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1
2\begin{latexonly}
3
4\begin{thebibliography}{599}
5
6\bibitem{VH73} Vandenbosch R., Huizenga J. R., Nuclear Fission, Academic
7Press, New York, 1973.
8
9\bibitem{ABIM93} Adeev G. D. {\it et al.} Preprint INR 816/93, Moscow, 1993.
10
11\bibitem{VKW85} Viola V. E., Kwiatkowski K. and Walker M, Phys. Rev.
12{\bf C31} 1550 (1985).
13
14\bibitem{Terrell 1957} J. Terrell, "Distributions of Fission Neutron
15Numbers", \textit{Phys. Rev.} \textbf{108}, 783 (1957).
16
17\bibitem{Cullen 2006} D.E. Cullen, "Sampling the Number of Neutrons
18Emitted per Fission," UCRL-TR-222526, Lawrence Livermore National
19Laboratory (2006).
20
21\bibitem{Zucker and Holden 1986} M.S. Zucker, N.E. Holden, "Energy
22Dependence of Neutron Multiplicity P$_{\nu}$ in Fast-Neutron-Induced
23Fission for $^{235,238}U$ and $^{239}Pu$," BNL-38491 (1986).
24
25\bibitem{Gwin 1984} R. Gwin, R.R. Spencer,
26R.W. Ingle, "Measurements of the Energy Dependence of Prompt Neutron
27Emission from $^{233}U$, $^{235}U$, $^{239}Pu$, and $^{241}Pu$ for
28$E_n=0.005$ to 10 eV Relative to Emission from Spontaneous Fission of
29$^{252}$Cf," \textit{Nucl. Sci. Eng.}, \textbf{87}, 381 (1984).
30
31\bibitem{Valentine 1996} T.E. Valentine, J.T. Mihalczo, "MCNP-DSP: A
32Neutron and Gamma Ray Monte Carlo Calculation of Source-Driven
33Noise-Measured Parameters ," \textit{Ann. of Nucl. Eng.}, \textbf{23},
3416, p. 1271 (1996).
35
36\bibitem{Valentine 2000} T.E. Valentine, "MCNP-DSP Users Manual,"
37ORNL/TM-13334, R2, Oak Ridge National Laboratory (2000).
38
39\bibitem{Frehaut 1988} J. Frehaut, "Neutron Multiplicity Distribution
40in Fast Neutron-Induced Fission," \textit{Proc. of IAEA Consultant's
41Meeting on Physics of Neutron Emission in Fission,}, Mito, Japan
42(1988).
43
44\bibitem{Spencer 1982} R.R. Spencer, R. Gwin, R.W. Ingle, "A
45measurement of the Average Number of Prompt Neutrons from Spontaneous
46Fission of Californium-252," \textit{Nucl. Sci. Eng.} \textbf{80}, 603
47(1982).
48
49\bibitem{Boldeman 1985} J.W. Boldeman, M.G. Hines, "Prompt
50Neutron Emission Probabilities Following Spontaneous and Thermal
51Neutron Fission," \textit{Nucl. Sci. Eng.}, \textbf{91}, 114 (1985).
52
53\bibitem{Holden and Zucker BNL} N.E. Holden,
54M.S. Zucker, "A Reevaluation of the Average Prompt Neutron Emission
55Multiplicity ($\bar{\nu}$) Values from Fission of Uranium and
56Transuranium Nuclides," BNL-NCS-35513, Brookhaven National
57Laboratory).
58
59\bibitem{Ensslin 1998} N. Ensslin, W.C. Harker, M.S. Krick,
60D.G. Langner, M.M. Pickrell, J.E. Stewart, "Application Guide to
61Neutron Multiplicity Counting," LA-13422-M, Los Alamos National
62Laboratory (1998).
63
64\bibitem{ENDL 1975} R.J. Howerton, et al, "The LLL
65Evaluated Nuclear Data Library (ENDL): Evaluation Techniques, Reaction
66Index, and Description of Individual Evaluations," UCRL-50400, V. 15,
67Part A, Lawrence Livermore National Laboratory (1975).
