1 | |
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2 | \begin{latexonly} |
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3 | |
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4 | \begin{thebibliography}{599} |
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5 | |
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6 | \bibitem{VH73} Vandenbosch R., Huizenga J. R., Nuclear Fission, Academic |
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7 | Press, New York, 1973. |
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8 | |
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9 | \bibitem{ABIM93} Adeev G. D. {\it et al.} Preprint INR 816/93, Moscow, 1993. |
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10 | |
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11 | \bibitem{VKW85} Viola V. E., Kwiatkowski K. and Walker M, Phys. Rev. |
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12 | {\bf C31} 1550 (1985). |
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13 | |
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14 | \bibitem{Terrell 1957} J. Terrell, "Distributions of Fission Neutron |
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15 | Numbers", \textit{Phys. Rev.} \textbf{108}, 783 (1957). |
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16 | |
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17 | \bibitem{Cullen 2006} D.E. Cullen, "Sampling the Number of Neutrons |
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18 | Emitted per Fission," UCRL-TR-222526, Lawrence Livermore National |
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19 | Laboratory (2006). |
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20 | |
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21 | \bibitem{Zucker and Holden 1986} M.S. Zucker, N.E. Holden, "Energy |
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22 | Dependence of Neutron Multiplicity P$_{\nu}$ in Fast-Neutron-Induced |
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23 | Fission for $^{235,238}U$ and $^{239}Pu$," BNL-38491 (1986). |
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24 | |
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25 | \bibitem{Gwin 1984} R. Gwin, R.R. Spencer, |
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26 | R.W. Ingle, "Measurements of the Energy Dependence of Prompt Neutron |
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27 | Emission from $^{233}U$, $^{235}U$, $^{239}Pu$, and $^{241}Pu$ for |
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28 | $E_n=0.005$ to 10 eV Relative to Emission from Spontaneous Fission of |
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29 | $^{252}$Cf," \textit{Nucl. Sci. Eng.}, \textbf{87}, 381 (1984). |
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30 | |
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31 | \bibitem{Valentine 1996} T.E. Valentine, J.T. Mihalczo, "MCNP-DSP: A |
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32 | Neutron and Gamma Ray Monte Carlo Calculation of Source-Driven |
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33 | Noise-Measured Parameters ," \textit{Ann. of Nucl. Eng.}, \textbf{23}, |
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34 | 16, p. 1271 (1996). |
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35 | |
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36 | \bibitem{Valentine 2000} T.E. Valentine, "MCNP-DSP Users Manual," |
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37 | ORNL/TM-13334, R2, Oak Ridge National Laboratory (2000). |
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38 | |
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39 | \bibitem{Frehaut 1988} J. Frehaut, "Neutron Multiplicity Distribution |
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40 | in Fast Neutron-Induced Fission," \textit{Proc. of IAEA Consultant's |
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41 | Meeting on Physics of Neutron Emission in Fission,}, Mito, Japan |
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42 | (1988). |
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43 | |
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44 | \bibitem{Spencer 1982} R.R. Spencer, R. Gwin, R.W. Ingle, "A |
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45 | measurement of the Average Number of Prompt Neutrons from Spontaneous |
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46 | Fission of Californium-252," \textit{Nucl. Sci. Eng.} \textbf{80}, 603 |
