.; Matushko, V.
A flashing driven moderator cooling system for CANDU reactors: Experimental and computational results
Khartabil, H. F.; International Atomic Energy Agency
A design study for an accelerator-based epithermal neutron beam for BNCT
D A Allen; T D Beynon
A Study of the Interaction of Neutrons with Moderating Materials
von Dardel, G. F.
7502 - Conceptual Design of 1400 MWe Supercritical Water Cooled Reactor Core Design with a Cruciform Type of U/Zr Solid Moderator
Bae, K.-M.; Joo, H.K.; Bae, Y.Y.
5235 - Fuel Channel Integrity and Moderator Behavior during a LOCA in Pressurized Heavy Water Reactor
Choi, J.H.; American Nuclear Society
Moderator temperature effect on reactivity in light water moderated experimental reactors
Mohapatra, D. K.; Mohanakrishnan, P.
Moderator Temperature Coefficient of Reactivity in Pressurized Water Reactors: Theoretical Investigation and Numerical Simulations
Antonopoulos-Domis, M.; Housiadas, C.
MODERATOR WORTH AND REACTIVITY CONTROL IN HEAVY WATER MODERATED NATURAL URANIUM FUELED REACTORS
Khan, M. J.; Aslam; Ahmad, N.
Website Policies and Important Links Comments
WorldWideScience.org is maintained by the
U.S. Department of Energy's
Office of Scientific and Technical Information as the Operating Agent
for the WorldWideScience Alliance.