68
69\bibitem{TART 2003} D.E. Cullen, "TART 2002: A Couple
70Neutron-Photon 3-D, Combinatorial Geometry, Time Dependent Monte-Carlo
71Transport Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National
72Laboratory (2003).
73
74\bibitem{Cullen 2004} D.E. Cullen, "Sampling ENDL Watt Fission
75Spectra," UCRL-TR-203251, Lawrence Livermore National Laboratory
76(2004).
77
78\bibitem{Everett 1983} C.J. Everett, E.D. Cashwell, "A Third
79Monte Carlo Sampler," LA-9721-MS, Los Alamos National Laboratory
80(1983).
81
82\bibitem{Mannhart 1987} W. Mannhart, "Evaluation
83of the Cf-252 Fission Neutron Spectrum Between 0 MeV and 20 MeV,"
84\textit{Proc. Advisory Group Mtg. Neutron Sources}, Leningrad, USSR,
851986 (IAEA-TECDOC-410), Vienna (1987).
86
87\bibitem{Madland 1984}
88D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and Average
89Prompt Neutron Multiplicities,"NEANDC Specialist's Meeting on Yields
90and Decay Data of Fission Products, Brookhaven National Laboratory,
91BNL 51778 (1984).
92
93\bibitem{Froehner 1990} F.H. Fr\"{o}hner,
94"Evaluation of $^{252}$Cf Prompt Fission Neutron Data from 0 to 20 MeV
95by Watt Spectrum Fit," \textit{Nucl. Sci. Eng.} \textbf{106}, 345
96(1990).
97
98\bibitem{Brunson 1982} G.S. Brunson, Jr., "Multiplicity and
99Correlated Energy of Gamma Rays Emitted in the Spontaneous Fission of
100Californium-252," Ph.D. Thesis, University of Utah (1982).
101
102\bibitem{Valentine 2001} T.E. Valentine, "Evaluation of Prompt Fission
103Gamma Rays for Use in Simulating Nuclear Safeguard Measurements,"
104\textit{Ann. Nucl. Eng.}, \textbf{28}, 191 (2001).
105
106\bibitem{Wagemans
1071991} C. Wagemans, "The Nuclear Fission Process," \textit{CRC Press,
108Inc.,} Boca Raton, Florida (1991).
109
110\bibitem{Maienschein 1958}
111F.C. Maienschein, R.W. Peelle, T.A. Love, \textit{Neutron
112Phys. Ann. Prog. Rep. for Sept. 1, 1958}, ORNL-2609, Oak Ridge
113National Laboratory (1958).
114
115\bibitem{Goldstein 1959} "Fundamental
116Aspects of Reactor Shielding," Addison-Wesley Publishing Company,
117Inc. Reading, Massachussetts (1959).
118
119\end{thebibliography}
120
121\end{latexonly}
122
123
124\begin{htmlonly}
125
126\section{Bibliography}
127
128\begin{enumerate}
129\item Vandenbosch R., Huizenga J. R., Nuclear Fission, Academic
130Press, 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
138Numbers", \textit{Phys. Rev.} \textbf{108}, 783 (1957).
139
140\item{Cullen 2006} D.E. Cullen, "Sampling the Number of Neutrons
141Emitted per Fission," UCRL-TR-222526, Lawrence Livermore National
142Laboratory (2006).
143
144\item{Zucker and Holden 1986} M.S. Zucker, N.E. Holden, "Energy
145Dependence of Neutron Multiplicity P$_{\nu}$ in Fast-Neutron-Induced
146Fission for $^{235,238}U$ and $^{239}Pu$," BNL-38491 (1986).
147
148\item{Gwin 1984} R. Gwin, R.R. Spencer,
149R.W. Ingle, "Measurements of the Energy Dependence of Prompt Neutron
150Emission 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
155Neutron and Gamma Ray Monte Carlo Calculation of Source-Driven
156Noise-Measured Parameters ," \textit{Ann. of Nucl. Eng.}, \textbf{23},
15716, p. 1271 (1996).
158
159\item{Valentine 2000} T.E. Valentine, "MCNP-DSP Users Manual,"
160ORNL/TM-13334, R2, Oak Ridge National Laboratory (2000).