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47 | (1982). |
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48 | |
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49 | \bibitem{Boldeman 1985} J.W. Boldeman, M.G. Hines, "Prompt |
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50 | Neutron Emission Probabilities Following Spontaneous and Thermal |
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51 | Neutron Fission," \textit{Nucl. Sci. Eng.}, \textbf{91}, 114 (1985). |
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52 | |
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53 | \bibitem{Holden and Zucker BNL} N.E. Holden, |
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54 | M.S. Zucker, "A Reevaluation of the Average Prompt Neutron Emission |
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55 | Multiplicity ($\bar{\nu}$) Values from Fission of Uranium and |
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56 | Transuranium Nuclides," BNL-NCS-35513, Brookhaven National |
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57 | Laboratory). |
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58 | |
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59 | \bibitem{Ensslin 1998} N. Ensslin, W.C. Harker, M.S. Krick, |
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60 | D.G. Langner, M.M. Pickrell, J.E. Stewart, "Application Guide to |
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61 | Neutron Multiplicity Counting," LA-13422-M, Los Alamos National |
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62 | Laboratory (1998). |
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63 | |
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64 | \bibitem{ENDL 1975} R.J. Howerton, et al, "The LLL |
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65 | Evaluated Nuclear Data Library (ENDL): Evaluation Techniques, Reaction |
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66 | Index, and Description of Individual Evaluations," UCRL-50400, V. 15, |
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67 | Part A, Lawrence Livermore National Laboratory (1975). |
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68 | |
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69 | \bibitem{TART 2003} D.E. Cullen, "TART 2002: A Couple |
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70 | Neutron-Photon 3-D, Combinatorial Geometry, Time Dependent Monte-Carlo |
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71 | Transport Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National |
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72 | Laboratory (2003). |
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73 | |
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74 | \bibitem{Cullen 2004} D.E. Cullen, "Sampling ENDL Watt Fission |
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75 | Spectra," UCRL-TR-203251, Lawrence Livermore National Laboratory |
---|
76 | (2004). |
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77 | |
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78 | \bibitem{Everett 1983} C.J. Everett, E.D. Cashwell, "A Third |
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79 | Monte Carlo Sampler," LA-9721-MS, Los Alamos National Laboratory |
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80 | (1983). |
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81 | |
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82 | \bibitem{Mannhart 1987} W. Mannhart, "Evaluation |
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83 | of the Cf-252 Fission Neutron Spectrum Between 0 MeV and 20 MeV," |
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84 | \textit{Proc. Advisory Group Mtg. Neutron Sources}, Leningrad, USSR, |
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85 | 1986 (IAEA-TECDOC-410), Vienna (1987). |
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86 | |
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87 | \bibitem{Madland 1984} |
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88 | D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and Average |
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89 | Prompt Neutron Multiplicities,"NEANDC Specialist's Meeting on Yields |
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90 | and Decay Data of Fission Products, Brookhaven National Laboratory, |
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91 | BNL 51778 (1984). |
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92 | |