161
162\item{Frehaut 1988} J. Frehaut, "Neutron Multiplicity Distribution
163in Fast Neutron-Induced Fission," \textit{Proc. of IAEA Consultant's
164Meeting 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
169measurement of the Average Number of Prompt Neutrons from Spontaneous
170Fission of Californium-252," \textit{Nucl. Sci. Eng.} \textbf{80}, 603
171(1982).
172
173\item{Boldeman 1985} J.W. Boldeman, M.G. Hines, "Prompt
174Neutron Emission Probabilities Following Spontaneous and Thermal
175Neutron Fission," \textit{Nucl. Sci. Eng.}, \textbf{91}, 114 (1985).
176
177\item{Holden and Zucker BNL} N.E. Holden,
178M.S. Zucker, "A Reevaluation of the Average Prompt Neutron Emission
179Multiplicity ($\bar{\nu}$) Values from Fission of Uranium and
180Transuranium Nuclides," BNL-NCS-35513, Brookhaven National
181Laboratory).
182
183\item{Ensslin 1998} N. Ensslin, W.C. Harker, M.S. Krick,
184D.G. Langner, M.M. Pickrell, J.E. Stewart, "Application Guide to
185Neutron Multiplicity Counting," LA-13422-M, Los Alamos National
186Laboratory (1998).
187
188\item{ENDL 1975} R.J. Howerton, et al, "The LLL
189Evaluated Nuclear Data Library (ENDL): Evaluation Techniques, Reaction
190Index, and Description of Individual Evaluations," UCRL-50400, V. 15,
191Part A, Lawrence Livermore National Laboratory (1975).
192
193\item{TART 2003} D.E. Cullen, "TART 2002: A Couple
194Neutron-Photon 3-D, Combinatorial Geometry, Time Dependent Monte-Carlo
195Transport Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National
196Laboratory (2003).
197
198\item{Cullen 2004} D.E. Cullen, "Sampling ENDL Watt Fission
199Spectra," UCRL-TR-203251, Lawrence Livermore National Laboratory
200(2004).
201
202\item{Everett 1983} C.J. Everett, E.D. Cashwell, "A Third
203Monte Carlo Sampler," LA-9721-MS, Los Alamos National Laboratory
204(1983).
205
206
207\item{Mannhart 1987} W. Mannhart, "Evaluation
208of the Cf-252 Fission Neutron Spectrum Between 0 MeV and 20 MeV,"
209\textit{Proc. Advisory Group Mtg. Neutron Sources}, Leningrad, USSR,
2101986 (IAEA-TECDOC-410), Vienna (1987).
211
212\item{Madland 1984}
213D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and Average
214Prompt Neutron Multiplicities,"NEANDC Specialist's Meeting on Yields
215and Decay Data of Fission Products, Brookhaven National Laboratory,
216BNL 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
220by Watt Spectrum Fit," \textit{Nucl. Sci. Eng.} \textbf{106}, 345
221(1990).
222
223\item{Brunson 1982} G.S. Brunson, Jr., "Multiplicity and
224Correlated Energy of Gamma Rays Emitted in the Spontaneous Fission of
225Californium-252," Ph.D. Thesis, University of Utah (1982).
226
227\item{Valentine 2001} T.E. Valentine, "Evaluation of Prompt Fission
228Gamma Rays for Use in Simulating Nuclear Safeguard Measurements,"
229\textit{Ann. Nucl. Eng.}, \textbf{28}, 191 (2001).
230
231\item{Wagemans
2321991} C. Wagemans, "The Nuclear Fission Process," \textit{CRC Press,
233Inc.,} Boca Raton, Florida (1991).
234
235\item{Maienschein 1958}
236F.C. Maienschein, R.W. Peelle, T.A. Love, \textit{Neutron
237Phys. Ann. Prog. Rep. for Sept. 1, 1958}, ORNL-2609, Oak Ridge
238National Laboratory (1958).
239
240\item{Goldstein 1959} "Fundamental
241Aspects of Reactor Shielding," Addison-Wesley Publishing Company,
242Inc. Reading, Massachussetts (1959).
243
244\end{enumerate}
245
246\end{htmlonly}
247
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