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93 | \bibitem{Froehner 1990} F.H. Fr\"{o}hner, |
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94 | "Evaluation of $^{252}$Cf Prompt Fission Neutron Data from 0 to 20 MeV |
---|
95 | by Watt Spectrum Fit," \textit{Nucl. Sci. Eng.} \textbf{106}, 345 |
---|
96 | (1990). |
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97 | |
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98 | \bibitem{Brunson 1982} G.S. Brunson, Jr., "Multiplicity and |
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99 | Correlated Energy of Gamma Rays Emitted in the Spontaneous Fission of |
---|
100 | Californium-252," Ph.D. Thesis, University of Utah (1982). |
---|
101 | |
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102 | \bibitem{Valentine 2001} T.E. Valentine, "Evaluation of Prompt Fission |
---|
103 | Gamma Rays for Use in Simulating Nuclear Safeguard Measurements," |
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104 | \textit{Ann. Nucl. Eng.}, \textbf{28}, 191 (2001). |
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105 | |
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106 | \bibitem{Wagemans |
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107 | 1991} C. Wagemans, "The Nuclear Fission Process," \textit{CRC Press, |
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108 | Inc.,} Boca Raton, Florida (1991). |
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109 | |
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110 | \bibitem{Maienschein 1958} |
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111 | F.C. Maienschein, R.W. Peelle, T.A. Love, \textit{Neutron |
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112 | Phys. Ann. Prog. Rep. for Sept. 1, 1958}, ORNL-2609, Oak Ridge |
---|
113 | National Laboratory (1958). |
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114 | |
---|
115 | \bibitem{Goldstein 1959} "Fundamental |
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116 | Aspects of Reactor Shielding," Addison-Wesley Publishing Company, |
---|
117 | Inc. Reading, Massachussetts (1959). |
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118 | |
---|
119 | \end{thebibliography} |
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120 | |
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121 | \end{latexonly} |
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122 | |
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123 | |
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124 | \begin{htmlonly} |
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125 | |
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126 | \section{Bibliography} |
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127 | |
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128 | \begin{enumerate} |
---|
129 | \item Vandenbosch R., Huizenga J. R., Nuclear Fission, Academic |
---|
130 | Press, New York, 1973. |
---|
131 | |
---|
132 | \item Adeev G. D. {\it et al.} Preprint INR 816/93, Moscow, 1993. |
---|
133 | |
---|
134 | \item Viola V. E., Kwiatkowski K. and Walker M, Phys. Rev. |
---|
135 | {\bf C31} 1550 (1985). |
---|
136 | |
---|
137 | \item{Terrell 1957} J. Terrell, "Distributions of Fission Neutron |
---|
138 | Numbers", \textit{Phys. Rev.} \textbf{108}, 783 (1957). |
---|
139 | |
---|
140 | \item{Cullen 2006} D.E. Cullen, "Sampling the Number of Neutrons |
---|
141 | Emitted per Fission," UCRL-TR-222526, Lawrence Livermore National |
---|
142 | Laboratory (2006). |
---|
143 | |
---|
144 | \item{Zucker and Holden 1986} M.S. Zucker, N.E. Holden, "Energy |
---|
145 | Dependence of Neutron Multiplicity P$_{\nu}$ in Fast-Neutron-Induced |
---|
146 | Fission for $^{235,238}U$ and $^{239}Pu$," BNL-38491 (1986). |
---|
147 | |
---|
148 | \item{Gwin 1984} R. Gwin, R.R. Spencer, |
---|
149 | R.W. Ingle, "Measurements of the Energy Dependence of Prompt Neutron |
---|
150 | Emission from $^{233}U$, $^{235}U$, $^{239}Pu$, and $^{241}Pu$ for |
---|
151 | $E_n=0.005$ to 10 eV Relative to Emission from Spontaneous Fission of |
---|
152 | $^{252}$Cf," \textit{Nucl. Sci. Eng.}, \textbf{87}, 381 (1984). |
---|
153 | |
---|
154 | \item{Valentine 1996} T.E. Valentine, J.T. Mihalczo, "MCNP-DSP: A |
---|
155 | Neutron and Gamma Ray Monte Carlo Calculation of Source-Driven |
---|
156 | Noise-Measured Parameters ," \textit{Ann. of Nucl. Eng.}, \textbf{23}, |
---|
157 | 16, p. 1271 (1996). |
---|
158 | |
---|
159 | \item{Valentine 2000} T.E. Valentine, "MCNP-DSP Users Manual," |
---|
160 | ORNL/TM-13334, R2, Oak Ridge National Laboratory (2000). |
---|
161 | |
---|
162 | \item{Frehaut 1988} J. Frehaut, "Neutron Multiplicity Distribution |
---|
163 | in Fast Neutron-Induced Fission," \textit{Proc. of IAEA Consultant's |
---|
164 | Meeting on Physics of Neutron Emission in Fission,}, Mito, Japan |
---|
165 | (1988). |
---|
166 | |
---|
167 | |
---|
168 | \item{Spencer 1982} R.R. Spencer, R. Gwin, R.W. Ingle, "A |
---|
169 | measurement of the Average Number of Prompt Neutrons from Spontaneous |
---|
170 | Fission of Californium-252," \textit{Nucl. Sci. Eng.} \textbf{80}, 603 |
---|
171 | (1982). |
---|
172 | |
---|
173 | \item{Boldeman 1985} J.W. Boldeman, M.G. Hines, "Prompt |
---|
174 | Neutron Emission Probabilities Following Spontaneous and Thermal |
---|
175 | Neutron Fission," \textit{Nucl. Sci. Eng.}, \textbf{91}, 114 (1985). |
---|
176 | |
---|
177 | \item{Holden and Zucker BNL} N.E. Holden, |
---|
178 | M.S. Zucker, "A Reevaluation of the Average Prompt Neutron Emission |
---|
179 | Multiplicity ($\bar{\nu}$) Values from Fission of Uranium and |
---|
180 | Transuranium Nuclides," BNL-NCS-35513, Brookhaven National |
---|
181 | Laboratory). |
---|
182 | |
---|
183 | \item{Ensslin 1998} N. Ensslin, W.C. Harker, M.S. Krick, |
---|
184 | D.G. Langner, M.M. Pickrell, J.E. Stewart, "Application Guide to |
---|
185 | Neutron Multiplicity Counting," LA-13422-M, Los Alamos National |
---|
186 | Laboratory (1998). |
---|
187 | |
---|
188 | \item{ENDL 1975} R.J. Howerton, et al, "The LLL |
---|
189 | Evaluated Nuclear Data Library (ENDL): Evaluation Techniques, Reaction |
---|
190 | Index, and Description of Individual Evaluations," UCRL-50400, V. 15, |
---|
191 | Part A, Lawrence Livermore National Laboratory (1975). |
---|
192 | |
---|
193 | \item{TART 2003} D.E. Cullen, "TART 2002: A Couple |
---|
194 | Neutron-Photon 3-D, Combinatorial Geometry, Time Dependent Monte-Carlo |
---|
195 | Transport Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National |
---|
196 | Laboratory (2003). |
---|
197 | |
---|
198 | \item{Cullen 2004} D.E. Cullen, "Sampling ENDL Watt Fission |
---|
199 | Spectra," UCRL-TR-203251, Lawrence Livermore National Laboratory |
---|
200 | (2004). |
---|
201 | |
---|
202 | \item{Everett 1983} C.J. Everett, E.D. Cashwell, "A Third |
---|
203 | Monte Carlo Sampler," LA-9721-MS, Los Alamos National Laboratory |
---|
204 | (1983). |
---|
205 | |
---|
206 | |
---|
207 | \item{Mannhart 1987} W. Mannhart, "Evaluation |
---|
208 | of the Cf-252 Fission Neutron Spectrum Between 0 MeV and 20 MeV," |
---|
209 | \textit{Proc. Advisory Group Mtg. Neutron Sources}, Leningrad, USSR, |
---|
210 | 1986 (IAEA-TECDOC-410), Vienna (1987). |
---|
211 | |
---|
212 | \item{Madland 1984} |
---|
213 | D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and Average |
---|
214 | Prompt Neutron Multiplicities,"NEANDC Specialist's Meeting on Yields |
---|
215 | and Decay Data of Fission Products, Brookhaven National Laboratory, |
---|
216 | BNL 51778 (1984). |
---|
217 | |
---|
218 | \item{Froehner 1990} F.H. Fr\"{o}hner, |
---|
219 | "Evaluation of $^{252}$Cf Prompt Fission Neutron Data from 0 to 20 MeV |
---|
220 | by Watt Spectrum Fit," \textit{Nucl. Sci. Eng.} \textbf{106}, 345 |
---|
221 | (1990). |
---|
222 | |
---|
223 | \item{Brunson 1982} G.S. Brunson, Jr., "Multiplicity and |
---|
224 | Correlated Energy of Gamma Rays Emitted in the Spontaneous Fission of |
---|
225 | Californium-252," Ph.D. Thesis, University of Utah (1982). |
---|
226 | |
---|
227 | \item{Valentine 2001} T.E. Valentine, "Evaluation of Prompt Fission |
---|
228 | Gamma Rays for Use in Simulating Nuclear Safeguard Measurements," |
---|
229 | \textit{Ann. Nucl. Eng.}, \textbf{28}, 191 (2001). |
---|
230 | |
---|
231 | \item{Wagemans |
---|
232 | 1991} C. Wagemans, "The Nuclear Fission Process," \textit{CRC Press, |
---|
233 | Inc.,} Boca Raton, Florida (1991). |
---|
234 | |
---|
235 | \item{Maienschein 1958} |
---|
236 | F.C. Maienschein, R.W. Peelle, T.A. Love, \textit{Neutron |
---|
237 | Phys. Ann. Prog. Rep. for Sept. 1, 1958}, ORNL-2609, Oak Ridge |
---|
238 | National Laboratory (1958). |
---|
239 | |
---|
240 | \item{Goldstein 1959} "Fundamental |
---|
241 | Aspects of Reactor Shielding," Addison-Wesley Publishing Company, |
---|
242 | Inc. Reading, Massachussetts (1959). |
---|
243 | |
---|
244 | \end{enumerate} |
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245 | |
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246 | \end{htmlonly} |
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247 | |
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